Text

Ginna Station Annual Report #11, Jan 1, 1975 to Dec 31, 1975 Inclusive
	ML18142A599
Person / Time
Site:	Ginna
Issue date:	12/31/1975
From:	; Rochester Gas & Electric Corp
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML18142A599 (711)
	v • d • e

ROCHESTER GAS & ELECTRIC CORPORATION GINNA STATION ANNUAL REPORT 811 JANUARY 1 1975 TO DECEMBER 31 1975 INCLUSIVE DOCKET 850-244

TABLE OF CONTENTS TECHNICAL SPECIFICATION TITLE PAGE //

6.9.1.b (1) NARRATIVE

SUMMARY

1-4 6.9.1.b (2) FORCED REDUCTIONS, thru FORCED OUTAGES, AND 6.9.1.b (2) (f) SCHEDULED OUTAGES 6.9.1.b (3) PERSONNEL EXPOSURES 42 43 6.9.1.b (4) FAILED FUEL INDICATIONS 44 6.9.3.a ENVIRONMENTAL MONITORING 1975 ANNUAL REPORT OF ALL PROCEDURE CHANGES 46 214 ANNUAL REPORT OF SYSTEM MODIFICATIONS 215 - 234 AND SPECIAL TESTS

ANNUAL REPORT 811 JANUARY 1 1975 TO DECEMBER 31 1975 INCLUSIVE NARRATIVE

SUMMARY

The Station began the year at full power and continued at this level until 1/4, when there was a reduction to 71%

level to isolate 1B Reheater for repair of the steam supply line. Reactor power returned to 100% level on 1/4. On 1/15 reactor power level was reduced to 83% and on 1/17 reactor power level was reduced to 60% due to turbine runbacks caused by a spurious downspike on a power range channel. Power level was also reduced to 95% on 1/26 and 2/24 to perform T14A (Monthly Intercept and Reheat Stop Valve Test). Reactor power returned to 100% level upon completion of the tests.

The Station was taken to hot shutdown on 3/5 to retrieve two dropped control rods (G5 and G9). The reactor returned critical the same day and returned to full power on 3/6.

The Station was shut down on 3/10 due to a tube leak in.

the "A" Steam Generator and remained shutdown for refueling.

The refueling outsge lasted from 3/10 until 5/10. During this time, thirty six new assemblies and two new secon-dary sources were loaded into the core. Four modifica-tions were made to the secondary side of both Steam Generators. These modifications provided for reduced moisture carryover and flow redistribution at the tube plate. Routine inspection and overhaul of the high-pressure turbine were performed. The Steam Generator primary side tubes were partially tested and all tubes indicating a reduction of 40% of their original thickness were plugged. Under this criterion eleven tubes in the "B" Steam Generator and forty seven tubes in the "A" Steam Generator were plugged. The reactor vessel cold leg,.:nozzle welds were ultrasonically inspected.

Annual Refueling Shutdown concluded with reactor criti-cality on 5/10. The power level was increased to 3%

level on 5/ll for a flux map and then brought subcritical.

The reactor returned critical on 5/12. Power level was increased to 3% level for a flux map, and then returned to a hot shutdown mode. The hot shutdown mode continued until 5/14, when the reactor was brought critical for operator training startups, upon completion of which, the reactor was brought subcritical. Plant startup was accomplished on 5/19, at 0145; and reactor power level was gradually increased to 25% level. The reactor tripped at 0615 due to low steam generator level; the turbine was tripped manually. Unit was started up at 1530, reactor power level was gradually increased to 25%.

Reactor power level was increased to 40% level on 5/20; a further increase to 55% level occurred on 5/21. At 2230 on 5/21, during performance of T-18B (Turbine Main Steam Stop Valves Test), the turbine tripped due to E. H. Control Fail-ure. Reactor was brought critical at 1815 on 5/22. Unit was restored to service on 5/23, reactor power level was gradually increased to 25%. On 5/24 T-18C, (Turbine Over-speed Trip Test) was performed, reactor power level was in-creased to 45%.

Further Reactor power level increase occurred on 5/25, to 50%

level. On 5/26 at 1645 the turbine was 'tr'ipped manually due to E. H. Control Valve Position Limiter malfunction. Reactor trip followed. 'he unit was restored to service at 2230 on 5/26, reactor power level was increased to 25%. The reactor power level was increased to 50% on 5/27. The reactor power level remained at 50% level thru 5/30. On 5/31 the unit was removed from service at 0000 to perform repairs on the E-H Unit and 1-B Main Feedwater Pump and return to service at 1847 and the power level was increased to 50%.

Reactor power level was increased from 50% on 6/1 to 60% on 6/2; to 80% on 6/3; to 90% and to 100% on 6/5. At 0115 on 6/6, when the reactor power level was at 100%, a plant trip occurred due to the main steam isolation valves malfunc-tioning (valves closed). The plant was started up on 6/6 at 1315 and the reactor power level was increased to 50'n the power level was increased to 95%. Reactor power level 6/7 remained at 90% from 6/8 through 6/ll. On 6/12 the reactor power level was increased to 95%. Reactor power level re-mained at 95% level from 6/12 through 6/16. On 6/17 at 0415 a plant trip occurred due to loss of the "A" converter. The plant was started up at 0815 and a power level increase was taking place when, at 1000, the turbine was manually tripped due to excessive vibrations. The plant was started up on 6/21 at 1115 and the reactor power level was increased to 50%. On 6/23 the reactor power level was increased to 88%;

at 0400, a plant trip occurred due to the main steam isolation valves malfunctioning (valves closed). The plant remained shut down through 6/25. On 6/26 the plant was started up at 1845, the reactor power level was increased to 25%. The power level increased to 50% level on 6/27 and to 90% level. The reactor power level remained at 90% through 6/29. Power level was increased to 95% and, further to 100% on 6/30.

On 7/8, reactor power was reduced to 88% level at 1030 due to main feedwater pump low suction alarms and swings in heater drain pump flow. Load increase to 100% level was initiated at 1215 after the generator hydrogen pressure was raised from 50-60 psi.

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Reactor power level was decreased to 14/ on 7/20 to repair a leak in a drain line on the high pressure turbine. Power level was returned to 100/ after repairs were completed.

Reactor power was maintained at 100%%u level until 7/24 when a turbine trip was followed by a reactor trip, at 1445, due to a lightning strike on Station 13A. Unit was returned to service at 0300 on 7/25 after a series of tests were conducted to verify the integrity of the Primary and Secondary Electrical Systems involved in the protective relays that operated.

Reactor power was maintained between 99/ and 100%%u level from July 25 through October 10 except:

7/30 power was reduced to 48/ to check for tube leaks in. the 1-A-1 and 1-A-2 condenser water boxes. On 8/3 power was reduced to 56/ per the load dispatcher's request to maintain transmission line capabilities. Severe thunderstorms were prevalent in the area on that date. On 8/24 power was reduced to 47%%u to perform T-18B (Turbine Main Steam Stop Valves Test).

on 8/25 power was reduced to 96/ to check HCV466 ("A" Feedwater Control Valve).

On 9/10 power was reduced to 97/ to perform PT-6.4 (Excore-Incore Calibration). On 9/23 power was reduced to 96/ level to perform PT-16 (Auxiliary Feedwater System Flow Check) .

On 10/3 power was reduced to 47/ level to perform T-18B (Turbine Main Steam Stop Valves Test). A Unit outage was required on 10/10 to replace cables for the lake intake heaters.. The Unit returned to service on October 12 and returned to 100/ level on 10/13.

The Unit remained at 100/ level from 10/13 through 12/30 except:

On 10/26 power was reduced to 70%%u due to the loss of the 81 gen-erator transformer cooling fans. Power was returned to 100%%u the same day. On 10/27 power was reduced to 97%%u to perform PT-16 (Auxiliary Feedwater System Flow Check).

On ll/18 power was reduced to 47%%u level to perform T-18B (Turbine Main Steam Stop Valves Test). On ll/23 power was reduced to 92/ level to perform T-18A (Intercept and Reheat Stop Valves Test) .

On 12/10 and 12/ll power was reduced to 95%%u level during Nuclear Instrumentation System ad)ustments. On 12/13 power was reduced to 47%%u level to perform T-18B (Turbine Main Steam Stop Valves Test). On 12/12 power was reduced to 47/ to perform M-54.2 (1-B-1 Condenser Water Box Leak Check, with Freon). On 12/22 Power was reduced to 94/ level to perform PT-16 (Auxiliary Feedwater System Flow Check). On 12/23 power was reduced to 46%%u level to perform M-54.2 (1-B-1 Condenser Water Box Leak Check, with Freon).

The Unit was taken to the cold shutdown on .12/30 due to a tube leak in the "B" Steam Generator. 'he Unit remained in cold shutdown through the end of the reporting period.

The safety-related maintenance not covered under Technical Specification Item 6.9.1.b (2) (e) is attached in tabulative form by month.

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ANNUAL REPORT Ill JANUARY 19'(g MALFUNCTION PRECAUTIONS SYSTEM OR RESULTS & EFFECT CORRECTIVE ACTION TAKEN TO COMPONENT ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR INVOLVED OPERATION REACTOR SAFETY 1A Charging Pump Corrective maintenance Keyway wear One Veridrive Replaced. Varidisc bushing and. Used maintenance at steady load on Varidisc belt broken installed new spacer bars and procedure M-ll.4.

Bushing and two space studs bar studs failed.

lA Boric Acid. Trans- None Preventive Annual Inspec Pump inspected.; found in excel Used Maintenance fer pump Maintenance tion lent condition procedures M-11 and M-ll.ll Gas Analyzer Vacuum None Failed. Dia- Loss of Capa- Replaced. disphragm and rein- N/A Pump phragm city stalled.

Turbine 'Driven None Low Oil Pump Failed Changed oil filter and. set dis N/A Auxiliary Feed. Pump Pressure to Start charge pressure on D.C. oil pump to 78 psig.

lB Charging Pump Leak off Return Pump Corrective Failed Loss of pump Replaced diaphxagm N/A Diaphragm capacity lA Auxiliary Building None Separation Reduced suppl Repaired duct and reinforced. N/A Supply Fan of seam in air flow due seams fan housing to recircula-between the tion in duct fan outlet ducts

ANNUAL REPORT Ill JANUARY 1975 1M FUNCTION PREC UNIONS S >T- . OR RESULTS & EFFECT CORRECTIVE ACTION T M~N TO CG'.~~ONE'.i a ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR INVOLVED OPERATION REACTOR SAF TY Hydraulic Snubber Hone Accumulator Leakage of Replaced accumulator with spare Used Procedure M-4 Unit FW-82 (B piston seal hydraulic flu-Feedwater Line) not holding. id from accu-ccumulator mulator of cylinder be- snubber unit lieved to be out of round TCV-130 None Rubber seat cessive Manual valve being used. to con- Used Procedure Non-Regenerative in va1ve cooling water trol component cooling flow EM-136 for Exchange Component lifting and o the non-re- through the non-regenerative for inspection Cooling Outlet tearing due enerative heat exchanger. Metal seated Valve to high velo eat exchanger valve is on order city Boric Acid Filter None ailed dia- eakage thru Replaced diaphragm Used Maintenance Vent Valve 390 hragm due alve procedures M-7.4 o high tem- and M-37.16A erature

ANNUAL REPORT /Ill FEBRUARY 1975 MALFUNCTION PRECAUTIOXS S ~xDf OR RESULTS & EFFECT CORRECTIVE ACTION T-'KEN TO CG'.i~OXE'.i T ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR IV'OLVED OPERATION REACTOR SPY""TY lA Waste Gas N/A Preventive N/A Annual Maintenance and M-36.1 Compressor Maintenance Inspection lB Waste Gas N/A Preventive N/A Annual maintenance and M-36.2 Compressor Maintenance inspection replaced leaking mechanical seal.

- 1c Befee~ Failure of pump to Possible Failure of Temporary wedge installed to Em-75 used to per Infection Pump start on alternate breaker pump to start hold. mechanical latch in form inspection bus 16 after proper misalignmen position. and maintenance operation on bus 14. or mechani- During upcoming refueling Failures occurred. cal binding outage, bus will be de-ener-

,during manual control of lockout gized to allow breaker and board starts in the solenoid lockout assembly operation performance of PT-2.1 plunger without motor starting duty.

Manufacturer notified and requested. to investigate problem New breaker being ordered Xor replacement and eventual testing of present breaker increased to weekly surveillan e.

1A and 1B N/A Service High hP on Cleaned service water side of Used. procedures Diesel Generator Water coolers oil.cooler M-15 and M-15.1 Oil Cooler Sediment Buildup Rll and R12 N/A N/A N/A Anhual inspection and pump N/A Containment overhaul.

Particulate and Gas Radiation Monitor

ANNUAL REPORT //ll FEBRUARY 1975 KQ FUNCTION PRECAUTIONS

--S. ~T ~ OR RESULTS & EFFECT CORRECTIVE ACTION TPZ""N TO

/I~V'DPg'0 ~P ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR INVOLVED OPERATION REACTOR SA:"~

R~ and-R=14 N/A N/A N/A Annual Inspection and. pump N/A Particulate and overhaul.

Gas Radiation Monitor R-10A Containment N/A N/A N/A Annual inspection 8 pump N/A Iodine Monitor overhaul.

Pump Boric Acid N/A Bearing Loss of head.; Inspection and pump overhaul Used. procedure Evaporator Dis- Failure excessive M-ll.ll tilate pumps noise land 2

ANNUAL REPORT //ll JUNE 1975 hGQ FUNCTION PREC UTIONS SvST=. CR RESULTS & EFFECT CORRECTIVE ACTION T KEN TO CG'.~20XEX ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR I'.O'OL1'ED OPERATION REACTOR SAF:"TY Steam Isolation N/A Valve leak- Turbine kept Lapped in seat and disc Used. Procedure Valve to turbine ing thru spinning M-37.35 driven auxiliary when valve feedwater pump closed valve 3504 "A" Travelling Broken Chai Sheared key Replaced Chain, Key, Drive N/A Screen N/A and broke Sprocket drive sprocke Boric Acid N/A Preventive Annual inspection and overhaul N/A Evaporator feed. Maintenance tank pump lB "B" House Service N/A Preventive Annual inspection and overhaul N/A M,ter Pump Maintenance South Turbine N/A Shaft Seal Steam Leak Replaced shaft and bushing N/A Stop Valve Leakage

ANNUAL REPORT //11 JULY 1975 KQ.FUNCTION PRECAUTIOXS S ~T- CR RESULTS & EFFECT CORRECTIVE ACTION TPSZN TO CO~ 0%~' ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR INVOLVED OPERATION REACTOR SAFE 1B Diesel Generato None Phase Pump tripping Ad)usted setting to 100/i. NlA PreIube Pump compensatio out setting at 854.

1A Motor driven None Preventive Ma)or inspection and ovexhaul Used M-ll.5 series Auxiliary feed Maintenance due to scheduled preventive of procedures pump Program maintenance.

No. 8 Environmenta None Pump failure Replaced with rebuilt unit NlA Monitor lA Charging Pump None Failed upper CVCS fluid. Repacked charging pumps with Used procedure and. lower leakage rebuilt gland. assemblies M-ll.4.1 "0" Rings on plunger gland assemb Blender flow None Failed. Valve bonnet diaphragm Used. procedure control valve bonnet leakage'eplaced. M-37.16 FCV-110C diaphragm lA Motor driven None Cut valve Leakage of Lapped out ma)ority of cuts, Used maintenance Auxiliary feed. plug and main feed- new valve internals on oxdex procedure M-37.16J pump recirc valve seat water back to 4304 condensate storage tank lA motor driven None Undetermined Leakage of Rebuilt valve internals under Used maintenance auxiliary feed parts worn main feedwate dix.ection of Crane'-Chapman procedure M-37.16H pump discharge back into service representative, new check valve 4009 auxiliary fee internals on order pump casing ANNUAL REPORT Ill AUGUST 1975 MALFUNCTION PREC UTIONS SYST~i CR RESULTS 6 EFFECT CORRECTIVE ACTION TPZZN TO CG'~~OXE'. i ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR INVOLVED OPERATION R""ACTOR SAF"TY Laundry and. Hot None Preventive Ma)or Inspection of Pump and Procedure M-ll.13 Shower-Pump Maintenance Motor 8 M-45.2 were used.

lB Diesel Genera- None Undet ermine Breaker faile Inspected auxiliary contacts, Used Procedure tor Breaker to to close dur- wire connections, control M-32.1 for breaker Bus 16 ing PT-12.2 switch and sync. switch. inspection and Tested successfully 8 times. M-15 for diesel maintenance.

lA Waste Conden- None Preventive Ma)or Inspection of Pump Used Procedure sate Pump Maintenance M-ll.13 1B Waste Conden-sate Pump None Preventive Ma)or inspection of pump Used Procedure Maintenance M-11.13 lB Sump Tank Pump None Preventive Maintenance Ma)or inspection of pump Used Procedure M-ll.13 Chemical Drain Tank Pump None Preventive Used. procedures Maintenance Ma)or inspection of pump and M-ll.13 and motor M-45.2 Over Power Trip Setpoint shifted. in Faulty Replaced Bistable with spare N/A Bistable TC-405A. the Non-Conservative Zener Diode Setpoint Shif unit Reactor Protection Direction Channel I

ANNUAL REPORT Ill SEPTEMBER 1975 MALFUNCTION PREC UTIONS S.ST=I OR RESULTS & EFFECT CORRECTIVE ACTION T SZN TO CGv~O.i EST ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR iNVOLVED OPERATION REACTOR SAF""TY

/I2 Boric Acid Noae Pump would Replaced valve diaphragms N/A Evaporator Dis- not produce tillate Pump desired flow lB Reactor Coolant None Preventive Performed major inspection on Used Procedure Drain Tank Pump Maintenance pump M-ll.ll New Resin Sluice None Muffler on Pump would Cleaned. Air Drive unit and. N/A Pump Air Drive not produce removed muffler assembly Exhaust desired flow Plugged .

1C Service Water None Preventive Performed minor inspection on Used Procedure Pump Maintenance pulllp M-11.10

'lend Valves llOB None One or both Borated water Adjusted. stroke on both valves Used. Procedures and llOC valves added to CVCS M-37.10 and.

leaking by System while M-37.16 blending to the refueling water storage t'ank ANNUAL REPORT 0'll OCTOBER 1975 KLLFUNCTION PREC .'.IONS S ~TM OR RESULTS & EFFECT CORRECTIVE ACTION T S"-N TO CG~ZGNEX a ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR INVOLVED OPERATION R""ACTOR SAF:"iY Non-Regenerative None Rubber Valve Excessive Replaced valve Used Emergency Heat Exchanger Seat Lifting flow through Maintenance Temperature and Tearing valve. Loss Procedure EM-136 Control Valve of tempera-TCV-130 ture control by valve Main Steam None Gasket Leak Steam leak at Sealed leak using Furmainite Used Maintenance Safety Valve 3513 valve flange process Procedure M-37.39 1B Containment None Preventive . None Performed. minor inspection; Used Procedures Spray Pump Maintenance change oil, aligned pump M-ll.2 and M-ll.14$

Schedule Plant Vent Monitor None Belt. Failure Loss of sampl Replaced belt N/A Pump R-13 8 14 flow lA Boric Acid None Preventive Removed. and performed major Used Procedure Evaporator feed- Maintenance inspection M-ll.ll tank pump Program Diesel Fire Pump None Heat Ex- Diesel runnin Plugged leaking tubes Used. Procedure changer tube hot due to M-38.1 leak loss of jacket water level

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ANNUAL REPORT Ill NOVEMBER 1975 KQ FUNCTION PRECAU IOUS SvSQ~ QQ RESULTS & EFFECT CORRECTIVE ACTION T ~~N TO CO'.~~QXE'.ii ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR INVOLVED OPERATION REACTOR SAFE Waste Evaporator None Preventive Performed inspection and Used Procedure Hot Water Recir- Maintenance overhaul. Replaced with spare. M-ll.13 culation Pump Schedule 1A Gas Stripper None Preventive Performed inspection and Used Procedure Feed Pump Maintenance overhaul. M-ll.ll.

Schedule lB Waste Gas None Preventive Performed annua1 inspection Used Procedure Compressor Maintenance of compressor and controllers M-36.2 Schedule Containment Purge None Air turbu- Tack welds on Repaired housing welds. N/A Supply Fan Housing lance housing cracked lA Service Water None Pump failed Replaced overcurrent trip Used Procedures Pump Breaker to start auto devices, alarm switch and B M-32 and M-32.1 matica1ly on phase arcing contact .,

diesel start ANNUAL REPORT f/ll NOVEMBER 1975 MALFUNCTION PR=C U. IO'.iS

>YSL f OR RESULTS 6 EFFECT CORRECTIVE ACTION T-'Mr'N TO CGv~OXEN ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR INVOLVED OPERATION REACTOR SAP"TY Spent Fuel Pit None Preventive Performed inspection and over- Used. Procedure Pump Maintenance haul M-11.14

-lA Gas Stripper Bottoms Pump None Preventive Performed. inspection and. Used Procedure Maintenance overhaul M-ll.ll Scheduled.

Waste Evaporator None Preventive Performed inspection and. Used. Procedure Distillate Pump Maintenance overhaul M-ll.ll Schedule lA Concentrates None Preventive Performed. inspection and. Used Procedure Transfer Pump Maintenance overhaul M-ll.ll Schedule lA Auxiliary None Valve plug Stop check Replaced. valve plug assembly Used Procedure Feedwater Pump and seat valve leaking and lapped to seat M-3'f.40 Motor Operated cut back through Discharge Valve 4007 Blender Valve None Bonnet "0" Instrument Replaced. "0" Ring and. valve Used. Procedure FCV-110B Ring failed. air pressure diaphragm M-37.10 on top of diaphragm caused. failur lB Charging Dis- None Pinhole leak Ground out and repaired. weld Used Procedure charge Drain Line in socket M-ll.4.2 and weld WE-1A-73 Waste Evaporator None Preventive Performed. inspection and Used. Procedure

'eed Tank Pump Maintenaqce overhaul M-ll.ll Schedule ANNUAL REPORT //ll DECEMBER 1975 1M FUNCTION PRECAU IOUS SYST. f OR RESULTS 6 EFFECT CORRECTIVE ACTION T Z"-N TO CR~~ONENT ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR I'EVOLVED OPERATION REACTOR SPy~i Boric': Acid. Filter None Diaphragm Valve Leaking Replaced Bonnet ~ Diaphragm Used. Procedure Vent Valve 390 Failure Through M-37.16A and. M-7.4 Waste Evaporator None Sludge High Radia- Acid. cleaned unit and. vacuumed. Used Procedure M-13 Unit Accumulatio tion readings out feed tank in Feed T at tank 1B Charging Pump None Poor initi Leak on drain Replaced section of affected. Used Procedures Disclarge Drain weld line at weld pipe M-ll.4.2 and Line WE-lA-73 1A L 1B Diesel None Sediment in High DP acros Cleaned Tubes Used Procedures Generator Oil Service cooler units M-15 and M-15.1 Coolers Water 1A Reheater Steam None Lower Plug Valve binding Installed. new stem and plug N/A Inlet Control

. Guide Worn and rattling Valve 3425 Excessively during opera-ti'on.

lA Waste Gas Compressor None Preventive Inspected unit replaced. Used Procedure Maintenance mechanical seal M-36.1 Schedule Containment None Bearing Pump. failed. Replaced with" spare unit N/A R-ll, 12 Sample Failure Pump lB Diesel Genera- N/A Prelube pump Changed holding coil on N/A l tor Prelube Pump not running contactor ANNUAL. REPORT ¹ll 6.9.1.b (2) Thru 6.9.l.b (2) (f)

January 4, 1975 Forced. Reduction (a) The unit was reduced from 100% level to 71% level to permit the removal of the 1B Reheater Steam Line from service. The orifice flange gasket failed causing a steam leak. Repairs were made by removing the failed gasket and. replacing with a new gasket.

(b) No reportable occurrence pertained. to this forced reduction.

(c) No appropriate corrective action was'required.

(d) Operating time lost was 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and 25 minutes.

(e) No ma)or safety-related corrective maintenance was performed during this forced reduction. The critical path activity dictating the length of the reduction was the replacement of the failed gasket.

(f) No release of radioactivity or radiation exposure was associated with the forced reduction.

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ANNUAL REPORT all March 5, 1975 FORCED OUTAGE The unit was at 100/ level when control rods G-5 and G-9 dropped into the core from the full out position. The drive control for both rods are located in the same Rod Drive Cabinet A hole was drilled in the floor above the cabinet. Water used for lubricant leaked th'rough the hole into the top of the cabinet and caused the holding coils to release the rods. The unit was taken to hot shutdown and the control circuits, for the rods, were checked.

There being no damage, the rods were returned to their" proper positions.

No reportable occurrence pertained to this forced outage.

Metal covers were installed above the Rod Control Cabinets to prevent a recurrence of this problem.

Operating time lost was 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and 31 minutes.

No ma)or safety-related corrective maintenance was performed during this forced outage. The critical path activity dictating the length of the outage was the determination of cause and verification that no damage to the rod control circuits occurred.

No release of radioactivity or radiation exposure was associated with the forced outage.

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ANNUAL REPORT 8'll March 10, 1975 SCHEDULED OUTAGE (a) The unit was scheduled to be shutdown for a refueling outage. A leak in the "A" Steam Generator was detected and the unit was removed from service four days early to minimize the effect of the tube leak.

(b) Three reportable occurrences occurred during this scheduled outage.

The reports were:

Abnormal Occurrence 75-07, Thinning of Steam Generator Tube Walls Abnormal Occurrence 75-08, Post-Accident Charcoal Filters Abnormal Occurrence 75-09, Control Rod Drive Housing (c) Corrective Action consisted of eddy current test of tubes in both steam generators and explosive plugging of all tubes indicating a reduction to 40% of their original thickness.

(d) Operating time lost was 1,658'ours, and 15 minutes.

(e) Major'afety-related"corrective maintenance performed during the scheduled outage is listed below. The critical path activity dictating the length of the scheduled outage was repairs to the steam generator tubes and the refueling of the core.

(f) No single release of radioactivity associated with the outage accounted for more than 10% of the allowable annual values. The radiation exposure of those individuals receiving greater than 0.5 rem from inspection of tubes is shown in the table.

Dose Range Number of Individuals Rem in each ran e 0.50 - 0.75 17 0.75 - 1.00 22 1.0 - 1.5 58 1.5 - 2.0 18 2+ 0 Total Exposure 132 Rem Number of Individuals 115 19 <<

NUAL REPORT Ill Ma,rch 10, 1975 SCHEDULED OUTAGE (a) The unit was scheduled to be shutdown f g o Steam Generator was detected an and thee unit was removed from service four da s earl (b) Three re portable. occurrences re durin occurred uring this scheduled outage.

The reports were:

Abnormal Occurrence 75-07 Thinn'nning of Steam Generator Tube Walls Abnormal Occurrence 75-08, Post-Accident Charcoal Filters Abnormal Occurrence 75-09, Control Rod Drive Housing (c) Corrective Action consisted of ultrasonic test of t d 1 1 gging of all tubes indicating a eir original thickness.

(d) Operating time lost was 1 658 h ours, and. 15 minutes.

(e) -re lated corrective maintenance Ma)or safet y-scheduled outage is listed below di tt th 1 en gth of the scheduled outa g e was repairs to the steam generator tubes es an th refueling of the core.

and. the h

ANNUAL REPORT //11 March 10, 1975 to May 10, 1975 1M.FUNCTION PREDUTIOXS OR RESULTS 6 EFFECT CORRECTIVE ACTION T ZZN TO CO'.~~OXE'.i T ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVID" FOB.

I!O'OLVED OPERATION REACTOR SAP~

Condensate~torage None Leakage at Air leakage Repaired leaks and vacuum N/A Tanks flanges and into tanks checked. Refueling Shutdown in bags on diafloat membranes Pressurizer relief None Technical Bench checked safety valves Used Procedure valves 434 and 435 Specifica- Rssp-l2.

tion Requirement Main Feedwater None Bonnet Gas- Seal welded. Cut off studs and bonnets, N/A Pump Suction Valves ket leakage flange and dressed. flanges and stud and 3970 and 3971: stud. holes to nut areas, cleaned. up gasket prevent steam area, and reassembled valves leakage 1A Main. Steam None Valve disc Installed new spindle and. Used Procedure Power Operated and seat cut lapped in M-37.34 Relief Valve 3411 due to steam I

leakage lB Main Steam None Valve disc Replaced disc and lapped seat Used Procedure Admission Valve 3504 and seat cut M-37.35 to turbine driven due to steam auxiliary feed. pump le'akage Charging Pump Relief None Annual Valves found Cleaned and repaired valves, Used Procedure Valves 283, 284, 285 Inspection to be leaking then retested RSSP-12 7

lA and. lB Steam None Original Excessive we Insta1led new design valve N/A Generator Main Teed application on. valve cage internals of different Refueling Shutdown water Control Valves of oversized and 'plug mater'ial 4269 and. 427O valves assemblies.

Possible fail ure of cage ANNUAL REPORT Ill Ms,rch 12, 1975 to May 10, 1975 MALFUNCTION PREC 'TIONS SvST f CR RESULTS & EFFECT CORRECTIVE ACTION T'Z""N TO CQ\/QO'l g l~ ON SIZE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR I!SOLVED OPERATION REACTOR SAF""TY Letdown Relief Valv Hone Cut disc an Valve leakage Installed new disc, nozzle and Used Procedure 209 nozzle during test bellows assembly then retested M-34 and RSSP-12 assembly Pressurizer Power None Seat Leakage Lapped out cuts on valve gate Used Procedure Operated. Relief and body seats M-37.2-Block Valve 515 Pressurizer Steam None Cut seat an Steam L'eakage Replaced Valve Used Procedure Space Sample Valve plug M-37.36 951 1A and Lb Diesel None Preventive Performed annual inspection Used Procedure Generators Maintenance M-15 and M-15.1 lA and IB Charging None Preventive Repacked pumps and replaced Used. Procedures Pumps Maintenance worn plungers M-ll.4.1 and M-ll.4.2 lA Service Water None Preventive Performed ma)or inspection Used Procedure Pump Maintenance and overhaul of pump M-11.10 Control Rod Drive None Possible Small borate Replaced cap Used. Procedure K-7 Housing Cap Fabrication deposit on E -140 defect cap indicatin causing pin leakage hole leak in canopy of cap above seal weld.

Main Feedwater Lines None Some initial Welds Repaired. welds using approved N/A construction MS-1000G procedures and then re-examined Refueling Shutdown welds poor MS-1000G2 MS-.1002B (Continued)

ANNUAL REPORT 1/ll March 12 1975 to Ma 10 1 75 MALFUNCTION PB.~C UTIONS S~ - ~ CR RESULTS & EFFECT CORRECTIVE ACTION T ZZN TO C/ QJQOQ'PL I ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR I'.EVOLVED OPERATION RF~CTOR SAFE.

Main Stream-Lines MS-1002Bl (Continued) MS-1002D MS-1002D2 MS-1002E MS-1003B MS-1003Bl MS-1003C MS-1003D MS-1003E 1C Safety Infection None Scheduled Intermittent Replaced old breaker with new N/A Pump Bus 16 breaker Inspection failure of spare unit breaker to close North Turbine None Galled leak- Shaft leaked Installed new shaft and. bushin , H/A Stop Valve off seal steam seat at bushing and.

shaft High Pressure Hone Scheduled Excessive Repaired. areas of erosion; N/A Turbine Inspection steam erosion remachined points in steam ches orifice and stationary seals and blades.

Waste Condensate None Diaphragm Diaphragm Replaced with spare N/A Demineralizer Resin Dried Out Failure Sluice Pump ANNUAL REPORT 0'll March. 12, 1975 to May. 10, 1975.

PM.FUNCTION PRECAUTIONS SYST~i CR RESULTS & EFFECT CORRECTIVE ACTION T ZEN TO C

f'/Q 6 g 'PL w ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR, IN"s'QLVED OPERATION REACTOR SAP~

Main Feedwater and Hone cheduled Rebuilt hydraulic units with Used Procedures Steam Hydraulic nspection spare parts including ethy. hf-40, M-40.1, Snubbers lene-propolene seal material. and M-40.2 h$ -22, FW-25, FW-82, FW-84, FW-85, MS-146 (lower), MS-160, MS-166, MS-167, MS-179, MS-185 Waste Disposal Retur . None Failed. Bonnet Leak Replaced diaphragm Used Procedures Valve 165A from Diaphragm M-37.16A and Drumming Station M-37.16G lA Containment None Scheduled Loss of Replaced charcoal in filter Post Installation l Post-Accident Test ~

Iodine Removal units check okay.

Charcoal Filter Efficiency Refueling.

ANNUAL REPORT //11 March 12,",1975 to May 10, 1975 KQ.FUNCTION PRECAUTIOiS OR RESULTS & EFFECT CORRECTIVE ACTION T M~N TO CP'I JQQi Q I ON SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR I.'EVOLVED OPERATION REACTOR SA==tY Boric Acid~apora- None Diaphragm o Restricted. Replaced diaphragm N/A tor Distillate suction val pump flow System to lA Distillate pump failed.

Main Steam Check None Misalignment Sloppy key Metalized. and. machined shafts; Used procedure Valves 3518 8 3519 of keyways fits. Wear o remachined keyways to align M-37.21 on shafts shafts in are keyways and disc of disc arms ~

Condenser Water None Fretting or 3 tubes with Plugged tubes..and also did N/A Refueling Box 1B1 Erosion small leaks eddy current examination of shutdown several tubes in waterboxes Pressurizer Power None Crud. Buildup Bypass leakag Lapped. area for good. gasket Used procedure Operated Relief Valv on valve around, cage seating surface M-37.11 PCV-431C body at and plug Refueling Shutdown lower cage i gasket area Safety Injection None Preventive Removed, cleaned., and bench System Valve 887 Relief Maintenance checked.

end'EM-107 Used, along with RSSP-12 1A Reheater Tube None 4 Tubes Increased. Plugged three tubes, repaired N/A Bundle leaking at steam flow to one tube tube to tube reheater, loss sheet joint. of unit effi-Cause believ d ciency to be ther-mal rachetin ANNUAL REPORT //ll March 12 1975 to Ma 10 1 KQ FUNCTION PR="CAUTIOXS OR RESULTS & EFFECT CORRECTIVE ACTION T ZZN TO CA'l/QO% ~~1~ ON .SAFE CAUSE RESULT TO PREVENT REPETITION PROVIDE FOR

".EVOLVED OPERATION REACTOR SAF~

Letdown System None Slight cut Valve leaked Replaced with spare Used procedure.

Relief Valve 203 on valve during bench RSSP-12 disc and check nozzle lD Service Water None Preventive Performed Inspection and Used Procedure Pump 1B Boric Acid Pump None Maintenance Preventive Maintenance Overhaul and overhaul Acid Transfer of 1B Pump

'sed Performed annual inspection Boric M-ll.lo Procedure M-11 and M-ll.ll Waste Evaporator None Possible Pump bearings Replaced pump, reduced. end Used Procedure Feed Tank Pump over con- and. motor point on batch concentration M-ll.3 and M-ll.ll centration stator of waste failure bottoms 1A Steam Generator None Slight tube Primary to Plugged leaking tube; eddy Used. M-43 Series 1B Steam Generator leak in lA Secondary current examination with all Procedures and S/G Leakage tubes with greater than 40$ SM75-24 Series defects plugged (47 tubes Procedures plugged including one above Refueling in 1A S/G and 1B S/G) ll plugged in Tube sheets lanced Shutdown and secondary internals modiTied Seal Return Relief None Preventive Valve Leakage Replaced. disc, spotted. nozzle; Used. Procedure Valve 314 Maintenance on bench test retested. valve RSSP-12 Condenser Steam None Steam cuts Steam leakage Replaced. valve internals N/A Dump Valves 3354, on disc and. through Refueling Shutdown 3351, 3353 and 3349 cage valves ANNUAL REPORT Ill May 19, 1975 FORCED OUTAGE (a) The unit was at 25/. level when a trip occurred due to a lo lo level in the steam generators. The automatic hotwell level control failed causing the hotwell water to be rejected. to the condensate storage tanks. This removed the source of water for the steam generators.

(b) No reportable occurrence pertained to this forced outage.

(c) The corrective action consisted, of removing the electronic hotwell level controller that had been installed during the scheduled outage and reinstalling the pneumatic control system.

(d) Operating time lost was 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months and. 17 minutes.

(e) No major safety-related corrective maintenance was performed during this forced outage. The critical path activity dictating the length of the outage was the time required to change hotwell level control systems.

No release of radioactivity or radiation exposure was ~ associated with the forced outage.

ANNUAL REPORT Ill May 21, .1975 FORCED OUTAGE The Unit was at 55/~ level when a Turbine trip occurred. due to a failure of Electric-hydraulic controller for the turbine. Vibration of control wires at the turbine caused the insulation to wear and.

shorting occurrecl. Heat from the shorted. wires caused additional damage

(

No reportable occurrence pertained to this forced. outage.

The corrective action taken to reduce the probability of recurrence was the installation of gasket material where the new wires enter or leave a conduit.

Operating time lost as a result of the forced outage was 43 hours4.976852e-4 days 0.0119 hours 7.109788e-5 weeks 1.63615e-5 months ancl 40 minutes.

No ma)or safety-related corrective maintenance was performed during the outage. The critical path activity dictating the length of the outage was replacement and testing of the damaged wires.

No release of radioactivity or radiation exposure was associated with the forced outage.

~ ~

ANNUAL REPORT ¹ll May 26, 1975 FORCED OUTAGE (a) The unit was at 55fo level when a manual trip was performed. The control valve position limiter malfunctioned due to a failed control circuit card. This card was damaged clue to the shorted. wires on.

May 21, 1975.

(b) No reportable occurrence pertained to this forced outage.

(c) The valve position limiter circuit cards were tested to insure no

-outer damage was present.

(d) Operating time lost was 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and. 37 minutes.

(e) No ma)or safety-related corrective maintenance was performed during this forced outage. The critical path activity dictating the length of the outage was the replacement and testing of the valve position limiter control card.

(f) No release of radioactivity or radiation exposure was associated.

with the.. forced outage.

ANNUAL REPORT Ill May 31, 1975 FORCED OUTAGE The unit was operating at 50$ level when a mismatch was noted between the "A" and "B" Feedwater Pumps. The unit was manually shutdown. Investigation showed. that the 1B Main Feed Pump Discharge valve had Jammed, but freed itself during the shutdown.

No reportable occurrence pertained, to this forced outage.

The valve was disassembled, inspected and the torque setting was readJusted.

Operating time lost was 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months and 30 minutes.

No maJor safety-related corrective maintenance was performed during this forced outage. The critical activity path activity dictating the length of the outage was the inspection of the valve.

No release of radioactivity or radiation exposure was associated with the outage.

ANNUAL REPORT 811 June 6, 1975 FORCED OUTAGE (a) The unit was operating at 1005 level when a reactor trip occurred due to lo lo level in the "B" Steam Generator. The "A" and. "B" Main Steam isolation valves malfunctioned and went closed.

(b) , No reportable occurrence pertained. to this forced outage.

(c) Valve actuators were cleaned and ad)usted.

(d) Operating time lost was 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months and 58 minutes.

(e) No maJor safety-related corrective maintenance was performed during this forced outage. The critical path activity dictating the length of the outage was the cleaning and ad)ustment of the valve actuator.

No release of radioactivity or radiation exposure was associated, with the forced outage.

ANNUAL REPORT ¹11 June 17, 1975 FORCED OUTAGE (a) The unit was at 951~ level when a reactor trip occurred due to the loss of the "lA" Inverter and corresponding loss of the "1A" Instrument Bus. The "lA" Inverter. failed due to a failure of the pulse drive printed circuit card.

(b) No reportable occurrence pertained to this forced. outage.

(c) Corrective action consisted of replacement of the failed pulse drive printed circuit card.

(d) Operating time lost was 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 5 minutes.

(e) Safety related corrective maintenance was performed. on the .1A Inverter.. This consisted of replacement of the pulse drive printed circuit card. The critical path activity dictating the length of the outage was the replacement of the pulse drive printed circuit cary No release of radioactivity or radiation exposure was associated with the forced outage.

-32"

ANNUAL REPORT 0'll June 17, 1975 FORCED OUTAGE (a) The unit was at 305 level when the turbine was manually tripped due to excessive vibration of the feedwater piping. The feedwater control valves were hunting causing pulsations in the feedwater piping.

(b) No reportable occurrence pertained to this forced outage.

(c) Corrective action consisted of modifying the feedwater control valves.

(d) Operating time lost was 97 hours0.00112 days 0.0269 hours 1.603836e-4 weeks 3.69085e-5 months and 16 minutes.

(e) No ma)or safety-related corrective maintenance was performed during this forced outage. The critical path activity dictating the length of the outage was the modification of the feedwater control valves.

(f) No release of radioactivity or radiation exposure was associated with the forced outage.

ANNUAL REPORT 811 June 23, 1975 FORCED OUTAGE (a) The unit was operating at 88fo level when a reactor trip occurred due to lo lo level in the "B" Steam Generator. The "A" and "B" main steam isolation valves malfunctioned and went closed.

(b) No reportable occurrence pertained to this forced. outage.

(c) Corrective action consisted of modifying the flapper stop to reposition the flapper when in the open position and modify the actuator to accept this new position.

(d) -

Operating time lost was 86 hours9.953704e-4 days 0.0239 hours 1.421958e-4 weeks 3.2723e-5 months and 45 minutes.

(e) Safety-related. corrective maintenance was the repositioning of the flapper and the modification of the actuator. These actions were the critical path activity dictating the length of the outage.

(f) No release of radioactivity or radiation exposure was associated with the forced outage.

ANNUAL REPORT 811 July 20, 1975 FORCED REDUCTXON (a) The unit was reduced from 100fo level to 14%%uo level to permit the repair of a steam leak on the high pressure turbine drain line.

(b) No reportable occurrence pertained to this forced reduction.

(c) No appropriate corrective action was required..

(d) Operating time lost was 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and 45 minutes.

(e) No major safety-related. corrective maintenance was performed during this forced reduction. The critical path activity dictating the length of the reduction was the repair of the drain line steam leak.

(f) No release of radioactivity or radiation exposure was associated with the forced reduction.

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ANNUAL REPORT Ill July 24, 1975 FORCED OUTAGE (a) The unit was at 100(a level when a lightning strike at station 13A caused a failure of the generator differential relay which in turn caused a turbine trip.

(b) No reportable occurrence pertained to this forced outage.

(c) No appropriate corrective action was required.

(d) Operating time lost was 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and 22 minutes.

(e) No ma)or safety-related. corrective maintenance was performed during this forced outage. The critical path activity dictating the length of the forced, outage was the repair of the generator differential relay and testing to verify the integrity of the Primary and Secondary Electrical Systems involved in the protective relays that operated.

No release of radioactivity or radiation exposure was associated with the forced reduction.

ANNUAL REPORT Ill July 30, 1975 FORCED REDUCTION (a) The unit was reduced from 99fo level to 48fo level to permit removal, of the "lA" condenser from service. Chemistry samples indicated a leaking condenser tube. There were no leaking tubes. The source of sodium was traced to a leaking heating coil:.in the sodium hydroxide tank.

(b) No reportable occurrence pertained. to this forced reduction.

(c) 'Corrective action consisted. of diverting the condensate from the heating coil to a floor drain.

(d) Operating time lost was 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months and 49 minutes.

(e) No ma]or safety-related corrective maintenance was performed during this forced. reduction. The critical path activity dictating the length of the reduction was the inspection of the condenser tubes.

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ANNUAL REPORT Pll October 10, 1975 SCHEDULED OUTAGE (a) The unit was scheduled to be shutdown for replacement of the power cables to the lake intake heaters.

(b) No reportable occurrence pertained to this scheduled outage.

(c) No appropriate corrective action was required..

(d) Operating time lost was 43 hours4.976852e-4 days 0.0119 hours 7.109788e-5 weeks 1.63615e-5 months and 32 minutes.

(e) Three safety-related corrective maintenance items were performed concurrent with the replacement of the heater power cables. How-ever, the replacement of the heater power cables was the critical path activity dictating the lengths of the outage. The safety-related corrective maintenance items were:

1. "B" Auxiliary Feedwater isolation valve was leaking at the" sea1 ring gasket. The leak was sealed by using the Furmanite process.

2. The Hydraulic Snubber on the "B" Feedwater line had a scored.

accumulator cylinder and was leaking fluid. The accumulator was replaced.

3. Bank B Control Rod Drive Mechanism has a faulty connector at the Reactor head causing the Control Rod. not to stop.

The cable and connector were replaced at the reactor head.

No release of radioactivity or single radiation exposure specifically associated with the outage accounted for more than 10'f the allow-able annual values.

ANNUAL REPORT Ill December 21, 1975 FORCED REDUCTION (a) The unit was reduced from lOOf~ to 47$ level to permit the removal of the "l3" condenser from service. The water boxes were opened, but no leak could be detected.

(b) No reportable occurrence pertained to this forced reduction.

(c) No appropriate corrective action was required.

(d) Operating time lost was 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months and 15 minutes.

(e) No ma)or safety-related, corrective maintenance was performed during this forced reduction. The critical path activity dictating the length of the reduction was in'spection of the tube sheets.

No r'elease of radioactivity or radiation exposure was associated with the forced reduction.

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ANNUAL REPORT //ll December 23, 1975 FORCED REDUCTION (a) The unit was reduced from 100$ to 465 level to permit the removal of the "1B" Condenser from service. Investigation showed that one tube was leaking.

(b) No reportable occurrence pertained to this forced reduction.

(c) Appropriate corrective action was to plug the leaking tube.

(d) Operating time lost was 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months and 25 minutes.

(e) No ma)or safety-related. corrective maintenance was performed. during this forced reduction. The critical path activity dictating the length of the reduction was locating and plugging of the leaking tube.,

(f) No release of radioactivity or radiation exposure was .associated with the forced reduction.

4O

ANNUAL REPORT $Pll December 30, 1975 FORCED OUTAGE (a) The unit was at 100%%u level when the increase in activity in the "B" Steam Generator started to approach the Technical Specification limit. To prevent exceeding this limit the unit was taken to cold shutdown.

(b) No reportable occurrence pertaining to this forced outage had been written, as of the end of this reporting period.

(c), No corrective action had taken place, as of the end of this reporting period.

(d) Operating time lost was 43 hours4.976852e-4 days 0.0119 hours 7.109788e-5 weeks 1.63615e-5 months and 45 minutes, as of the end of this reporting period; (e) No ma)or safety-related corrective maintenance was started as of the end of the reporting period. The critical path activity dictating the length of the outage could not be determined, as of the end of this reporting period.

(f) No single release of radioactivity or radiation exposure, specifically associated with the outage, accounted for more than 10/ of the allowable annual values, as of the end of this reporting period.

41

ANNUAL REPORT ¹ll JANUARY 1, 1975 Tt)RU DECEMBER 31 1975 INCLUSIVE 1 5 GINNA STATION IN-PLANT EXPOSURE 6.9.l.b.3 EXPOSURE IN REM (b Film Bad e)

Number of Reactor Operation Manpower Personnel and Routine . Special Inservice Waste Total Source >100 mrem a/b Permanent Plant 87 6/0 13 0 113 Other RGIlE 304 120/4 50 0 262 Contractors 167 30/20 24 17 121 Total 558 27 162 156/24 61 30 19 17 496

a. Steam Generator Tube Examination, Mechanical Modifications

b. Auxiliary Feedwater Piping Installation f

'ANNUAL'EPORT /311 JANUARY 1 1975 THRU DECEMBER 31 1975 INCLUSIVE 6.9.1.b.3 During 1975, Rochester Gas 5 Electric Corporation provided. monitoring for 836 individuals. The table below summarizes the doses received by individuals during the year. The 4 individuals who exceeded 3.0 Rem were permanent Ginna Station employees and the maximum dose was 3.430 Rem.

Dose Ranges (Rem) Number of'ndividuals in each range No measurable Exposure 151 Measurable Exposure less than .3.00 127

.100 .250 93

.250 .500 93

.500 750 68

.750 1.000 74 1.000 - 1.500 149 1.500 2.000 57 2.000 - 3.000 20 3.000 - 4.000 4 4.000 + 0

-43'-

~4

<c

'1

ANNUAL REPORT Ill January 1, 1975 to December 31, 1975 Inclusive 6.9.1.'b (4) Failed Fuel Indications There were no indications of failed fuel from visual examinations performed. Four fuel assemblies, X-Ol thru X-04, were inspected, by underwater television inspections. Other fuel assemblies were viewed by binoculars as they were transferred.

There were no examinations performed on irradiated fuel, nor were eddy current or ultrasonic testing performed.

44

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t

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ANNUAL REPORT /311 JANUARY 1, 1975 TO DECEMBER 31 1975 INCLUSIVE

'.9.3.a Environmental Monitorin 1975

(

A summary of the survey results is presented below:

(ab) (d) (c)

RESULTS TYPE NO.. OF NO. OF LOCATION SAMPLES FREQUENCY AVG. MAX.

Atmospheric 3 541 Weekly .077 .320 pci/m Dust'all Out 2 59 Monthly 42.5 86; pci/m Radiation Film 144 Monthly clO <10 mRem TLD 23 46 Quarterly 24.1 30.3 mRem Lake Ontario Water 183 Weekly 5.5 13.5 pci/1 Deer Creek Water 22 Monthly 7.6 14.4 pCi/1 Well Water 10 Monthly 12.1 16.7 pCi/1 Milk 10 Monthly .38 1.21 pCi/1 Fruit Annual .028 Ci Cs137 gm Marine Organisms Fish Quarterly 2.84 3.45 pci/gm Algae ;-9. 7 pCi/gm Lake Bottom Annual 14.2 pCi/gm 6.9.3.a (2) No sample or measurement indicated statistically significant levels of radioactivity above the background.

- 45

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F

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ANNUAL REPORT //11 JANUARY 1 1975 TO DECEMBER 31 1975 INCLUSIVE Annual Report of all procedure changes:

PORC ITEM NUMBER: DESCRIPTION A-2.3 Maximum Unit Power PCN74-1476. J. S traight presented this procedure change. It requested; Add reference 2.2; 2.2. - U.S. Atomic Energy Commission R.O. Inspection Report No. 50-244/74 Item E.4.c Add to 3.1; If the calorimetric exceeds 102.0%, notify the plant supt. and/or duty engineer.

Add note; notification of plant supt. and/or duty engineer ensures compliance with containment in Reference 2.2.

The Committee recommended approval of this change.

75-3 PT-23.15 Containment Isolation Valve Leak Rate Testin Containment Air Sam le Out PCN75-4. J. Straight presented this procedure change. These changes were to reflect valve numbers and other minor changes. The Committee recommended 'approval of this change.

75-4 RSSP-5 Immediate Boration S stem PCN75-3. J. Straight presented this procedure change. It requested to incorporate test control tag steps along with the request to delete steps 4.4.1 through 4.4.3. The Committee recommended'pproval of this change.

75-5 RSSP-9 Rod Position Indicator Ali nment PCN75-7.

J. Straight presented this procedure for deletion. This procedure is now covered by CP-2.0. The Committee recommended approval of this deletion.

1 C

C

Annual Report //11 of all procedure changes: (Continued) 1/]/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-14 ST-75-1 Ra id Fuel hssembl Power Escalation Test PCN75-17. C. Peck presented this new procedure. This procedure is to determine the effect of rapid power escalation upon fuel cladding that has a high burn-up.

The Committee reviewed this procedure.

75-22 0-6 0 eration & Process Monitorin PCN75-16. J. Straight presented this procedure change, It requested step 5.10 be changed to read; "Log average delta-flux every half hour to insure adherence to Technical Specifications" The Committee recommended approval of this change.

75-23 P-6 Precautions Limitations & Set pints Nuclear Instrumentation S stem PCN75-2. J. Stxaight presented this procedure change.

. It requested; B - Set points Change NC-304 setpoint (P-.8) to read 50%

- Full Power.

Also update to A-30 format.

The Committee recommended approval of this change.

75-25 PT-3 Containment S ra Pum & NaOH Additive S stem PCN75-35.

J . Straight presented this pxocedure change. It requested step 6 ' ' be added; 6.3.5 - open test line valve 864A The Committee recommended approval of this change.

75-26 T-8F Fillin The Il ochlorite Tank PCN75-8. J. Straight presented this new procedure. This procedure is to describe the steps for the filling of the Sodium !Iypochlorite Storage Tank. The Committee recommended approval of this procedure.

- 47'-

Annual Report $/ll of all procedure changes: (Continued) l/1/75 to'12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-37 A-46 B ass Of Safet Function Or Jum er Control PCN75-117.

(74-331) J. Straight presented this procedure change. These changes provide requirements that the jumper request has been verified by two qualified personnel, the. defeat or bypass device installation locations are clearly described, and criteria for PORC review are identified. The Committee recommended approval of this change, 75-38 PT-17.2 Process Monitors R R-20, Iodine Monitors R- 10A &

R-10B PCN75-46. J. Straight presented this procedure change. It requested several changes be made to further avoid repeated trips.

The Committee recommended approval of this change.

75-39 E-16.1 Hi h Activit Radiation Monitorin System, PCN75-49. J . Straight presented this procedure change.

This was a rewrite to conform to A-30 format. The Committee.

recommended approval of this change.

75-41 GS-21 Site Access, PCN75-37. J, Straight presented this procedure change. It requested step 3.1.2.1 be changed to read; "Personnel issued a white photo-identification card, do not require permission to enter the site. During off hours the control room will be advised upon entry of these personnel. Personnel issued 14 F 0 approval of this change.

'he Committee recommended r

75-42 M-11 Re lacement Or Maintenance Of A Boric Acid Transfer Pum PCN75-56 75-57 75-121. J, Straight presented these temporary changes for review.

PCN75-56 - add to step 5.1.4; "to close valve 345 to provide PCN75-57 << reque. ted temporary approval to close valves 348-A, 341, 347 and 398 in order to check diaphragm in valve 442.

PCN75-121 - N.A. steps 5.10 and 5.11 The Committee reviewed these temporary change.

75-43 M-32 Use Of Circuit Breaker Multi-Am Test Unit, PCN75-45.

J. Straight presented this procedure change. It requested minor changes be made to the Breaker Test Data sheet. The Committee recommended approval of this change.

Annual Report fill of all procedure changes: (Continued) 1/l./75 to .12/31/75

~

Inclusive PORC ITEM NUMBER: DESCRIPTION 75-44 0-5.2 Load Increases PCN75-116. J. Straight pxesented this procedure change. It requested a new precaution be added to read; 4.3 If valve position limit light is lit on the E.H. panel, reduce load until light clears, and before turbine load increase commences, raise valve position limit back to 100%

The Committee recommended approval of this change.

75-45 M-11.4.1 Isolation of 1A Char in Pum For Maintenance And Restorin To Service After Maintenance. J. Straight presented this temporary change for review only.

It requested steps 4.4 through 4.9 and 5.1 through 5.8 be N.A.'d.

It requested also to change step 4.10 to read; motor varidi5c 4.10.1 - Remove damaged shifting .

assembly 4.10.2 - Install new shifting motor varidisc assembly including studs and ball bearing 4,10.3 - Insrall new shifr box upper oam followers NOTE: See Ajax. Iron Works Charging Pump with Motors and varidrive instruction manual for maintenance items.

The Committee reviewed this change.

75-46 E-12.1 Malfunctionin Rod Cluster Control. Fu11 Len th Rod, PCN75-42 E-12.2 Malfunctioning Part Len th Rod PCN75-43.

J. Straight presented these two new procedures. They were rewritten to conform to A-30 format, also to separate them from part 6 full length rods. The Committee recommended approval o f th is change. This item IS COMPLETE.

75-47 E-12, Malfunctionin Rod Cluster Control, PCN75-41. J . Straight presented this procedure change. It requested this procedure be deleted as it has been rewritten into 2 separate procedures.

The Committee recommended approval of this deletion.

75-48 CP-128.0, Calibration and/or Maintenance Of: Char, in, Line Flow Channel "128" PCN75-44. J. Straight presented this procedure change. It requested on the System Data Sheet, under Test Equipment to remove the S/N after Foxboro Current Simulator.

The Committee recommended approval of this change.

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hnnual Report I/ll of all procedure changes: (Continued) 1/1/75 to 12/31j75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-31 EM-136 Maintenance Of Non-Re enerative Heat Exchan er Com onent Coolin Water Valve TCV 130 PCN75-54.

S. Spector presented this new procedure. The purpose of this procedure is to describe the steps necessary to isolate TCV-130, perform necessary maintenance and return system to service. The Committee recommended approval of this procedure.

75-32 S-3.2E Establishin Normal Letdown PCN75-55.

J. Straight presented this new procedure to go from excess letdown to normal letdown. The Committee recommended approval of this procedure.

75-35 TCV-130 Tem erature Control Valve For The Com onent Coolin From The Non-re enerative }I'eat Exchan er. J. Noon reported to the Committee that after determining the cause of failure of the rubber seat in the valve Mr. George Coons, of R.M.Newell Co.

was contacted. R.M,Newell is the local representative for Continental (Fisher) Valves.

He has recently informed me that the seat is vulcanized to the valve body. This valve is not a shelf item and lead time is 30-36 weeks. He also cheeked alternative and stated the same style valve with a cast iron body and a metal seat. is available.

Xt has shutoff leakage of about 38 gpm and has a capacity well in excess of the 500 gpm in the original purchase specs. Since the valve is not required to provide shutoff isolation, this valve should be suitable, The method seat will provide a more maintenance-free valve. Mr. Coons is forwarding information on the metal seated valve to us.

75-36 GS-31.0, Door Alarm S stem,PCN75-38,75-118. J. Straight presented these procedure changes.

PCN75-38 << requested a new step 3.16.1 be added to read; "Doors 7 thru 14 and doors 19 thru 23 may be unlocked during normal wo king haurs at the discretion of the shift foreman. Door 25 will be unlocked by operating personnel around 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months Monday thru Friday, excluding holidays.

Door 24 will be unlocked by general office per-sonnel when the office is staffed, Monday thru Friday, excluding holidays unless advised other-wise by the shift foreman. The above doors will all be locked at 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months " unless advised other-wi se by the shift foreman.

PCN75-118 - temporary for review only. Requested to remove section 3,15 for period of printer maintenance.

The Committee recommended approval of PCN75-38.

Annual REport P11 of all procedure changes: (Continued) 1/1/75 to 12/31/75

't Inclusive PORC ITEM DESCRIPTION NUMBER:

PT-ll 60 Cell Hatter Banks "A & "B" PCN75-125. J. Straight 75-54 presented this procedure change. It requested to; Add under step 6.1.2; If batteryuse is placed M-38.

on equalizing charge The Committee recommended approval of this change.

Emer enc Di.esel ese Generator e 'Pre'-Start Ali nmo PCN75-133 7.5- 63 T-27.1 lA D T-27.2 1B Emer onc Diesel Generator Pre-Start Ali nmert PCN75-132.

J. Straight presented this procedure change. Changes were made to alignment check-off to provide better definition of switches which are to be checked. Tho Committee recommended approval of these changes, 75-64 PT6.3A Calibration Procedure Power Ran e Channels PCN75-134.

J. Straight presented this procedure change, It was reque srecommended ted thi procedure be deleted as CP-41 replaces it. The Committee approval of this deletion.

75-65 PT6.4 Excoro/Incore R6.calibration PCN?5-138. J. Straight presented this procedure change. It roques ted; Add new step 1 to read "The following steps may be marked N.A.

if Flux. Maps are generated by other.procedure, test shift foreman signatures are not required. Nuclear of operation, Engineer of alternate must note flux map number .used",

The Committee recommended approval of this change.

75-70. GS-31.0 Door Alarm S stem, PCN75-143. J. Str'aight pxcsonted this temporary change request. It was requested to romare section 3. 15 for period of printer maintenance. The Commi t too reviewed thi.s temporary chango.

75-71 J. Straight presented the following new procedures; RF-8.4 Fuel & Coro Com onont Movement In The S ont Fuel Pit PCN75-131. This procedure describes tho stops necessary to move fuel and/or coro components in the spent fuel pit.

RF-14.1.1 Thimble Retraction Procedure For Plant Rofuolint; PCN75-72. Thi.s new procedure describes tho steps to be taken in Flux Thimble Retrac'tion for refueling.

RF-14.1.2 Thimble Insertion Procedure For Plant Rofuoline PCN75-71. This new procedure describes the stops necessary to insert the flux thimbles into the core.

The above new procedures were recommended for approval by the Committee.

l Annual Report I/11 of all procedure 'changes; (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DHSCRIPTIO!r 75-50 CP-41 42 43 & 44 Calibration &/or Maintenance Of Power Ran e N41 42, 43 & 44 PCN75-50 51 52 & 53.

J, Straight presented these new procedures to replace PT-6.3A also to conform to A-30 format. The Committee recommended approval of these new procedures, 75-51 J. Straight presented the following CP procedures; CP-405 Calibration &/Or Maintenance of Delta T (Channel 1 PCN75-12 CP-406 Calibration &/Or Maintenance of Delta .T Channel 2 , PCN75-13 CP-407 Calibration &/Or Maintenance of Del.ta T Channel 3 PCN75-14 CP-408 Calibration &/Or Maintenance of Delta T (Channel 4) PCN75-15 Cp-405,10 Calibration &/Or Maintenance of 4 T SP-1, Module In Channel I, PCN75-30.

Cp-406.10, Calibration &/Or Maint'enance of 8 T SP-1, Channel- II, PCN75-32.

CP-407.10, Calibration &/Or Maintenance of QT SP-1 Channel III PCN75-31.

CP-408.10 Calibration &/Or Maintenance of 5 T SP-1, Channel IV PCN75-33.

The Committee recommended approval of these procedures.

75-52 PT-6.3A. Calibration Procedure power Ran e Channels, pCN75-123.

J. Straight presented this temporary change for review only.

It requested steps 14 through'7.6 'to be marked N.A. The Committee reviewed this change.

75-53 M<<38 E ualizin Char,e Station Batter S stems, PCN75- 124.

J. Straight presented this procedure change. It requested a new step 4.10 be added to read; 4.10- Take complete set of vo)tage and specific gravity readings of all cells and temperature readings of designated pilot cells. One week after the battery haa received an aqua>itin>, charge Dare

- 52-

Q~

Annual Report f!11 of all procedure changes (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUIIBER: DESCRIPTION 75-72 J. Straight presented the following procedures which were rewrites to conform to A-30 format; RF-17 Drive Rod Bow Measurement Procedure PCN75-60.

RF-25 Movement of Irradiated Flow Mixers Mitl> Rack Inserts,PCN75-58.

RF-14.8 Procedure For llandlin Cast DOT 55-14300 PCN75-64.

RF-14.5 Fuel Ilandling Durin Ins ection In The S ent Fuel Pit: PCN75-67.

RF-9s16 Lower Core Su ort Structure Removal & Re lacement PCN75-79.

RF-9.14 Irradiation Sam le Ilandlin Tool 0 eratin Procedure PCN75-81.

RF-9.8.2 Part Len th P/L) Control Rod Drive Shaft Relatchin PCN75-90.

RF-9.8.1 Part Len th P/L) Control Rod Drive Shaft Unlatchin PCN75-91.

RF-4.0 Site Removal Of New Fuel Assemblies From Shi in Cont:ainers And Ilandlin Of Shi in Containers PCN75-107.

RF>>9.15 New Fuel Handlin Tool 0 eratin Procedure PCN75-80.

RF-2 Reactor Refuel. in Outa e 0 eraeions and Activities PCN75-114.

RF-9.2 Fuel Transfer S stem PCN75-97.

RF<<9.4 Thimble Plu llandlin Tool PCN75-95.

RF-9.7 Burnable Poison Rod Assembl Ilandlin Tool 0 eratin Instruction PCN75-92.

RF-9.13 Core Ha After Fuel Loadin PCN75-82.

RF-8.3 Core Loadin Periodic E ui ment Status Check PCN75-100.

RF-8.1 Ste b See Fuel I.oadin Se uence and Ma s PCN75-102.

RF<<9.3 S ent Fuel Assembly llandlin Tool PCN75-90.

RF-9.5 RCC Chan e Fixeure PCN75-92.

RF-6.0 Ilandlin Of Burnable Poison Rod Assemblies PCN75-105.

RF-8.0. Fuel Assembly & Core Com onent Movement Prere uisities &.

& Precautions PCN75-103.

RF-10.0 Fuel Transfer S stem Checkout & Demonstration Procedure PCN75-78.

RF- ,12.2 Assembly Of Instrument Port Conoseals PCN75-85.

RF-9.6 Guide Tube Cover llandlin Tool 0 crati.n Inseruceions PCN75-93.'F-3.0 Fuel Assembl & RCC Re leeeeient PCN75-108.

The Committee recommended approval of these rewrites.

75-73 1%-11.1 Dro in Of A New VOo Fuel Assembl Or Col.lision Of A New VO I'ucl Assembly Wield Another Ob'ect PCN75-76.

RF-11.2 Dro in Of A New PO Fuel Assemhl Or Collision Of. A New PO 0 VO Fuel Assembl Mich Another Ob 'ect PCN75-75.

RF-11.3 Dro in Of A S ent Fuel Assembly Or Rod Control Cluster Or Collision Of A S ent Fuel Asscmbl Or Control Cluster Hit:h RF-11.4 Sticki Of A I'uel Asscmbl Inside The Reactor Vessel Or Inside The Transfer Basket PCN75-73.

The Committee disapproved tliese change request:s as it was the recommendation of. t: he PORC that these procedures be written a E's ~

t Annual Report II11 of all procedure changes: (Continued) 1/1/75 to 1?/31/75 Inclusive PORC ITEM NUMBER:

DESCRIPTION 75-74 RF-15 Fuel Ste I'te PCN75-62.

Loadin Used Burnablc Poison Rods Into Used RF-16 Ste 8 Ste Chan e In Location Of Radio active Material In S ent Fuel Pit PCN75-6l.

I J. Straight presented these procedure changes. It was the recommendatio:

of the Committee that these two procedures be deleted as this in-formation is incorporated in A-4.

The Committee recommended approval of these deletions.

75-77 T-25 Instrument And Control Bus PCN75-135. J. Straight presented this procedure change. This change request was to incorporate steps from S-20. This item IS COMPLETE.

75-78 S-20 Instrument Busses PCN75-136. J. Straight presented this procedure to the Committee for deletion. It was requested to delete this procedure as it is being incorporated in T-25.

75-80 M-37.16A Ins ection & Maintenance Of Manual '0 crated Crinnel Dia hra m Valves PCN75-158 & PCN75-1.6l..

J. Straight presented this procedure change.

PCN75-161- requested to change second line of step 5.8 to read; "tighten bonnet nuts (with torque wrench if possible)"

PCN75-158 - requested to change in 5.1, "M-37.16 series to H-7.4" The Committee recommended approval of this change.

PT-22.1 E ui ment Hatch Door Seal Leakrate Test PCN75-147.

75-82 J. Straight presented this procedure change. It was requeste d the follow'ing be added; Equipment lock door seal leak rate test add; 6.3.1 - Turn outer hatch door hand wheel 1-3/4 turns open.

I remove: note pa ge PT- 22. 1: 2 add; 6.26.1 - Resecurc hatch door by turning hand wheel 1-3/4 turns closed.

add: 6.35.1 - Turn outer hatch door handwheel 1-3/4 turns open.

add: 6.40.1 - Resecure hatch door by turning handwheel 1-3/4 turns closed The Committee recommended approval of this change.

" 54

Annual Report Pll of all procedure changes: (Continued) I/1/75 tv 12/31/75 Inclusive NUMBER'ESCRIPTION PORC ITEM 75-83 PT-22.2 Personnel tlatch Door Seal l.eakrate Test PCN75-148.

I J. Straight presented this procedure change. It was requested the following steps be added; add: 6.3.1 - Turn outer hatch door handwheel 1-3/4 turns open.

I drop: Note on page PT-22.2:2 add: 6.25.1 - Resecure hatch by turning handwheel 1-3/4 turns closed.

add: 6.39.1 - Resecure hatch by turning handwheel 1-3/4 turns closed.

The Cormnittee recommended approval of this change.

75-84 M-45.1A Ins ection of Safe Guard Motor For PCN75-172 6 M-45.3 Ins ection Of Non Safe uard Motor For PCN75-171.

J. Straight presented this procedure change. It requested to move step 5.13 up to follow step 5.9.3. The Cormnittec recommended approval of this change.

75-88 RF-8.4 Fuel And Core Com onent Movement In The S ent Fuel Pit PCN75-174. J. Straight presented this temporary change to be made permanent. It was requested to change step 4.1 in precautions to step 3.10 in initial conditions. The Cormnittee recormnended approval of this change.

75-93 E-37.1 Dro pin Of A New UO Fuel Assembly Or Collision Of A New UO Fue Assem ly Hit > Another 0 ject, PCN E-37.2 Dro in Of A New PuO -UO2, Fuel Assembly Or Collision Of A New PuO -UO Fuel Assembly With Another Ob'ect PCN75- 154.

The Committee recommended disapproval of these procedures as they ax'e not ones we need.

E-37.3, Dro ing Of'A S ent Fuel Assembly Or Rod Control Cluster Or Collision Of A S ent t:uel Assembl Or Rod Control Cluster With Another Obicct, PCN75-155.

E-37.4, Stickinp Of A Fuel Assembly Inside The Reactor Vessel Or Inside The Transfer Basket, PCN75-156.

The Committee recormnendcd approval of these new procedures.

55 "

Annual Report (tll of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive NUMBER'ESCRIPTION PORC ITEM 75-94 J. Straight present:cd these procedures, which are rewrites to conform to A-30 format.

RF-9.9 Control Rod Drive Shaft Vnlatchin Tool 0 eratin Ins true t ion, PCN75-89.

RF-9. 10 Head Liftin Ri 0 eratins Instruction, PCN75-88.

RF-9.11 Interals Liftin Ri. 0 cratin Instruction,

~ PCN75-87.

RF-9.12.1 Disassembl. Of Inst:rument Port Conoseals, PCN75-86.

RF-1 Refuclin Or anization PCN75-115.

RF-2A Rc uircmcnt For Reactor Ilcad Removal PCN75-113.

RF-2l3 Re ui.red Valve l.inc>> For Reactor Head Removal PCN75-112.

RF-2D Fillin Of The RefuelinS Canal PCN75-111.

Rl'-2E Drainin Of Rcfuelins Can-.l PCN75-110.

RF-2F Reactor Cavit Filtcratior. S stem 0 eration PCN75-109.

RF-8.2 1'ucl Handlin Instruction Pre-Loadin & Periodic Valve Tes t PCN2,5-101.

RF-14. 6 Air Educ tor 0 era tin Procedure, PCN75-66.

RF-5.0 Fuel Handlin Instruction Limitations And Precautions For Handlin New & Part iall S ent Fuel Assemblies, PCN75-106, RF-9.0 Refuelin E ui ment 0 eratin Instructions List, PCN75-99.

RF-9.1 Mani ulator Crane PCN75-98.

RF-9.12.3 Disassembly Of The Part Len th Control Rod Conoseals PCN75-84.

RF-9.12.4, Assembl Of The Part Len th Control Rod Conoseals, PCN75-83.

RF-10.1 Auxiliar Building Crane Interlock Checkout, PCN75-77.

The Committee recommended approval of these rewrites.

75-98 PT-22.10 Mechanical Manifold "C" Leakrate Test PCN75-182.

J . Straight presented this procedure change. It was requested step 4.3 be deleted, step 6.4 read, "approx. 60 minutes", and step 6.11 read; "record ambient temperature at penetration and time" S-2.3 Pressurizer Relief Tank Control PCN75-184. J. Straight 75-100 presented t:his procedure change. This was a rcwritc to conform to A-30 forma t:. Thc Commit: tec recommc>>dcd approval of this change.

56-

Annual Report //ll of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM

.'NUMBER:

75-102. CS-31 Door Alarm System, PCN75-157 PCN75-1.95.

J . Straight presented these procedure cliangcs .

PCN75-157 - 3.16.1 - Door 4G may be deactivated from 0200 L'o 2400 liours Monday through Friday and at any other time wlien the area is considered manned. Under these conditions tlie requirements of 3.10 and 3.10.1 do not apply.

PCN75-195 - change 3.14 - the sliift foreman or head conLrol operaLor shall initial all printer entries for identified door alarms and defeated doors indicating lie is aware of the reason for the activity. Unidentified door alarms shall be handled as outlined in 3.11 tliru 3.13.

change 3.14.1 - eliminate words "alarm logs" eliminate door alarm system - daily log sa.;.pl The Committee recommended approval of this change.75-107 M-<<0 Surveillance 6 1faintenancc 01 11 draulic Sn<<l>hers, PCN75-196.

J. Straight presented this procedure change'. It was requested snubbers fh1S-179 and MS-180 be added to the list. The Committee recommended approval of this change. This item IS COMPT.ETE.75-109 RSSP-12. Testin Of Primar 6 Secondary Relief Valves On Test "Stand PCN75-179. J. Straight presented this procedure change .

It was requested; Add to precautions 5.2 - test medium should be air for a valve which is used on gas or vapor service and air or water for one used on liquid service. Also on page five after R.V. 1818-RG6 E should be 1100 psi.

The Committee recommended approval of this chango.

J. Straight presented these Leo new procedures;75-111 M 60.1 'ctor 1e Tri

'1'ri!

Undervol ta e Protection Vn<larvoltere Prot<ation Pius 1 lA 1111 PCN75-193.

PCN75-1!)<<.

N-60.2 Nrnctor 11ns Tlicse procedures outline the step: for removing and replacing corrective

'Qc 'iv relays 273/llB and 274/llB for calibratioo or rotective pro maintenance. Tlic Committee rcconuncndcd approval of tlicsc procedures.

Annual Report //11 of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 1C Safet In'ection Pumi Circuit Breaker Maintenance & Ins ection 75-115 PCN75-230. B. Snow presented this proceclurc change. It was requested to add bus 14 where bus 16 appears. Also requested a note be added to read; "This procedure is written for both breakers. If only one breaker is being inspected, other steps for other breaker maybemarked N.A."

The Committee recommended approval of this chango.75-119 0-6 0 eration & Process Monitorin PCN 75-218. J. Straight presented this procedure change. It was requested to change step 5.10 to read; The computer is programmed to monitor conformance of flux difference band operating limits in the Technical Specifica-tions. One program alarms to indicate non conformance with the +5% flux difference band around the target valve for operation at power levels greater than 90% of rated power.

The other program alarms to indicate non conformance ~~ith the limit ori time (1 hr. in 24) that the 5% flux di fference band may be exceeded for ope ".tion at or below 90% of rated power.

If these programs are ri operable, the flux difference shall be logged hourly for the first 24 hrs. and half-hourly there-after.

The Committee recommended approval of this change.75-122 , RSSP-10.1 Conditions For Main Steam Safet Valve Test, PCN 75-209. J. Straight presented this procedure change.

It was requested to delete steps 4.5 & 4.7, also to add at end of step 6.1 "or by condition steam damp". The Committee recommended approval of this change.

I I

Annual Report F11 of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-123 John Straight presented the following new RF procedures:

RF-42 Television Visual Fuel Assembl Ins ection PCN 75-211.

This procedure is to outline the scape and the examination instructions for fuel inspection program. This will consist of television visual examination of selected fuel assemblies and will be performed in the spent fuel pit.

RF-43 Fuel Rod Len th Measurements PCN 75-213. This proce-dure describes the steps necessary to perform fuel rod length measurements of irradiated fuel.

RF-44 Fuel Rod Diameter Measurement PCN 75-214. This proce-dure describes the steps necessary to perform fuel rod diameter measurements of irradiated fuel.

RF-45 Fuel Assembl Bow Measurement PCN 75-215. This proce-dure describes the steps necessary to perform fuel assembly bow measurements of irradiated fuel.

The Committee recommended approval of these procedures.75-124 SC-1 Radiation Emer enc Plan PCN 75-139. J. Straight pre-sented this procedure change. It was reque'sted that on appendix A, E, and K to omit note at bottom of page. "The general office will update this call list on a quarterly basis." The Committee recommended approval of this change.75-125 PT-17.2 Process Radiation Monitors R-ll - R-20 Iodine Monitors R10A and R10B PCN 75-226. J. Straight presented this procedure change. It requested step 6.5.13 should read as follows:

- operating vent valve 1581.

Step 6.5.19 change 4.5"of water to 5.0"of water.

Step 6.6.14 Change 4.5 " of water to 5.0" of water.

The Committee recommended approval of this change.75-132 T-36.1 Station Service Water lleader Valve Ali nmcnt 'for Two Lope 0>eration PCN 75-206. J. Straight presented this ncw procedure. This procedure is to provide procedural coverage, to describe the valve alignment necessary for two loop operation. lhe Committee recommended approval of this procedure.

- 59

Annual Report I/ll of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-138 M-43.6 Installation of Cover On Permanent Rin On Stcam Generator Loo Nozzle PCN 75-241 PCN 75-233. J . Straight presented this procedure change.

PCN 75-241 - was to facilitate step 5.10.5 marked N,A.

PCN 75-233 - new step 3.9 to read; In the event that refueling will not be conducted concurrent with - S/G work, the following steps may be marked NA 3.10, 3.11, 5.1, 5.4, 5.6, 5.8j 5.9.

Renumber present steps 3.9 and 3.10 to 3.10 and 3.11.

Step 5.7 - delete words "all hold down' delete 20

- add sentence; All studs must be used if refueling is to be, conducted con-current with S/G work, otherwise a minimum number of (4) will be sufficient.

The Committee recommended approval of this change.

M-43.13 Removal of Steam Generator Permanent Rin Loo Nozzle 75-139 Cover PCN 75-242. J. Straight presented this procedure change.

It was requested; Step 5.2 - delete number 20 Step 5.4 - insert after bars, if used, and pass outside.

Remove steps 5.7 and 5.8 Step 5.10 - add "if used" Step 5.11 - add "if used" The Committee recommended approval of this change.

1 75-140 M-43.25 Installation of Steam Generator Handhold Cover PCN 75-244.

M-43. 26 Installation of Steam Genera tor Secondar tfanwa Cover PCN 75-243.

J. Straight presented this procedure change for both above proce-dures. A figure sheet has been added to these two procedures.

The Committee recommended approval of this change.75-141 EM-75 1C Safe't In ection Pum Circuit Breaker Maintenance &

Ins ection PCN 75-240. J . Straight presented this temporary change for review. This PCN was to facilitate the N.A. of step 5.3. The Committee reviewed this temporary change.

Annual Report fI11 of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-142 P-9 Precautions Limitations & Set oints P-9 Radiation Monitorin S stem PCN 75-762 PCN 75-245. J. Straight presented these procedure changes.

PCN 75-762 requested; step 2.3.2.2 regarding R-11 setting with Containment Isolated; change to read:

"7X10 CPM is Sufficient For Operations,"

Also change R-11 setpoint on page P-9:6 for temporary review only.

PCN 75-245 requested: step 2.3.2.2 regarding R-11 setting with Containment Isolated; change to read:

"5X105 CPM is sufficient For Operations,"

Also change R-11 setpoint on page P-9:6 to be made permanent.

The Committee recommended approval of PCN 75-245 and reviewed PCN 75-762.

75-143 S-4.1A Li uid Haste Process Startu PCN 75-231. J. Straight presented this procedure change. It was requested to delete step 7.8 also to rewrite into A-30 format. The Committee recommended approval of this change.75-144 S-4.1C Li uid Haste Process 0 eration and Shutdown PCN 75-232.

J. Straight presented this procedure change. It was requested to delete last sentence in step 4.2, add a new step 4.10 to read:

"When boron approaches 10%, verify drums ready per S-4.1D thru steps 4.8 Also a note to be added to read:

NOTE: If evaporator is to be stopped due to lack of chemistry coverage or full waste condensate tanks, put on reject.

The Committee recommended approval of this change.75-145 GS-31 Door Alarm S stem PCN 75-228 PCN 75-246. J. Straight presented those procedure changes.

PCN 75-228 - request to change data sheet to remo'c door alarm number 49.

PCN 75-246 requested; 3.16 alarms on doors 7 thr ugh 14,, 19,20, 22, 24, and 25 Annual Report //ll of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-148 J. Straight presented the following CP's for changes:

CP-41.0 PCN 75-248 CP-41.1 PCN 75-249 CP-41.2 PCN 75-250 CP-41.3 PCN 75-251 CP-41.4 PCN 75-252 The procedures were put in check-off form, also consolidated the components into one larger procedure. The Committee recom-mended approval of these changes.75-150 RF-8.4 Fuel Q Core Com onent Movement In The S ent Fuel Pit PCN75-261. J Straight presented thia .procedure change.

a new shuffle sheet be added.

It requested The Committee recommended approval of this change.75-151 SM75-3.2 Steam Relief Vent Pi Su ort Ste'el & Concrete PCN75-229. J. Straight presented this temporary procedure change for review.

Pg. 2 - Delete Jan. 18, replaced with Jan. 22 Pg. 7 <<Delete E-9, except for final backup---

Pg. 8 - Delete E-13, --- the final bol tup of steps has been completed---

E-13 --- add removed and the three --<<

The Committee reviewed this change.75-152 T-18B Turbine Main Steam Sto Valves Test PCN75-257. J. Straight presented this procedure change. This PCN was to facilitate steps that were marked N.A. The Committee reviewed this change.75-153 E-38 Loss Of Service Hater PCN75-205. J. Straight presented this new porcedure. This proc'edure describe operator actions to be taken in the event of loss of service water. The Committee recommended approval of this procedure.75-154 PT<<9 Undervolta e & Underfre uenc Protection llA & llB 4160 Volt Busses PCN75-258. J. Straight presented this procedure change.

This request was to add to existing steps of procedure as follows:

6.1.1 and 6.2.1 - (knife switch /P2) 6.1.2, 6.2.2, 6.3 Jl, 6.3.7, 6.4.1, and 6.4.7 (knife switch 88)

The Committee recommended a proval of this change.

I a ms ~ i~ ~ sns l s I

Annual Report Il11- of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEN NUMBER: DESCRIPTION PT>>12.1 6 PT-12.2 Emer enc Diesel Generator on 1A and 18 75-155 PCN75-259 PCN75-260. J . Straight presented these two procedures for the same change, It was requested; Add note after step 6.2 as follows:

NOTE: Zf this procedure is being used'o perform post-maintenance reliability check, mark steps 6.2.l through 6.2.7 N.A. and continue with step 6.3.

The Committee recommended approval of this change.75-156 RSSP-ll Pressurizer Safet Valve Test PCN75-265. J. Straight presented this procedure change. It requested a new step 3.4 be added to read; 3.4 <<Crosby Nozzle Relief Valves, Inst. Book No. 20 Installation, Maintenance and Adjustment Also several minor changes were requested..The Committee recommended approval'f this change.75-157 RSSP-12 Testin 'of Primar 6 Secondar Relief Valves On Test Stand PCN75-264. J. Straight presented this procedure change. - It requested ths following be added at the end of step 6.2; Flush water through stand until water at drain valve is clear 75-164 ~it specifications 3.1.2, 3.1.3, 4.2, plus table changes 3.1-1, 3.1-2.

Bob Eliasz presented this proposed Technical Specification change to the Committee for review. There were no unrcviewod safety questions and the Committee recommended approval of these Tech-nical Speciiication changes.75-172 17nderfr~cllanc Protection Eus ala N 60 3 Roacto~rTri PEN 280. J. Straight presented this new procedure pertaining to calibration or corrective maintenance of this on pro-Bus llA. The Committee recommended approval cedure,

-es ~

Annual Report 811 of. all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION I

M-60.4~Reactor Tri~UndcrZrc ucnc Protection Bus 1lg PCN-75-231.75-173

'r J. Straight presented this new procedure pertaining to calibration corrective maintenance approval of. the procedure, on Bus llB. The Committee recommended This item IS COMPLETE;75-174 seated this procedure change as follows:

Step 4.1.2.2 - Insert" the word "starts" at end of sentence.

Step 4.1.2s4 - Insert the word "starts" at end of sentence.

ADD: New step 4.2.1 and change numerical sequence thereafter.

Step 5s8 changed to read: Maintain reactor in a safe shutdown state by referring to operating instruction, 0-3> "Plant At Hot Shutdown with Xenon Present".

Also add new Step 5.10.

The. Committee recommended approval of this procedure change.75-175 T-35C Auxiliar Unit PCN-75-270..

and lntcrmadiate B~uildin

. l ~*

Ventilation J. Straight presented this procedure S stem change.

Step 5.5.3 - change monometer reading to .36 from .2.

The Committee recommended approval of this change.75-176 ~fns ection~PCN-75-322. 3. Straight presented this procedure change. It was requested that Step 5.1 to 5.1.4 be changed to provide procedural coverage for 'further investigation into breaker problem.

The Committee recommended approval of this procedure change.

Annual Report //11 of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER'ESCRIPTION 75-177 J. Straight presented the following CP procedures:

CP-42.0,Calibration and/or Haintena'nce of Power Range N-42, PCN-75-298.

CP-42.1, General Defeat Procedure for N-42, ZCN-75-299.

CP-42.2, General Reinstate Procedure for N-42, PCN-75-300.

CP-42.3, Calibration of Power Range N-42, PCN-75-301.

CP-42.4, Calibration of Power Range N-42 Bistable Relay PCN-75-302.

CP-43.0, Calibration and/or 1faintenance of Power Range N-43, PCN 75-303.

CP-43.1, General Defeat Procedure for N-43, PCN-75-304.

CP-43.2, General Reinstate Procedure for N-43, PCN-75-305.

CP-43.3, Calibration of Power Range N-43, PCN-75-306.

CP-43.4, Calibration of Power Range N-43 Bistable Relay Drivers, PCN-75-307.,

CP-44.0, Calibration and/or Maintenance of Power Range N-44, PCN-75-308.

CP-44.l, General Defeat Procedure for N-44, PCN-75-309.

CP-44.2, General Reinstate Procedure for N-44, PCN-75-310.75-181 GS-31.0- Door Alarm S stem PCN-75-33~0also 22S 246. 330$

J. Str'aight presented further changes to this procedure (in the interim Rev. 86 never issued due'o additional PCN's) (75-320 and 75-330).

The Committee recommended approval of this change.75-182 A-52.2 Control of Locked Valve 0 aration PCN-75-263.

J. StraiSht presented this nau procedure. The purpose of this procedure is to describe the requirements for a locked valve.

The Committee recommended approval of this procedure.

I Annual Report fall of all procedure changes: (Continued) 1/1/75 to l2/31/75 Inclusive PORC ITEN NUHBER: DESCRIPTION 75-207 S-23.2.2 Containment Pur e Procedures PCN-?5-284.

J, Straight presented this procedure change. It requested in step 5.2 to change the following;

l. Open PEVO purge exhaust valve outlet to open PEVO purge exhaust valve outside V-5879.

2, Open PEVI purge exhaust valve inlet to open PEVI purge exhaust valve inside V-5878.

3. Open PSVO purge supply valve outlet to open PSVO purge supply valve outside V-5869.

4. Open PSVI purge supply valve inlet to open PSVI purge supply.

The Committee recommended approval of these changes.75-208 T-27.1 1A Emer enc Diesel Generator Pre-Start Ali nment PCN-75-272. J. Straight presented this procedure change.

It requested a valve number change. The Committee recom-mended approval of this change.75-209 A-2.8 S ecial Nuclear Material Inventor 6 Record Re uircments PCN-75-273. J. Straight presented this procedure change. This requested; Attachment A Item 1 changed to read: "Filled out and and signed by Quality Control Inspector Level II."

The Committee recommended approval of this change.75-213 PT-1?.2 Process Radiation Nonitors R-ll - R-20, Iodine lfonitors R-]OA and 1<-108 PCN-75-331. J. Straight presented this procedure change. This change requested steps 6.3.12, 6.4.12, 6.5.ll, 6.6.9 be added.

The Committee recommended approval of this change.

Annual Report 811 of all procedure changes: (Continued) 3/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION PT-23.37 Reactor Com axtmcnt Coolin Unit "A" PCN-75-278.

75- 215 purpose oi J. Straight presented this ncw procedure. ofThc Reactor Compartment:

this procedure is to test leak tight:ness Cooling "Unit A".

The Committee recommended approval of this procedure. I d SSe uence Test,75-216 -2 RSSP-2.2 D'~ese Generator Load and Safe uard cedure chan e.

359. J. Straight presented thxs added, pro PCN-7 also to delete It requested new steps 2. 4 thru ru 2.7 be the first line. in the NOTE.

appxov al of this change.

The Committee recommended Water Pi in 75-21? M 17 Isolate'on and Relocation of Reactor ffakeu procedure. The PCN-75-328. J. Straight presented this new the steps necessary purpose of this procedure is to descxibefor maintenance.

to isolate reactox makeup water piping The Committee'recommended approval of this change.75-218 M-48.5 Isolation of Bus 17 PCN75-429.. J. Straight presented this new procedure. The purpose of this procedure is to describe steps necessary to isolate Bus 17 for cleaning and breaker main-tenance including a list of work performed. The Committee re-commended approval of this procedure.75-219 S-3 .3D, CVCS Cation Demineralizer Bed 0 eration Usin The A Deboratin Unit) PCN75-403. J . Straight presented this procedure change. This change requested that valve numbers be changed, as valves associated with lA deborating demineralizer were incorrectly assigned to be 1B demineralizer. The Committee recommended approval of this change.75-220 S-25.4 Steam Generator: Draininp The A and/or B Steam Generator To Blowdown Tank, PCN75-411. B. Snow presented this new procedure. The purpose of this proceduie is generator to describe operations necessary to drain 1A or 1B steam to the steam generator blowdown tank and transfer to the blow-down tank water to the monitor tank via waste condensate polishing D. I.'s. The Committee recommended approval of this procedure.75-221 S-12.1 Leaka e Detection Systems Pre-Startu, PCN75-316.

J. Straight presented this ncw procedure. This procedure provides the necessary conditions to ensure proper leakage detection systems necessary for operation are operable, The Committee recommended approval of this procedure.

\

Annual Report //ll of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-222 RSSP-2.1 Safet In'ection Functional Test PCN75-400. J. Straight presented this procedure change. This was a rewrite to A-30 format with a new step 4.8 added to read; "all prealignment sheets have been completed" The Committee recommended approval of this change;75-223 PT-23.38 Reactor Com artment Coolin Unit "B" PCN75-279.

J. Straight presented this new procedure. The purpose of this procedure is to test the leak tightness of reactor compartment heat exchanger and manual isolation valves 4635 & 4636. The Committee recommended approval of this procedure.75-224 RF-8.4, Fuel 6 Core Com onent Movement In The S ent Fuel Pit PCN75-405. J . Straight presented 'this procedure change. It requested the Fuel )landling Data Sheet have some figures added.

The Committee recommended approval of this change.

\

75-225 RF-8.1 Ste B Ste Fuel Loadin Sec uence And Ha s PCN75-406. J. Straight presented this procedure change. This requested a new schedule bc added using step by step fuel load sequence and maps. The Committee recommended approval of this change.75-227 M-43.8 Edd Current Ins ection Of Steam Generator Tubes, PCN75-441. J. Straight presented this procedure change.

It requested removing present attachment A and replacihg it with a new attachment A (H MRS 2.4.2 GEN-9, Eddy Current Inspection Of Steam Generator Tubes). A new attachment A will be added to this procedure. 00 MRS 2.4.2 GEN-5, Positive Identification of Steam Generator Tubes By Eddy Current Inspection).75-230 H-37.34, Maintenance Of Hain Stcam Power 0 crated Relief Valves 3410 or 3411 PCN75-388. J. Straight presented this new procedure.

This procedure describes the steps necessary to isolate, inspect and repair power operated relief valve 3410 or 3411. The Committee recommended approval of this procedure.75-233 75-1.1 Instrument Relocation-Intermediate )31d PCN 75-336.

SM J. Straight presented this temporary procedure change. It requested:

Step H-6 and H-7 to be done aft'er E-l and before H-2.

The Committee reviewed this temporary change.

Annual Report /Ill of all procedure changes: (Continued) 1/1/75 to Inclusive PORC ITEM NUMBER: DESCRIPTION 75-234 M-45.4 Ins ection oF. Safe uard Valve Motors, PCN 75-367.

J. Straight presented this new procedure. The purpose of this procedure is to describe the instructions necessary for removal of a safeguard valve'motor from service and for performing inspections and repairs.

The Committee recommended approval of this now procedure.75-235 A-46 B ass of Safet Function On Jum er Control, PCN 75-408.

J. Straight presented this procedure change. It requested to~

Add to step 3 2.3: At .cold shutdown, the PORC review requirement will not be necessary for those engineered safety features at reactor control and protection systems whose functions are not required.

The Committee recommended approval of this change.75-236 S-25.4 Steam Generators: Drainin A and /or B Steam Generator to Blowdown Tank PCN 75-437. J. Straight presented this procedure change. This change was to correct mislabeled .value numbers.

The Committee roconnnendod approval of this change.75-237 SM 75-3.3, Revisions To Roheater Relief Vent Pi e PCN 75-402.

,J . Straight presented this temporary change to be made permanent.

It requested the following chang'cs:

I Change step E<<3 to read as follows: The plant is in cold shutdown condition and Ell valve 6963, main steam STOP valves bypass valves 3545A, 3544A have been tagged as "marked up" by cognizant RGGE engineer.

Change step E-4 to read as follows: The undersigned has verified that valves 6963, 3545A, 3544A have been tagged as "marked up" by the RG&H Hngic>oor.75-238 M-11.10 Ma'or Ins ection of Service Mater Pum s PCN 75-428.

J. Straight presented this procedure change. It requested; Add step after 5.3: Measure distance from top of shaft nut to shaft, loosen nut and drop shaft until in bottom, then take measurement. Record this total shaft drop.

Add step after 5.32: Raise shaft .125" off. bottom.

The Conanittoo recommended approval of this chango.'69-

Annual Rcport Ijll of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEN NUMBER: DESCRIPTION 75-240 0-2.2 Plant Shutdown 1:rom Ilot Shutclown PCN 75-401.

J. Straight presented this procedure change. It requested the following changes:

llydrogen Peroxide should be added to thc primary system while there is still a RCP in service and after the system has cooled to 200 F, Enough H202 should be added t:o obtain a positive re-sidual as determined by the chem. lab.

also a note to be added; NOTE: (to be inserted after 5.25)

If this cooldown is for a refueling outage, add Hydrogen Peroxide and maintain at least one Reactor coolant pump running until proper residual is det:ermincd by the Chemical Lab.

5.25.1 Secured the running reactor coolant pump at approximately 150 F.

The Committee recommended approval of these changes.Sharav 75-241 PT-23.1SA. Cont:ainment Isolation Valve l.cak Rate Tc.stin "A" Containment S ray llcaclcr. PCN 75-424, ancl PT 23.1811. Containment Isolation Valve I.cak RAte Testint, "B" Containment lleadcr PCN's requested;

~43Q Step 6.8 Delite words "close valve 8698" insert the following words "Close test valve 2859 at conn. Bl 2'~~~

Step 6.8 Delite words "Close valve 869A insert in its place the following "Close test valve at valve 82857 conn. Bl ctc.

The Committee reconnnended approval of this change.75-244 PT-27 Containment Tendon Strcssin this new procedure. This procedure is toJ. provide PCN 75-407. Straight presented necessary for performing the Containment Vessel (CV) Tendon steps Lift Off Test.

The Committee recommended approval of this new procedure.75-245 P-1 Precautions Limitations and Set: pints P-1 'Reac-tor Control and Protection S stem PCN 75-542.

J. Straight presented this procedure change. There were several changes to conform to a change in thc Reac-tor Coolant Syst:cm prcssure sctpoints. The Connnittee rec-ommended approval of this change.

I 70

I Annual Report f/11 of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM 5QMBHR: DESCRITPTION 75-246 J. Straight presented the following CP's for the following changeq It was requested to increase primary loop pressure from 1985 psi to 2235 psig per Mcstinghouse functional analy-sis II ~

CP-10.0 CaliBration and/or Maintenance or Delta Flux Controllers PCN 75-578.

CP-20.0 Calibration and/or Maintenance of Delta Flux Controllers PCN 75-579.

CP-30.0 Calibration and/or Maintenance of Delta Flux Contxollers Channel 3 PCN 75-580.

CP-40.0 Calibration and/or Maintenance of Delta Flux Controllers PCN 75-581.

CP-405. 10 Calibx'ation and!ox Maintenance of TSPl Channel 1 PCN 75-544. The Conunittee recommended approval of these changes. This item IS COMPLETE.75-247 The following CP procedure changes were, presented by J.

S traight.

CP-429.0 Calibration and/or Maintenance of Pressurizer Pressure Channel "429" PCN 75-545, requested an update on the latest Pl change.

CP-429.6 Pressurizer Prcssure Bist:able PC-429A PCN 75-546 CP-429. 7 Pressurizer Prcssure His table PC-4298 PCN 75-547.

Both PCN's requested to change set:point 2185 psig = 44.25 MA.75-248 J. St:raight presented all the following CP's ior a change in thc setpoints, per P I, Rcv. XII.

CP-429.8 Pressurizer Pressure Bistable PC-429 C/D PCN 75-

~

548.

CP-429.9 Pressurizer Pressurizer Bistable PC-429E PCN 75-.

549.

CP-430 Calibration and/nr Maintenance 430 Pressurizer Prcssure Channel PCN 75-550.

-71<<

I Annual Report //11 of all procedure changes: (Continued) 1/1/75 to ] 2/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-248 CP-430.6 Prcssrrrizer Pressure Bistable PC-4'30A PCN-75-551 (Continued)

CP-430.7 Pressurizer Pressrrrc Bistable PC-430 E/P PCN 75-552 ~

CP-430.8 Pressurizer Pressure Bi.stable PC-430ll PCN 75-553 CP-431.0 Calibration nnd/or Maintenance of Pressurizer Pres-sure Channel "431" PCN 75-554.

CP-431.6 Pressurizer Pressure Bistable PC-431A PCN 75-555 CP-431.7 Pressurizer Pressure Bistable PC-431 PCN 75-556 CP-431.8 Pressurizer Pressure Bistable PC-431.7 PCN 75-557 CP-449.0 Cnlibration and/or Maintenance of Pressurizer Press-ure Channel "449" PCN 75-558 CP-449.6 Pressurizer Pressure Bistable PC-499A PCN 75-559 CP-499.7 Pressurizer Pressure Bistable PC-449B PCN 75-560 CP-407.10 Calibration and/or Maintenance of TSP1 Channel 3 PCN'5-561 CP-408.10 Calibration nnd/or Maintenance of A TSP1 Chnnrrel 4 PCN 75-562 CP-408.20.0, Calibration nnd/or Maintenance of TSP2 Channel 4 PCN 75-563 CP-406.20.0 Cnlibrnt:ion nnd/or Maintenance of - ATSP2 Clranncl 2 PCN 75-565 n d n Hn'ntcnnnce of TSPl C)ranncl 2 PCN 75-566

"'/

1 PCN 75-567 CP-404.6 T Av Bist:rblc TC - 404 A PCN 75-568 CP-403.0 Calibration nnd/or Hnintcnancc of T Avr . Channel "403",

PCN 75-569 CP-402.6 T Av . Bi.stable TC - 402A PCN 75-570 CP-402.0 Calibrat:ion arrd/or Hnintcnnncc of T Av~ Channel "402",

PCN 75-571 CP-404.0 Calibration anrl/or Haint:cnancc of T Av . Clrannel "404",

PCN 75-572.

Thc Committee rccommendcd approval of tlrese chnngcs.

- 72"

Annual Report 811 of all procedure changes; (Continued) 1/1/75 to 12/31/75 InclusLve PORC ITEM NUMBER: DESCRIPTION 75-249 CP-401.6 T Av . Bi.,Lable TC- 40l A PCN 75-573 1

J. Straight prcscntcd the following procedure change. It request-ed to change data sheet to read; Hi h Tav 578 F = 30.26 MA Thc Committee recommended approval of this change.

J. Straight presented the following changes;75-250 CP-401..0. Calibration and/or Maintenance of T av Channel'"401",

PCN 75-574, requested t'e following changes; lligh Tavg Bistable Charge as shown on attached data sheets circled in red.

Od Setpoint 571 F = 26.52 MA New Setpoint 578 F 30.26 MA Change pcr Revision Pl dated March 17, 1975. Rev. 3, Change 10 (Westinghouse Functional Analysis II) also, CP-403.6 T Av Bistable TC-403A PCN 75-575

~

Change procedure per attached sheet liigh ravg 578'F = 30.26 liA The Committee recommended approval of this change.75-253 0-2.4 Plant Shutdown From Hot Shutdown to Cold Shutdown Durin Blackout PCN 75-377. J. Straight presented this procedure change. It requested a new precaution be added, step 4.14 to read as follows; Mhen the R11R sys tem is in operation and the RCS Lempera ture is grcatex'han 200oF a maximum of 2 charging pumps are to be op-erated to present over pressurizing the RllB system. Below 200oF the operation of 3 charging pumps is all operable, but should be limited if possible.

Also, add new refcrencc, step 2,3 as follows letter daLed 2-25-75, px'occdure change to limit charging pump usc at cold shutdown.

I The Committee rcconnnendcd approval of this change.75-254 PT-23.?O'eactor Su iort Coolers Inlet and Outlet PCN 75-480. J. Straight presented this procedure change.

It was requested step 6.5 through 6.17 bc modified for draining water from containment side of MOU 813 and 814 and to utilize high point vents at valve 2733 and 2734 to check'PXV separately. C The Committee recon!mended appxoval of. this change.

73

Annual Report 0'll of all procedure changes: (Continued) l/l/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-255 ~PT-7 ll dro Test of Reactor Cool.aat 5 stem, PCR 75-383.

J. Straight presented this procedure change.

under references It requested a new step 3.3 bc added to read; 3.3 Letter dated 2-25-75, procedure change to limit charging pump use at Cold Shutdown.

Also to add a new step 5.7 under precautions to xead; 5.7 When the RIIR system is in operation, and the RCS temperature is greater than 200oF, a maximum of two charging pumps are to be operated to pxevent over pres-surizing the 1UIR system. Below 200oF, the operation of 3 charging pumps is allowable but should be avoided possible.

if PCN 75-415 requested the following additions; Add to Primary Hydro Checklist:

I

1) Pressuxizer: (psig) 2335 (only) e) Heater Connections

2) Reactor (delete Head) f) 'Incore Penetrations (lower vessel)

Add new step 7; M-40.3 completed for Spring Hangers and Supports in containment.

The Committee x'ecommended approval of these changes.75-256 S-23.2.1 Containment Pur e S stem Pre-Startu 7 Procedure PCN 75-335. J. Straight presented this new procedure. This pro-cedure describes the steps necessaxy to ensuxe the containment purge system is ready for operation.

The Coumvittt c recommended approval of this procedure.75-257 FZ-13 Pire Pum 0 cx'ation and S stem Ali nmcnt PCN

. 75 3 40 PCN 75-341. J. Straight px'cscnted this procedure chango.

PCN 75-341 was to facilitate steps N.A,'d.

PCN 75-340 requested a s tcp 4.3.5 be added to x'cad; Verify proper water level in Die 1'irc pump llcat Evchangcr (Radiator)

Thc Committee recommended approval of. this change.

74

Annual Report 811 of all procedure changes: (Continued) '/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-258 EH-117 Rcmovin Fault 4KV Underfre uencv Rcla For Ins ection And/Or Rc iair PCN 75-314 and EH-72 Reactor Tx'i Undcrvoltapc ProL'ection PCM 75-313. J. Straight presented these procedures for deletion as they vere replaced by H-60.1, H-60.2, H-60.3 and M-60.4.

The Committee recommended approval of these delctions.75-259 M-43.20B "B" Steam Generator Secondarv Side Pressure Test PCN;75-426. J . Straight 'presented this procedure change'.

It requested; Step 5.1.10 should read for AOV-4297 to be operable and closed.

Step 5.1.11 should read for AOV-4298 to be operable and closed.

Step 5.1.57 valve 4348A to read open.

The Committee recommended appx'oval of this change.75-260 M-48.6 Installation of Bus 18 PCN 75-463. J. S raight presented this nev procedure. This procedure is to describe the steps necessary to isolate Bus 18 for cleaning and breaker maintenance a 'list of vork performed. 'ncluding The Committee recommended approval of this pxocedurc.75-261 Steam Generator Blovdovn Jum er. B. Vanderveel presented this SH-74-30 design criteria and safety analysis for this SH. The Committee performed the safety evaluation and found that the modification does not involve any unrcviewed safety question and that Technical Specifications are not e'ffected.75-262 SH-74-41, HoniLor Circuits Eor UV and Tri Scheme Test. if@.

Schcctz prcsenLcd the, design criteria and safety analysis l.oe [hi:.."8, Th<<Committee performed thc safety evaluation and found thaL the modification does not involve any unrcvicvcd safety question and that Tcchnical Specifications are not cE-fcctcd.75-265 -

Tech. S cc. Ch ., C cle 5 . Dr. Hccredy presenLed .the proposed Tech. Spec. chg., attachment A and B, Cycle 5 to the Committee

~

for commenLs.

The Committee rccopmcndcd approval of this change.

Annual Report Itll of all procedure cltanges: (Continued) 1/1/75 Inclusive t:o . 12/31/75 PORC ITEM NUMBER: DESCRIPTION 75-267 M-43,16 Stcam Generator Ex losive Tube Plu in PCN 75-409.

J. Straight presented this procedure change. It: requested; Change step 3.9 to read as follows: 3.9 at. least one door in each pex'sonncl access hatch shall bc closed and all automatic containment isolation'alve operable on loclccd closed.75-268 PT 14 Circulatin Pum s - lli h Mater Tri Lo ic PCN 75-457.

J. Stxaight presented this proceduxe change. It request:cd several changes to include computer print out of relay operat:ion.

The Committee recommended approval of this change.

75-2)0 CP-111.0 Calibxation and/or Maintenance of React:or Hike-U Mater Flow Channel "III" PCN 75-576. J. Straight presented this procedure change. This requested a change to the data sheet also to add step 5.1.12 to xead; 5.1.12 (CP ill.ll) power calibration and/ox maintenance supply FQ111 on to outline a procedure for reactor make-up water flow power

, supply.75-271 PT-23.16A, Con ainment Isolation Valve Leak Rate. Testin . "A" Steam Generator Blowdown PCN 75-433. J. Straight presented this procedure change. It was requested; Steps 6.1 and 6.12.2 Delete "Manual Valve RV-3" and replace with "A" Steam Generatox'lowdown Regulating Valve."

Step 6.3 Delete "Manual Valve RV-1.

Delete step 6.7 and replace wi.th "6,7 Place test tag on "A" Steam Generator Blowdown (5709) Regulating Valve and open to provide an atmospheric Vent for PIV AOV 5737".

The Committee xecommended approval of this change.75-272 S-4.1A Li uid Hasta Proce s Startu PCN 75-584. J. Straight present:ed this procedure change. It: requested step 5.3.10 to read; Leave inlet valve from RO unit open due to hot laundry watex'.

The Committee recommended approval of this change.75-273 PT-23;7 Containment isolation Valve Leak Rate Tcstin Letdown From React:or Coolant S stem PCN 75- . J. Straight presented this procedure change. It requested seep 6.5 be changed to read; Request operations to open or ensure open AOV 371. '

The Committee rccommcndcd approval of t:his change.

T6

Annual RCport /Ill of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NETHER: DESCRIPTION

'PT-23.20 Containment: Isolation Valve Lealc Rate Tcs't:in R C D.'f 75-274 ~ ~

Gas )leader PCN 75-391. J . Straight presented this procedure change. It was requested step 6.3 road; Ensure that AOU 1786 is in thc closed position and ensux'e that AOV 1787 is in the open position.

Thc Committee recommended approval of this change'.75-275 PT-23.21 Containment Isolation Valve Leak Rate Tcstin R.C.O.T-.

Gas Anal rer PCN 75-390. J. Straight presented this procedure change. Xt rcqucstcd step 6.3 to read; Close or ensure closed AOV 1789 and place test tag at selector switch on panel.

The Committee recommended approval of this change.75-276 PT-23.1 Containment Isolation Valve Leak Ra,te Tcstin Pressurizer Relief Tank Gas Anal zer Line PCN 75-.389. J. Straight presented this procedure change. Xt was requested step 6.4 read; Close or ensure closed AOV 539 by use of the gas analyzer switch and place'est tag at selector switch.

panel'elector The Commigtee xecommended approval of this change.75-277 PT-23.28 Containment Xsolatioh Valve Lealc Rate Testin Auxiliar Coolant .S stem From "A" Reactox Coolant Pum , PCN 75-586.

J. Straight presented this procedure change. It requested several valve number designations changed.

The Committee recommended approval of this change.75-278 PT-23.23 Containmcnt Isolation Valve Leak Rate Testin Sum "A" Dischar e PCN 75-587. J. Straight presented this procedure change.

X t was requested under stop 6. 1 to change MCB to MDP, to correct the switch location.

The Committee recommended approval of this change.75-279 J. Straight presented the following CP's, it was requested step 5.5 to change + 1% of Span to read + 2% Span. undcx'nstxuctions CP-950.3 Containment Pressure Transmitter "PT-950 " PCN 75-488.

CP-949.3 Containment Pressux'e Transmittcx "PT-949 " PCN 75-489.

CP-948.3. Containment.Pressure 'fransmittcr "PT-948," PCN-?5-490.

- 77

I Annual Report f/ll of all procedure changes: (Continued) 1, 1,'75 t;o 12/31/75 Inclusive PORC XTHM NUMBER: DESCRIPTION 75-279 CP-947.3 Containment Pressure Transmitter "PT-947 " PCN 75-491.

(Continued)

CP-946.3. Cont:ainmcnt Prcssure Transmitter "PT-946 " PCN 75-492.

CP-945.3 Containmcnt: Pr<<ssurc Transmitter "PT-945 " 1'CN 75-493.

CP-941.1 Accumu1ator Prcssure Transmitter "PT-941," PCN 75-494.

CP-940.1, Accumulator Pressure Transmitter "PT-940 " PCN 75-495.

CP-937.1 Accumulator Pressure Transmitter "1'T-937 " PCN 75-496.

CP-936.1 Accumulator Pressure Transmitter "PT-936 " PCN 75-497.

CP-920.3 Refuclin Hater Stora e Tank Level Transmitter LT-920, PCN 75-498.

CP-626.3 Residual Heat Removal Flee Transmitter FT-626 PCN 75-499.

CP-486.3 Turbine 1st Sta e Pressure Transmitter PT-486 PCN 75-500.

CP-48S.3 Turbine 1st Sta e Pressure Txansmitter PT-485 PCN 75-501.

CP-483.3 Steam Generator Pressure Transmitter PT-483 PCN 75-502.

CP-482.3 Steam Generator Pressure Tra'nsmitter PT-482 PCN 75-503.

CP-479.3 Steam Generator. Pressure Transmitter PT-479 PCN 75-504..

CP-478.3 Stcam Generator Pressure Transmitter PT-478 PCN 75-505.

CP-106.3 Boric Acid Tank Level Transmitter LT-106 PCN 7S-538.

CP-128.3, Char in Line Flow Transmitter FT-128 and Local Indicator FI 128A PCN 75-537.

CP-171.3 Boric Acid Tank Level Transmitter LT-171 PCN 75-536.

CP-172.3 Boric Acid Tank Level Transmitter LT-172, PCN 75-535.

CP-411.3, Reactor Coolant Flow Transmitter FT-411 PCN 75-534.

CP-412.3 Reactor Coolant Flow Transmitter FT-142 'PCN 75-533.

CP-413.3, Reactor. Coolant Flow Transmitter FT-413, PCN 75-532.

CP-414.3 Rcactox Coolant: Floe Transmitter FT-414 PCN 75-531.

CP-415.3 Reactor Coolant Flow Transmitter FT-415 PCN 75-530.

CP-416.3 Reactor Coolant Flow Transmitt:cr FT-416 PCN 75-529.

CP-426.3 Pressurizer Level Transmitter LT-426 PCN 7S-528.

CP-427.3 Pressuri'r Level Transmitter. LT-427 PCN 75-527.

Annual Report !/11 of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive NUMBER'ESCRIPTION PORC ITEM 75-279 CP-428.3 Prc.'>surl .cr l.cv('1 Tra>>s!!i L t(!r LT-428 PCN 75-526.

(Continued)

CP-429.3 Pressurizer Pres.,ure TransmiLLcr PT-429 PCN 75-S25.

CP-430.3,'ressurizer Prcssure Transmitter PT-430 PCN 75-S24.

CP-431 s3 klressuri.zer Pressure Tran."ani.ttcr PT-431 PCN 75-523.

CP-449.3 Pressurir;er Pressure Transmitter PT-449 1'CN 75-522.

CP-46}.3 Steam Generator 7,evel Transmitt:cr LT-461 PCN 75-.521.

CP-462.2, Steam Generat:or Level Transmittex LT-462 PCN 75-520.

CP-463.3 Steam Generator Level Transmitter PCN 75-519.

CP-464.3, Steam 1 low Transmitter FT-464, PCN 75-S18.

CP-465.3 Steam Flow Transmitter FT-465 PCN 75-517.

CP-466.3 Feedwater Flow Transmittex FT-466 PCN 75-516.

CP-467.3, Feedwater Flow Transmitter FT-467 PCN 75-515.

CP-468~3 Steam Generator Pressure Tx'ansmitter PT-468 PCN 514.

CP-469.3 Steam Generator Pressure Transmitter PT 469~PCN 7S-513.

CP-471.3~ Steam Generator'evel Transmitter -LT-471 PCN 75-512.

CP-472.3 Steam Conqueror Level Transmitter LT-472~PCN 75-511.

CP-473.3 Steam Generator I.evel Transmitter LT-473. PCN 75-510.

CP-474.3 Steam Flow Transmi.ttcr FT-474 PCN 75-509.

CP-475.3 Steam Plow lrsnsmittor PT.-475>> PCN 75-500.

CP-476.3 "E" Feedwatcr Flow Transmi.tt:cr FT-476 (PCN 75-507.

CP-477.3 Fee>1>>uter Plow Transmitter I'-477 PCN 75-506.

CP-102.3 Bori.e Aei>l Tonic l.evel Tra>>.'r>>>i ttar LT-102 PCN 75-539.

The Committee recommended approval of these changes.75-282 H-40.2> Isolation of Bu.". 14. 1'CN 75-.'>90~I1-40.5 lsoleti on of Sus 17~ 1'CN 75-598. J. Straight prese>>tud these procedure Cltangcs.

They xcquestcd to add steps fox notificat:ion of Relay DcpL. for the purpose of performing calibration tnd trip. s

- 79

Annual Report f/ll of all procedure changes: (Continued) 1/1/75 to 12/31/75 Xnclusive PORC ITEM NUMBER: DESCRXPTON 75-283 CP-624.1, Residual Heat Removal Heat Exchan er Outlet Valve HCV-G24, Isolation, PCN 75-3G9> PCN 75-361. J. Straight presented this procedure change.

PCN 75-361 - was a temporary change requesting step 3.1 be'.A.'d.

PCN 75-369 - requested on data sheet valve calculation %

be changed as they were reversed. This is to be made per-manent.

The Committee reviewed the temporary change and recommended approval of PCN 75-369 75-284 CP-'625.1> Residual Heat Removal Heat Exchanger Outlet Valve>

HVC-625> Isolation> PCN 75-362 and PCN 75-370. J. Straight presented this procedure change, PCN 75-362 - was temporary requesting step 3,1 be N.A.'d.

PCN 75-370 - requested to change valve position calculation of % be changed on the data sheet as they were reversed.

This is to be made permanent.

The Committee recommended approval of PCN 75-370 and reviewed PCN 75-362.

75-289 M-37.35> Maintenance of Valves '3504 and 3505> Hain Steam to Turbine Driven A'uxiliar Feedwater Pum , PCN 75-443. J. Straight presented this new procedure. The purpose of this procedure is to describe the steps necessary to inspect and repair valves 3504 and 3505.

The Committee recommended approval of this procedure.75-291 0-2.1> Normal Shutdown to Hot Shutdown> PCN 75-339 and PCN 75-349.

J. Straight presented these procedure changes.

PCN 75-339 - requested mark step 5,35 and make this possible in future procedures when the plant is to remain in hot shut-down or started back up and stopping 1 RCP is not necessary.

PCN 75-342 requested not operating.

- add to step 4.6.2.4 - if computer is The Committee recommended approval of this change.75-292 RF-8.4, Fuel and Care Com onent Movement In the S ent F ue 1 P4N 757 3368.

J. Straight presented this procedure change.

Xt requested to delete steps 12 and 14 in Appendix "A" The Committee recommended approval of this change.

C I

Annual Report /Ill of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEN NUMBER DESCRIPTION PT-23.168, Containment Isolation Valve Leak Rate Tcstin 75-293 "B" Stcam Generator l31owdown> PCN 75-434, J, Strdight presented this procedure change. It requested; Step 6.1 delete "ManuaL Valve RV-3" and replace with B Steam Generator Blowdown Regulator Valve 5710 and step 6.12,2.

Step 6.3 delete "Manual Valve RV-3".

Step 6.7 should read: .Place test tag on B Stcam Generator Blowdown Regulator Valve 5710 and open to provide an atmos-pheric vent for primary isolation valve AOV 5738.

The Committee recommended approval of this change.75-294 M-43.20A, "A" Steam Generator Secondar Side Pressure Test~

PCN 75-439. J, Straight presented this procedure change.

It requested; Step 5.1.63 - B Chem pump discharge change V-5038 from open to closed.

Step 5.1.63.4 - common suction valve for chem pump from open to closed. V-5036.

Step 5.l,63.? - Chem. discharge to A S/G change from open to closed. V-4281.

The Connnittee recommended approval of this change.75-295 M-48.5> Isolation of Bus L?> PCN 75-440 and PCN 75-436.

J. Straight presented this procedure change.

PCN 75-440 requested; add to step 5.6 "open and hold main incoming breaker Bus 17 on MCC 1G,'CN 75-436 requested; change procedure so that step 5.12 and '5.13 come af tcr 5.14.

The Committee recowncndcd approval of these changes.75-297 M-43.1, Stcam Generator'Hanwa Cover and Insert Removal>

PCN 75-482, and M-43.15, Reinstallation of Stcam Generator Manwa Insert and Cover CLosurc> PCN 75-483. J. Straight presented these two procedures for the same procedure change, which was; Add step 3.4.1 - verify that supplied air is being passed thru the dcl-monox purifier and the, filter cartridge is acceptable for use.

The ommittce 'rcconnnended approval of this chango.

Annual Report Ill of all procedure chnnges: (Continued) 1/1/75 to 12/31/75 Inclusive PORC 1TH)k NUMBER i)HSCRIPTION 75-298 J. Straight presented the following procedures for temporary procedure changes> for review.

PT-5.10> Process Instrumentation Reactor Protection Channel Tri Test> PCN 75-442., Requested steps 6.15, 6.62, 6.1, 6.100 and 6.101 be marked N. A.

PT-5.20, Process Instrumentation Reactor Protection Channel Tri Test, PCN 75-444>'equested steps 6.15, 6.67 and 6,68 be marked'.A.

PT-5.30, Process Instrumentation Reactor Protection ChanneL Tri Test, PCN 75-446t PCN 75-447. Requested steps 6.106>

6. 107, 6. 16 and 6. 50 be N.A.

PT-5.40, Process Instrumentation Reactor Protection Channel Tri Test, FCN 75-449. Requested steps 6.14, 6,42 and 6.65 be marked N.A.

The Committee reviewed the above changes. This item 75-299 PT-23.12A Containment Isolation Valve Leak Rate Testin Pressurizer Steam S ace Sam le, PCN 75-396, PCN 75-453.

J. Straight presented this procedure change.

PCN 75-396 requested to change step 6.4 to read: Close or ensure closed AOV 966 and place test control tag at control switch location.

PCN 75-453 - requested the same change as75-396.

The Committee recommended approval of this change.75-300 PT-23.128, Contain~ent Isolation Valve Leak Rate Testin Pressurizer Li uid S ace Sam le> I'CN 75-395, PCN 75-452.

J. Straight presented this procedure change.

PCN 75-395 - requested step 6.4 to read> Close or ensure closed AOV 9668 and place test control tag at control switch location, PCN 75-395 - requested the same change as75-395.

The Committee recommended approval of this change.75-301 PT-23.12Ct Containment Isolation Valve Leak Rate Testint, PCN 75-394, PCN 75-454. J. Straight presented this procedure change. PCN 75-394 and PCN 75-454 requested step 6.4 be changed to read:

Close or ensure closed AOV 966C and pl'qce test control tag at control switch location.

'Tltn t't rnnnmmnrnrtnil onnwnrrn't nt' r

Annual Rapport /Ill of all procedure changes: (Continued) 1/] /75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 0

75-302 PT-23.13A, Containment Isolation Valve Leak Rate Testinp, "A" Steam Generator Sam le> PCN 75-393 and 75-455. J, Straight presented this procedure change. Both PCN's requested to change 6.4 to read; Ensure that control switch (located at sample panel) for AOV 5735 is in the "AUTO" position. Request operation to close or ensure closed AOV-5735 by use of CB master switch.

The Committee recommended approval of this change.75-303 PT-23.13B> Containment Isolation Valve Leak Rate Testine, "B" Steam Generator Sam le> PCN 75-392 and PCN 75-456.

J. Straight presented this procedure change. Both PCN's requested step 6.4 to read; Ensure that control switch (located at sample panel) far AOV-5736 is in the "AUTO" position. Request operation to close or ensure closed. AOV-5736 by use of CB master switch.

The Committee recommended approval of this change.75-304 J. Straight presented the following procedures with temporary changes for review only.

PT-12.1>- Emer enc Diesel Generator lA, PCN 75-438.

Requested steps 6,F 1 through 6.2.7 be N.A.'d.

PT-6.3.3> Power Range Nuclear Instrumentation S stem, PCN 75-472, Channel 43, reques ted s tep 6. 54 be marked N A PT-6.3.4> Power Ran e Nuclear Instrumentation S stem, Channel 44 PCN 75-473 > requested step 6. 54 be marked N,A.

PT-6,3.1, Power Ran e Nuclear Instrumentation S stem>

Channel 41, PCN 75-47~>> requested step 6.54 be marked N.A.

PT-6.3.2, Power Ranpi~ Nuclear Instrumentation, Channel 42, PCN 75-475> re uested ste 6.5.4 be marked N.A.75-305 RF-2A, Re uirements For Reactor Head Removal, PCN 75-470.

J. Straight presented this procedure change for review only. It was requested; Step 5.10.5 - Water level at steam generator repair level.

Step 5.11 >> Mark N,A. since not making head lift.

The Committee reviewed this change.

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Annual Report //ll of all procedure changes: (Continued} 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-307 M-43.2QA, "A" Steam Generator Secondar Side Pressure Test PCN 75-448 and PCN 75-427. J, Straight presented this tem-porary procedure change. It requested some steps to be marked N,A.

The Committee reviewed this change. PCN 75-427 requested to add "valve 436 open."

The Committee recommended approval of this change.75-308 M-48.5~ Isolation of Bus 17> PCN 75-445. J. Straight presented this procedure change. It requested to; Add new step between step 5.2.6 and 5.27 to read; Remove hold and close main incoming breaker Bus 17 at MCC-1G position 4M clear.

The Committee recommended approval of this change.75-309 CP-43.01, Calibration and/or Maintenance 430 Pressurizer Pressure Channel, PCN 75-4581A and CP-485, Calibration and/or Maintenance of Turbine 1st Sta e Pressure Channel "485"> PCN 75-464 and PCN 75-466.

PCN 75-458A requested under instructions step 5.12 change Channel 1 Rack 1 to read Channe'1 2, Rack 1.

PCN 75-464 - requested the same change on steps 5.6 and 5.7. ~ ~

PCN 75-466 - requested the same change on steps 5.1 and 5.2.

The Committee recommended approval of these changes.75-310 RF-2B> Re uired Valve Lineu for Reactor Head Removal, PCN 75-469. J. Straight presented this procedure change.

It was requested; Change step 5.9 ' to r'ead: Isolation valves locked closed.

The Committee recommended approval of this change.

J, Straight presented the following temporary changes for review only;75-311 CP-626.1, Defeat of Residual Heat Removal Flow Channel "626" PCN 75-365> N. A. step 5.3.2..

CP-626.2, Reinstate of Residual lleat Removal Flow Channel "626" PCN Ts-335> N.A. steps 5.3,2, 5.3.3 and 5.3.4.

CP-464.0, Calibration and/or Maintenance of Steam Flow Channel "464", PCN 75-476, steps 5,7 and 5.9 to be marked N.A.

Annual Rapport f/11 of all procedure cIianges: (Continued) 1/I/75 to 12/31/75 PORC ITEM Inclusi ze NUMBER:

DESCRIPTION 75-311 S-4 ~ lII, "B" I.aundr (Continued) and Ifot Shower Tank Release To Dischar e Canal> PCN 75-477> N.A, step 5.6.

M-43.5, I'nstallation of Steam Generator Tem )orar Loo Nozzle Covers> PCN 75-481., N.A. step 5.9 temporary to be made permanent.

The Committee reviewed these procedure 1 changes.

J. Straight presented the following two procedures for deletion;75-312 RF<<l4, S ecial Instructions and Tech. Manual PCN 75-297.

Procedures~

0-4> Load Follow, PCN 75-366.

The Committee recommended approval of these de1.etzons.75-313 SM 74-231i Install Boric Acid Su 1 to the Safet In ection S stem~ PCN 75-471. J. Straight presented thxs new proc edur e.

This rocedure is to describe the steps necessary to change the logic and timer circuits for the refueling water storage tank to safety injec'tion system valves 825A and 825B.

The Committee recommended approval of this procedure.

75"316 SM 75-l.2, Instrument Cable Reroutin , PCN 75-458B.

J. Larizza presented this procedure change. It requested;

l. Change reference B.11.5 to read 4155 D-215-081.

2~ Change reference B.ll.10 to read 4666 B-281-041.

The Committee recommended approval of this change.75-317 SM 75-2.1, "TV S stem Insert In Containment, PCN 75-478.

J~ Larizza presented the following procedure change; Change step E.3 to read as follows: Nitrogen supply valve has been closed and flange on penetration sleeve AE-l2 has been removed in accordance ith B.lli 9.12> B.13.

Also add signoffs.

Add step E.4 to read as follows: The outboard cap on pene-tration sleeve AE-I.7 has been removed in accordance with B. 11 B.12'13.

A>><<dd signoffs, Change numbering sequence from present E-9 to E-10.

The Committee recommended approval of this change.

Annual Report II)ll of all procedure c)ranges: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM

" DESCRIPTION NUMBER EM-138 New Fuel Element Index Hole Reamin. PCN 75-625.75-321 Co Peck presented this ncw proccduxo. Tho purpose of this procedure is to provide instruction for roaming out the indexing hole of a new Westinghouse fuel assem-bly in the new fuel elevator The Committee recommended appxoval of this procedure..75-322 PT-25 Containment Air L iltoration Post Accident Charcoal Filter B -Pass Flow & Prcssure Dro Test PCN 75-626.

C. Hartlieb presented this new procedure. .The purpose of this procedure is to permit by-pass flow determination of the containment post accident charcoal filters (A & 8 Units).

The committee recommended approval of this new procedure.75-323 M-61.1 Mechanized Ultrasonic Examination of Reactor Vessel Nozzle Helds PCN75-595. J. Straight presented this new

~

procedure, The purpose of this procedure is to provide instructions for the Mechanized Ultrasonic Examination of Reactor Vessel Nozzle Welds. The Committee recommended approval of this procedure.

E 75-325 0<<2.3.1 Drainin The Reactor Coolant S stem PC "

orary procedure chan e. ~ ~

g th o h 5 16 d st 5 18 b k 75-327 RF-8.2 Fuel Handlin Instruction Pre-Loadin & periodic Valve Test PCN75-5 94 9 . J. Straxght presented thxs procedure change.

was requested undex instructions, step 5.10 be changed to read II H2 recumbxner - Isolation Valves locked closed The Committee recommended approval of this change.75-328 . PS'-9.9 Control Rod Drive Shaft Unlatchin Tool oo 0 era txn Ins true t ion PCN75 -654 and PCN75-652.

PCN75-652 was to correct a typing error in step 5.2.5.

PCN75-654 requested two data sheets be added.

The Committee recommended approval of these changes.

J . Straight presented those temporary procedure changes;75-329 M-37.ll Ro air & Ins ection of Pressurizer Power 0 ioratod Relief Val.vcs 430 and 4310 PCN75-655 requested step 3.2 N.A.

and steps 5.3 through 5.15 N.A.

RF-9.2, Rofuolin ~

Procedure RF-9.? Fuel Transfer System 0 oration PCN75-589 xoquostod under Instruction, step 5.6.12 bo N.A.'d.

0-2.3.1 Drainin Tho Reactor Coolant System, PCN75-599 requested step 3.4 bo marked N.A.

Tho Committee reviewed they'd procedures.

I l

Annual Report 811 of all procedure changes: (Continued) 1/1/75 to 12/31/75 I'klc Us ive

~

PROC ITEM NUMBER: DESCRIPTION 75-331 M-7.4 Boric Acid Stora e Tank Filter PCN75-653. J. Straight presented this procedure change. It was requested step 4.1 bc deleted. The Committee recommended approval of this change. This item IS COMPLETE.

P-9 S seem it Precautions PCN75-590. '.

Limitations & Set oints P-9 Radiation Honitorin Straight presented this procedure change; requested in step 2.3.2.11, the setpoint shall be set at about 15, 000 cpm to keep the alarm above normal levels.

The Committee recommended approval of this procedure,75-332 RF-8.1 Ste Fuel Loadin Se uence and Ma s, PCN75-613 Bv Stem PCN75-614 PCN75-615 PCN75-616 PCN75-617 PCN75-622 PCN75-623 PCN75-628 PCN75-629 PCN75>>630 PCN75-631 PCN75-632 PCN75-633 PCN75-635 PCN75-639 PCN75-643 PCN75-644 PCN75-645, 'CN75-634 PCN75-646 PCN75-647 PCN75-648. J . Straight presented all these procedure changes. The Committee recommended approval of these changes. which were made in regards to fuel shuffle.75-333 0-2.3.1 Drainin The Reactor Coolant S stem PCN75-599. J. Straight presented this temporary procedure change. .It requested step 3.4 be N.A.'d. The Committee reviewed this change.75-334 RF-8.1 Ste B Ste Fuel Loadin Se uence 6 Ha s PCN75-669.

J . Straight presented this procedure change. It was requested after step 117a to read; "conduct test assembly inspection in accordance with RF-8.4, Rev. '5" The Committee recommended approval of this change.75-335 RF-8.4, Fuel and Core Com onent Movement In The S ent Fuel Pit PCN75-662. J . Straight presented this procedure change. It requested to remove Revision 3, Fuel llandling Data Sheets and replace them with new updated ones. The Committee recommended approval of this change.75-336 SM 75-20.1 Control Rod Drive Shaft Chamferin 0 cratin PCN 75-667. J. Straight presented thi" new procedur'c.

This procedure defines the s teps to accomplish thc mach-ining of a.chamfer on a radioactivity contaminated control rod assembly.

~

The Committee recommended approval of this procedure.

Annual Report //11 of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-337 SM 75-11.1 Switch Control Boax'd Rccordcrs 6 Controllers Instrument Bus 1C PCN 75-668. J. Straight presented this ncw procedure. This procedure describes the steps necessary to provide unintcrruptable power supply to control board recorders and controllers dura.ng blackout.

The Committee recommended approval of the procedure.75-338 PT-10 Station Batter Load Test PCN 75-642 PCN 75-663; J". Straight presented this procedure change.

PCN 75-642 requested - Period IX - decrease battery load to 484 amps for 12 min, add 10 min. reading for "A" battery on page PT-10:9.

Period IX - decrease battery load to 229 amps for 12 min. add 10 min. reading for "B" battery on page PT-10:13.

PCN 75-663 requested to - add to PT-10 station battery load test where indicated on marked-up copy.

Page 3,4,5,6 add lines to page 8 and 12 also heading on battery charger data.

Page 9 and 13 (add data to be taken) and changes where indicated.

Page 10 '(add data to be taken) Page lines) Page 14 (add data to be taken).

ll (add lines) Page 15 (add The Committee recommended approval of this change.

?5-340 PT-23 Containment Isolation Valve Leak Rate Testin PCN 75-274.

J. Straight presented this procedure change. It was requested:

1. PT<<23.37 Change "Reactor Compartment Cooling Xn" to read "Reactor Compartment Cooling Unit A".

2. PT-23.38 Change "Reactor Compartment Cooling Out" to read "Reactor Compartment Cooling Unit B".

The Committee recommended approval of this change.

1 75-342 S-23.3A Penetration Coolin S stem Control Rod Dx'ive Coolin S stem Reactor Com artment Coolin S stem and Auxiliar Charcoal Filter S stem Prc-stax t-u PCN 75-468. J.* Straight presented this new pxocedure. This px'ocedure describes the pre-startup of the penetration cooling system, control rod drive cooling system, reactor compartment cooling system, and the auxiliary charcoal filter system.

The Committee recommended approval of this procedure.

- 88 "

Annual Report /Ill of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM

'UMBER:

DESCRIPTION 75-344 RF-8 Fuel Assembl and Core Com onent Movement Prere uisites, PCN 75-601 PCN 75-604. J. Straight presented this procedure change. PCN 75-601 requested step 4.3 to read; A daily sample shall be taken from the reactor cavity and the spent fuel pit and analysed for boron concentration during refueling.75-345 PCN 75-604 requested to delete precaution 4.13, this was dis-approved as PCN '75-601 took place of this.

J. Straight presented the following PCN's to facilitate steps N/A'd.

RF-9.2 Fuhl Transfer S stem 0 eration PCN 75-657, step 5.6.12.

RF-2E Drainin of Refuelin Canal PCN 75-602 steps 5.8.1 thru 5.13 also step 3.6 N/A'd.

S-16.4 Ventin N From the "B" Accumulator PCN 75-611, step 3.3 N/A'd, S-16.3 Ventin N From the "A" Accumulator PCN 75-612 step 3.3 N/A'd.

M-37.30 Rc air and Ins ection of "A" Accumulator Fill Valve 835A PCN 75-658 mark steps 5.4 thru 5.14 N/A'd.

reques ted s teps 5.8. 1 and 5. 13 be N/A '.

RF-8.3 Core Loadin Periodic E ui ent Status Check, PCN 75-664, S-3.48 Gas Stri er Startu PCN 75-609, mark steps 5,3.20, 5.3.21 and 5.3.22 N/A. Also requested to add; NOTE: If recirculating H.U,T, to reduce activity steps 5.3.20 5.3.21 and 5.3.22 may be marked N/A.

The Committee reviewed the above items.75-346 M-ll.ll Ins ection and Maintenance of Crane Chem um s, Series G PCN 75-585. Requested; Step 5.6.3 add - measure oriface bore I,D, Step 5.6.7 add - measure oriface bore I.D.

Step 5.6.11 add - line to sign on, The Committee recommended approval of this change.

- 89

,,;,i'i 4 re'J' Annual Report 1/ll of all procedure changes: (Continued) 1/1/75 to 12/31/75-Inclusive PORC ITEM NUMBER- DESCRIPTION 75-347 PT-23.23 Containmcnt Isolation Valve Leak Rate tTestin Sum "A" Dischar,c PCN 75-587. J . Straight presented this procedure change. It was requested undex instructions step 6.1 thc MCB be changed to; M)P control MDP control Also Step 6.5 change MCB to N)P.

I The Committee xecommended approval of this change.75-348 RF-9.5 RCC Chan e Fixture PCN 75-606. J. Straight presented this procedure change fox review only. It was xequested; add to step 5.1.11 and turn on air step 5.1.14 and turn off air.

step 5,1.24 and turn on air step 5.1.26 and turn off aix'

~

The Committee reviewed this change.75-349 PT-23.20 Containmcnt Isolation Valve Leak Rate Testin R.C.D.T Gas 1leador PCN 75-608 and PT-23.21 Cont:aimnent Isolation Valve Leak Rat:o Tostin R.C.I).T. Gas Anal rcr PCN 75-607.

Both those procedures requested a minor temporary change for review only. The Committee reviewed these changes.75-350 SM 75-4.1 Reroute of Steam Generator Blowdown Line PCN 7 -610, PCN 75-618. J. Straight presented this procedure change.

PCN 75-610 requested to add step H 6.1 - Insure blowdown tank is drained, "Rcmove manway cover, II.P. to survey tank to see if protective clothing is requixod, and inspect tank from the inside for wall thinning". Also sign off.

PCN 75-618 request:od to change step H.6 - Change valve jf 3630 to 3530.

Add these two valves fP5763, 84694.

The Committee rcconancnded approval of this chango.

Annual Report //11 of all procedure changes: (Continued) 1/1//5 t:o 12/31/75 Inclusive PORC ITEM NUMBER'5-352 DESCRIPTION M-37.11 Re air and Ins ection of Pressurizer Powex' erat:ed Relief Valves 430 and 431C PCN 75-641. J. Straight presented this procedure change. It was requested; Step 5.4 eliminate (slings axe used)

Add step 5.2.1 - Locate air set at job area Step 5.7 - Hliminat:e the words "by the eye bolts" as they are not used ~

Step 5.13 - Eliminate words "Torque to 340 ft. lbs." as this is not presently possible.

Step 5.14 - Eliminate words "Torque to 271 ft. lbs," as this is not presently possible.

The Committee recommended approval of this change. This item IS COMPLETE.75-353 PT-23.7 Containment Isolation Valve Leak Rate Testin Letdown From Reactor Coolant S stem PCN 75-649 75-650. J. Straight presented this procedure change.

PCN 75-540 requested steps 5.4.5 through 5.8 be N/A, also after step 5.4..4 after the words "torquing to" add the words, "at least This was temporary for review only.

PCN 75-541 requested to; add (if used) after each of the following steps: 5.2, 5.3, 5.4, 5.8, 5.9, 5.10, 5.11 to allow N/A when covers are used only for loop protection and reactor water level is not to be raised.

Add checkoff line for step 5.15 Add (as applicable) to. sign off for Foreman.

The Committee recommended approval of this change.75-356 H-48.6 Isolation of Bus 18 PCN 75-660. J. Straight presented this procedure change.

to read; It was request:ed to change the following steps 5.18 Remove hold on Switch /$ 6, Bus 18 emergency DC Supply, in screenhouse DC distribution panel lB and close. clear 5.19 Remove hold on Switch 82, Bus 18 normal DC Supply, in screenbousa DC discribucion panel la 'and close. clear The Committee xecommended approval of. this change.

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Annual Report fill of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-357 CP-428.3 Pressurizer Level Transmitter LT 428'CN 75-651.

J. Straight presented this procedure change. It was requested to provide sign-off lines per each Instruction for Transmitter Calibration. The Committee recommended approval of this change.75-358 M-43.11 Steam Generator Tube Removal PCN 75-627. J. Straight presented this procedure change. It requested; 5.4.10 "with the 13/20" - 20 tap" should be changed to:

"with the 13/16 - 20 tap".

. The Committee recommended approval of this change.75-359 CP-139 Calibration and/or Maintenance of Volume Control Tank Level Channel "139" PCN 75-582. J. Straight presented this procedure change. Xt was requested % on the Data Sheet Column LI-139A.

The Committee recommended approval of this change.75-360 S-23.2 in 18 H dxo en Recombiner Pur and 0 exation PCN 75-592.

J. Straight presented this new procedure. This procedure is to describe the steps necessary to purge air from the recombiner system hydrogen piping.

The Committee recommended approval of this procedure.75-361 S-21.2 1A 11 dro cn Recombiner Pur in and 0 eration PCN 75-593.

J. Straight presented this new procedure. This procedure is to describe the steps necessary to purge air from the recombiner system hydrogen piping.75-363 PT-2.2 Residual fleat Removal S stem PCN 75-780.

J. Straight presented this procedure to add new precaution, step 5.4 to change.

read; It was re uested M>en R11R system is in operation greater than 200 F, a maximum ofand 2 the RCS temperature is o prevent overpressurizing the RliR system below ow 200oF , the operation g'

'f

~

pumps xs allowable but should be limit imite d x,. possible.

Also a new refexence .

xence step 3.3 to xead; Letter R. Hecred y to Bruce Snow concex'ning dated e - -

2-25-75 from

. charging pump use at cold shutdown. px'ocedure change to limit .

The Committee recommended approval of this change c >ange.

92

[

Annual REport fill of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-364 PT-4 Residual ltcat Removal Loo Annual 11 dro Test of Low Pressure Pi in PCN 75-381. and PT-4.1 Residual 1leat Removal Loo )l dro Test of Ili h Pressuxc Pi in PCN 75-382.

J. Straight'resented these procedure changes. It requested both procedures be changed as follows; 3.7 Letter dated 2-25-75 from R. Mecredy to Bruce Snow concerning procedure change to limit charging pump use at cold shutdown.

5.4 When RHR system is in operation and the RCS temperature is greater than 200 F, a maximum of 2 charging pumps are to be operated to prevent overpressurizing the RHR system below 200 F, the operation of 3 charging pumps is allowable but should be limited if possible.

The Committee recormncnded approval of this change.75-365 S-13A RlIR S stem Line-u for Safet In ection PCN 75-379.

J. Straight presented this procedure changes. It requested the following steps xcad; 2.2 Lettex dated 2-25-75 from R. Mecrcdy to Bruce Snow concerning procedure change. to limit charging pump use at cold shutdown.

4.3 When RIK system is in operation and RCS temperature is greater than 200 F, a maximum of 2 charging pumps are to be operated to prevent overpressurizing the M1R system below 200oF, the operation of 3 charging pumps is allowable but should be limited if. possible.

The Committee recommended approval of these changes.75-366 J. Straight presented the following procedures for changes to step 2.2 and 4.14; Coolant System, PCN 75-376.

l O-l.l, Plant 1leat u from cold shutdown to hot shutdo n PCN 75-371.

0-1.1D Pre-}leatu Plant Re uircmcnt Check List PCN 75-372.

0-2.3 Plant at Cold Shutdown PCN 75-374.

0-2.3.1 Drainin thc Rcactox Coolant System PCN 75-375.

0-2.2 Plant Shutdown from IIot Shutdown to Col<1 Condition, PCN 75-373. These changes werc to read; 2.2 Letter dated 2-25-75 from R. Mecredy to Bruce Snow concerning procedure change to limit charging pump use at cold shutdown.

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Annual Report illl of all procedure changes: (Continued,) 1/1/75 to l.2/31/75 Inclusive PORC ITEM NUMBER: DESCRXPTXON:

75-366 4.14 Mhcn RIIR system is in operation and the RCS temperature is (Continued) greater than 200 F, a maximum of 2 charging pumps are to be op-erated to pxevcnt ovcrprcssurizing the RllR.system below 200ol',

the operation of 3 charging pumps is allowable but should be limited if possible.75-367 SH 74-2.1 RPX Pulse to Anglo Convertcx Chan c PCN 75-211.

J. Straight prese<<Led this new procedure. The puxpose of this pro-cedure is to provide instructions for the removal of the two existing pulse -to- analog converters, and the Installation of the ncw solid state pulse to analog converter. This item is NOT COHPI.ETE pending completion of the job.75-368 S-4.2.10 Bur in the Pressurizer Relief Tank and RCDT and Isolatin from thc Ucnt lleader, PCN 75-450. J. Straight presented this pro-cedure change. It was requested step 5.3.2 read V-554.

The Committee recommended appxoval of this change.75-369 PT-17.2 Process Radiation Monitors R R-20 Iodine Monitors R-10A and R-lOB PCN 75-485. J. Straight presented this procedure change. It was requested step 6.11.9 read; Raise setpoint to 10K The Committee recommended disapproval of this change.75-375 RSSP-2.6 Hmer encv Diesel Staxt and Breaker Closure Time PCN 75-670. J. Straight presented this pxocedure change.

Xt was requested; Initial Condition 4.2 should read - Service wat:cr cooling requirements arc such that one service water pump is adequate for heat load removal.

The Committee recommended approval of this change.75-376 H-50.1 Isolation of 812 Transformer, PCN 75-672.

J. Straight presented this procedure change. Xt requested to add st:cps for notification of Piclay Dept. for Lhc purpose of performing calibration and trip test on 812 .transformer.

The Conmiittcc recommended approval of. this change.75-377 H-ll.lO 11a'or Inn~ection of Service theater Pum) PCN 75-673.

J. Straight presented this procedure change. IL requested to; Add t:o instruct:iona - 5.8.1 inspect: rubber expansion joint and replace if necessary.

Thc Cuamiittcc rccommcndc<1 <<pproval of this change.,

94

Annual Report /Ill of all procedure changes: (Continued) I/I/75 to l2/3l/75 Inclusive PORC ITEM NUMBER: DESCRIPTION:

75-3?9 0-1 .2 Plant from llot Shutdown to SLead l.oad PCN 75-675.

0-5.2 Load Increases PCN /5-676.

J. Straight presented these procedure changes;

.Add reference 2.4 to read as follows - Letter from P.L. tfallcor (Westingho'usc Nucleax'uel Division) to A.A, Fuiexer rogarding

~

st.art-up requirements for Westinghouse Zi.rcaloy Clad Fuel, NFD News le t tor, December, 1974.

Also t:o add; PRECAUTION: During the initial return to power following a refueling shutdown or following a cold shutdown where fuel assemblies have been handled (e.g.,

inspection), the rate of reactor power 'ncrease shall be limited to 3% of full power in an. hour between 20% and 100% of full pow'er.. This ramp rate requirement applies during the initial start-up and may apply cluring subsequent power increases depending on thc.maxitnum power level achieved and length of op-eration at that powex level.. Specifically, this re-quirement can be removed for reactor power levels at or below a given level P (20% ~ P ': 100/) providod the plant has operated at or above level P for at least 72 cumulative houxs out of any 7-day operating period.

PRECAUTION: Thc x'ate of reactor power increase above the highest:

power lovel sust:aine:cl for at least 72 cumulative hours during th>> preceding 30 days oi operat:ion at power shall be limitc.d to 3% of full power in an hour. Alternatively, reactor power increase can bo accomplished by a single step increase less than or equal to 10% of full power followed by a maxitnum ramp raLc of 3'/ of full power. in an hour beginning 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months after tho stop increase.

The Connnit:Loc rcconnncnclcd approval of those cltangcs..75-38l RF-9.8. 1 Part Lc.n Lh P jl. Control Rod Drive Shaft UnlaLchin PCN 75-465. J. Straight prc cnLcd t:his procedure, chango. 1'L request:cd a now step 3.6 be added to reacl; Refueling integrity established as outlined i'ech. Specs. 3.8.1.

Tho Conmd.ttoc rcconnnondcd approval of this change.

95

t I

I Annual Rcport l/11 of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER:

75-382 Dia hra Valves PCN 75-680. J. Straight presented this procedure change. lt requested; 3.3 Valve to be inspected. Valve No.

Add step 5.9.4 Note any irregularities found during thc inspection and attach or note a list oi parts used.

Step 4.1 "diaphragm" Thc Connnittcc recommended approval of this change.75-387 SH 74-41.1 Reactor Tri Breaker, Train A 6 B Undcrvolta,c 20ET and 20AST Honitor Circuit In. tallation, PCN 75-683.

J. Straight presented this new procedure. The purpose of this procedure is to describe the stops necessary for installing monitor lights to verify proper operation and circuit makc-up of the trip breakers and undervoltage trip scheme.

The Committee recommended approval of this procedure.75-389 H-61.1 Hcchanircd Ultrasonic Examination of Reactor Vcssc)

Nozzle Nc1ds. S. Spcctor presented his past maintenance icvi<<w on this procedure. This job was completed on 4-1-7~.75-390 RSSP-2.7 Safet I'n ection Se uence Timers Train s A an d B PCN 75-682 J. Straight presented thxs new procedure. The purpose of this p roce dure is to set timers time sequence, for proper 1 d'a ing Thee Co Committee recommended approval of this change 75-394 H-43.)1 Stcam Generator Tube Removal PCN 75-716.

J. Straight presented this procedure change. It was requested to delete step 4.0, step 5.5 and attachment and attachment B C.

Step 3.11 should read; "required plant conditions shall be

'stablished as pcr paragraph 5.1 of attachment "A",

that 5.1.2 shall require that the water level in the except primary system be drained to the proper level and inaintained there as per operating procedure 0--2.3.1 S te P 4. 1 should

~ 1 >ave added, where tube plugging is in progress".

Step 5.3 should read; Specific instructions for the tube removal and tube hole closure procedure were followed pcr lSS-2.3.2 generator 1 series 44 S/G in leg of Stcam Generator.

Thc Connnittec rcconuncndcd approval of these changes.

- 96-

Annual Report fill of all procedure changes: (Continued) l/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION:

75-396 EM-139 Isolation And Maintenance Of Tntmo<liaec Boratc Valve Nov 350 pcH75-71o . s . spaetor presented t:his now pxocc:dure.

'fhe Connnfttea reeoinaoedad approval of'tls procedure. Thi.s item is NOT COMPLETE pe>>cling complot:ion of tho job, plus a post-mai.ntcnanco review.75-397 M-15;1 A or B Diesel Generator Removal From Service PCN75-(>92.

Jack Noon presented t: ho chango to this procedure. The POI<C recommendec approval of thc changes.75-398 H-37.36 Re ai.r of Pressurizer Steam S aco Sam le Valve '951, PCN 75-678. J. StraighL presented this new procedure. The purpose of this procedure describes ehe steps necessary for maintenance to the pressurizcx seoam space air operated valve 951. If this procedure is to be used in other than a cold shutdown condition it must be modified. Haintenance not required, may be marked N/A.

The Committee recommended appxoval of this procedure.75-399 H-38 E ualizin Char e Station Batter S stems PCN 75-707.

J. Straight present:od this. procedure change. It requested a

'change in the data sheets to include serial numbers of in-struments used. Also to change step 4.7 to read; Continue equalizing charge according to manufacturer's in-structions. Stablization of current reading can be calcu-lated by type of equalizing charge required. Phon normal main and small total chaxger current level i.s reached rocoxd voltage and specific gravity readings on all cells, temperature readings on designaeed pilot cells and ampoxage readings on main and small battery chargors for 3 consecutive hours.

Then sot timers for completion time designated by manufacturer's table. (NOTE: Hanufacturcr's instructions and data sheets attached).

The Committee reviewed and approved this chango.75-400 P-9 Prccaut:io>>s I.imitations and Sot: pints P-9 Radiat:ion HoniLorin S .,Lcm PCN 75-694s J. Straight pxoscntod this

~

procoduro change t:o bo made pormanonL. It was requested; Step 2.3.2s10 should road: R-19, (Stcam Gcnorat:or Blowdown),

Monitors for primary to secondary leakage, It is located in an area of'ariable background and thorofox'o, cannot alarm at too low a level. 6000 cpm is sufficient to not allow above mpc releases and yot not give, spurious alarm.

The Committee recommended approval of this change.

97

'I 4 Annual Report Ill of all procedure changes: (Continued) l/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION:

75-401 J. Straight presented thc following temporary procedure changes for review only; S-4.1C Li uid Haste Process 0 cration and Shutdown PCN 75-711.

Change stops 5.6.1 and 5.6.2 from 12.5% to 9%.

SM 74-23.1 Installation of the Modification for Control of the Boric Acid Sui lv to the Safet In'ection S stem ZCN 75-684.

This request was to change terminal black numbers.

RF-8.3 Coxe Loadin Periodic E ui ment Status Check PCN 75-704, PCN 75-705 and PCN 75-712. All PCN's were to facilitate stop N/A'd.

S-3.4F Boron Rec cle Process Shutdown PCN 75-698.

Requested step 5.8.6 be N/A'd.

The Committee reviewed these changes.75-402 M-605.5 lA Emer encv Diesel Protective Relay Calibration and Tri Test PCN 75-708.

M-60.6 1B Emer enc Diesel Protective Rela Calibration and Tri Test PCN '75-709.

J. Straight; presented these two new procedures. The purpose of these procedux'es are to provide instructions for removing and replacing protective relays associated with the 1A or 1B Emergency Diesel fox calibration or corrective maintenance.

The Committee recommended approval of these two procedures.75-403 CP-464.0 Calibration and/or Maintenance of Stcam Flow, Channel "464" PCN 75-710. J. Straight presented this procedure change. It requested some figures bc changed on the system data sheet.

The Committee recommended approval of this change.75-405 RSSP-2.6 Emex cnc Diesel Start and Breaker Closure Time, PCN 75-693. J. Straight presented this procedure change.

It was requested to add to step 6.1.2 and 6.2.2; IIConnect trace xccordcr to Diesel Generators voltmeter and diesel bu" tie breaker".

The Committee recommended approval of this change.

<<98-

Annual Report /ill of all procedure changes: (Continued) 1/l/75 to 12/31/75 Inclusive PORC ITEM NUtdBER: DESCRIPTION:

75-406 SM,75-23 Relocation of Accumulator Level Transmitter.

T, Schuler presented the modification design criteria xeport and system description, plus safety analysis fox relocation of level transmitters on both A and B loop accumulator. The level transmitter will be cut from their present position and raised 17 inches.

The Committ:ee reviewed the modification concept and pex'formed the'safety evaluation.75-407 SM74-30.1 Steam Generator Blowdown Jum er Swithch PCN75-732.

J. Straight presenLed this new pxocedure. This procedure is t:o prov.'de instructions for modifying the steam generator blowdown isolation valves (CV-70 & CV-71) control cirucitry to permit opening of the valves when main feedwater pumps are not out of service. The Committee recommended approval of this procedure.75-408 SM-74-30.2 Post S stem Modification 0 erational Test Of The Steam Generator Jum er Switch, PCN75-746. J. Straight presented this new procedure. This procedure is to outline steps for testing system modification 74-30 for operability. The Committee recommended approval of this procecure.

pending completion of the job.75-409 M-42.2, Removal And Installation Of Charcoal Fi1ters In The Post Accident Or Containtment Pur e Air Filter Systems, PCN75-759. E. DeMeritt presented this new procedure. This procedure is to describe the s teps necessary to remove or install charcoal filter trays. The Committee recommended approval of this procedure.75-411 RSSP-3 .0 Verification Of Emex enc Feedwat:er Pumps PCN75-751.

Start Lo ic Auxiliary J . Straight presented this procedure change. The procedure was rewritten the A-30 format. The rewrite also included according to Blowdown mode switch which has been aadded the Steam Generator The Committee recommended approval of e ass a system d'f' t modificat:ion.

this change.

75<<415 M-55.1 Re air ox Re lacement of Ty e P-2 Breal<e J. Straight presented this procedure.

Thiss procedure wa'M74-3 and rewritLen procedure describes the s teps nece s s Lo M-55.1. The replacement of b1-2 switches. The Co ary f or t >e xe air ox' ommiLtee reco ended procedure.

75>>416 H-6 Loss Of Com onent Cooling, J. Strai presen ted t:his procedure cha nge. PNC75-!165.

g I t w'as requested; ht On page H-6;5, Case XXX under "NOTE" Remove reference of compon ent cooling spray pumps igoing to containment JUROR pumps, and safety injection p mps.

The Committee disa should no t be remnvr d ppp roved this PCN because the reference - 99

t //ll of o all a prrocedure changes: (Continued) 1/I/75 to 12/3l/75 Annual Repor Inclusive PORC ITEM DESCRIPTION NUMBER:

PCN75<<-733. J. Straight kate 13oration- S stemTh's is cchange was to add 75-418 dure chango.

d low P m vent valve an to a valve number for s stem sys recommende roval of d d aapprov this change.

diagram. Th e Committee I 4

H-43.25 Installation Of Steam Generator Rand ol Cover PCN75-720 75-420 J. Straight presented for review the following changes; Delete stops 5.5 to 5.8 Change step 5.2 to read; "use old gasket" RF-8.3 Core Loadin Periodic H ui ment Status Check PCN75-717 requested to N.A. the second RHR sample in step 5.1.3.

The Committee reviewed these changes.75-423 J. Straight presented the following procedure changes. They all requested; Step 6.54 to read "return rod mode sele'ctor switch on >iC13 to auto position (if desired)"

PT-6.3.1 Power Ran e Nuclear Instrumentation S stem Channel 41 PCN75<<739.

PT-6.3.2 Power Ran e Nuclear Instrumentation S stem Channel 42 PCN75-740.

PT-6.3.3 Power Ran e Nuclear Instrumentation S seem Channel 43 PCN75-741.

PT-6.3.4 Power Ran e Nuclear Tnstrumcntation System, Channel 44 PCN75-742.

The Committee recommenclcd appproval of this change. This item IS COHPL1'.TE,75-424 S-4.1G "A"'1munclry & 11ot Shower Tank Release To Dischar e Canal PCN75-737 "13" Launclr 11ot Showc.r Tanlc Release To Dischar c Canal,

'-4.111 PCN75-738.

J. Straight present d both procedure for the following change; if

~

m'k

~

Change step 5,9 to add: or N A followed immediately by a low activity waste condens e tank release.

100 The Committee recommended approval of this change. This item

Annual Report I/ll of all procedure changes: (Continued.) 1/1/75 to 12/31/75 Inclusive PORC ITIC NUI43ER: DESCRIPTION:

0 75-428 SM74-40.2 Installation of Voltmeter for indication of backu su 1 for Instrument Busses A-I3-C-D PCN75-755. J. Straight presented this new procedure. This procedure's'o describe the steps necessary to install a voltmeter for the backup power supply to ins trument busses A-B-C-D. Thc Committee recommended approval of this procedure.- This item is NOT COMPLETE pending completion of the gob.

75<<429 EM-139 Isolation And Maintenance OfImmediate Borate Valve MOV 350 PCN75-719 and PCN75-721. J. Straight presented these procecure changes.

PCN75>>719, requested to add to s.tep 5.1; 398A Closed PCN75-721, requested to change step 5.2 to read; Hol.d valve MOV 350. Remove motor leads and control leads from MOV350 (Be sure to maintain proper wire identification)

Step 5.2.1 Remove heat tracing from area of MOV350, if necessary (otherwise mark N.A.)

Step 5.6 Replace wiring into MOV 350 and reconnect heat tracing

~

if removed 5.6.1 Stroke valve to verify proper operation after removing

'tep holds from step 5.2 The Commit tee recommended- approval of these changes,75-430 SM75-23.1 Relocation of "A" 6 "B" Accumulator Level J, Straight presented this new procedure. This Transmitters'CN75-767.

procedure descr'ibe the steps to be followed for removal and reinstallation of the A and B Loop Accumulator Level Transmitters LT-934, LT-935, LT-938 and LT<<939. It is necessary to relocate t ce level indicators to a higher elevation in the>e ex>sting to bee aablee to meet the t' ocation h new Technical Specification requirements 0 f at least 1 1100 cu. ft. of water in each accumulator or. To register thee proposed levels, the level transmitters must b e rai ase d 16 .778 inches. The Committee recommended approval of this procedure.

101-

Annual Heport //ll oi'll procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive POHC ITEM DESCHIPTION:

NUMBEH'5-:432 PT-14 Circulatin Water Pum s - Hi h Hater Tri Lo ic PCN75<<758 and PCN75-761. J. Straight presented this procedure change.

PGN75-758 - was temporary for review only PCN75-761 - requested, to add to step 6.5.8 as follows; "close states bl.ock N6 in THE terminal. box" also make additional changes and correction as per attached marked up copy (marked up copy incorporates PCN's75-758 and 75-761)

This was to be made permanent. The Committee reviewed PCN75-758 and recommended PCN75-761 be approved.75-438 M-34 Removal & Reinstallation of CVCS Relief Valve 209 PCN75-774.

J. Straight presented the following procedure change. It requested; Step 5.2.17 to read; "Seal water heat exchanger inlet, valve 265" Add step 5.3.1; "Open seal water heat exchanger outlet, valve 321" Add step 5.3.2; "Open seal water heat exchanger drain, valve 282C" The Committee recommended approval of this change.75-439 CP-465.0, Calibration and/or Maintenance Of Steam Flow Channel "465" PCN75-735. J. Straight presented thi.s procedure change. It was requested some figures be changed on the System Data Sheet. The Committee recommended approval of this change.75-440 M-45.3 Ins ection Of Non-Safe uard Motor For ,PCN75-785.

z of procedure be removed from first page, also step 5.2 should read; "Uncouple or remove belts, from driven unit" along with several minor changes. The Committee recommended approval of this chango.75-449 J. Straight presented the following new procedures.

E-6.1 Loss of Com onent Coolin Durin Power 0 eration, PCN 75"701.

E-6.2 Toss of Com onent Coolin 'N>lie Plant i.s Shutdown,

~

PCN 75-702.

E-6.3 Loss of Com onent Cool in Durin Recirculation Phase of Accident PCN 75-703.

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Annual Report //ll of all procedure changes: (Continued) l/l/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION:

75-449 E-18.1 Loss of S ent Fuel Pit Coolin Due to thc Failure (Continued) of the S ent Fuel Pit Pum PCN 75-725.

E-18.2 Loss of S ent Fuel Pit Coolin Due to the Failure of the S en t Fuel Pi t Hea t Exchan er PCN 75-724.

E-39.0 Fire At Facilit PCN 75-825.

E-39.1 Containment Vessel Fixe PCN 75-826.

E-39.2 Rela /Com uter Room Fire PCN 75-827.

E-39.3 Grinnell Delu e S stem Fire PCN 75-828.

E-39.4 Smoke Detector S stem Fire PCN 75-829.

E-39.5 S rinkle S steat Fixe PCN 75-830.

E-39.6 Auxiliar Buildin /Controlled Area Fire PCN 75-831.

'75 450 0-2.5'lant Shutdown From Hot Shutdown to Cold Shutdown When Condenser Steam Dum Is Unavailablc PCN 75-876.

The 'purpose of this procedure is to describe alternate methods of cooldown in the event condenser stcqm dump is unavailable.'he Committee recommended approval of this p'rocedure.

g5 4+5 S-3.2F 'rainin thc A B or C CVCS 1loldu Tank to thc 4'astc Holdu Tank via the Sum Tank Pum s, PCN 75-954.

The purpose of this procedure is to outline the steps:necessary to drain one of the CVCS Holdup Tanks to the waste holdup tank via the sump tank pump. The Committee recommended approval of this procedure.

-1.17 Communications PCN 75-953.

This procedure is to describe the communications available during a radiation emergency for use by the Fmcrgcncy Coordinator, on-site and off-site emergency survey teams. The Commi'tteq recommended approval of these procedures.75-453 J . Straight presented the following'procedures for changes to comply with Item 4 of I.E. Bulletin 75-04A.

E-20, 'mmediate Boration PCN 75-836.

E-7 Dro of a Full Len th Rod Cluster Control Assembly PCN 75-939.

E-]9 Continuous Insertion of RCCA Control Bank PCN 75-937.

E-22.2 Com lete Loss of Chan in Flow Due to Ru ture of S stem PCN 75-935.

E-26.1 Emer cnc Shutdown Resultin From A Reactor Tri > From 8.5% Power or Loss PCN 75-934.

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Annual Report i/ll of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION:

75-453 E-26.2 Emer cnc Shutdown Rcsultin from A Reactor Tri Vhcn (Continued) Between 507. and 8.5'/ Power PCN 75-933.

E-26.3 Emer enc Shutdown Resultin From A Reactor Tri Uhen 0 eratin at Greater Than 50/ Power PCN 75-932.

A-17 Plant 0 eration Review Committee 0 eratin Procedure, PCN 75-931.

A-51 Plant S stem Modifications Activities PCN 75-930.

0-2.1 Normal Shutdmm to Hot Shutdown PCN 75-919.

A-30 Plant Procedure Re uiremcnts PCN 75-929.

0-1.1 Plant Heat U From Cold Shutdown to Hot Shutdown PCN 75-909.

0-2.2, Plant COMPLETELY Shutdown From 11ot Shutdmm to Cold Condition PCN 75-910.

The Committee recommended approval of these .changes. This item IS 7'5 =454 M-45.1A Ins ection of Safe Guax'd Motor For PCN 75-835.

J. Straight presented this temporary change for review. It requested step 5.15 be N/A'd.

ST-73-4 DB-75 DB-50 & DB-25 Circuit Breaker Overcurrent Tri Device Test and/or Re lacement Procedure PCN 75-801.

J. Straight presented this temporary procedure change.

It was requested steps 4.1, 4.2, and 4.6 be N/A'd.

T-14B Isolation and Restoration of 5-A Fccdwater lleater, PCN 75-811.

J. Straight presented this temporary change. lt requested steps 5.16 thru 5.31 be N/A'd.

T-14C Isolation and Restoration of 5-8 Fcedwatcr 11catcr, PCN 75-812.

J. Straight presented this temporary change. It was requested steps 5.16 thru 5.31 be N/A'd.

The Connnittee reviewed these changes.

75= 456 0-2.3 Plant at Cold Shutdown PCN 75-911.

J. Straight presented this procedure change. It requested Step 5.3 change procedure H-1 to 0-2.3.1.

Step 5.4 change procedure H-4 to 0-2.3.2 The Committee rcconnnendcd approval of this change.

-106,-

Annual Report //ll of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRXPTION:

75-457, E-5 Control Room Xnaccessibilit PCN 75-918, J. Straight presented this proccdurc change. It was requested in step 4.9 1985 psig be changed to 2235 psig, also in step 4.12, the following be added; Refer to procedure, E-20, "Innnediatc Boration" if necessary.

The Committee recommended appxoval of this change.

75-<58 E-17.1 Reactor Coo]ant Drain Tank Pum 0 eration For"'Ccrc Coo 1 in 1'CN 75-917.

J. Straight presented this procedure change. It was requested this procedure be eliminated. Xt was the recommendation of PORC that this be disapproved and the procedure remain as. is.

This item XS COMPLETE.75-459 0-1.2 Plant From Hot Shutdown to Stead Load PCN 75-920.

J. Straight presented this procedure change. It was requested a new step 5.5.16 be added and some minor changes made for axial flux difference'.

The Committee recommended approval of. this change. This item IS COMPLETE, 75%60 E-4 Station Blackout 0 eration FCN 75-921.

J. Straight presented this procedure change. Changes were made to comply with X.E. Bulletin 75-04, Xtem 4, plus rewritten to conform to A-30 format.

The Committee recommended of these changes. This item IS COMPLETE.75-461 T-32 Fire Service Mater S stem PCN 75-916.

J. Straight presented this procedure change. It wAs requested changes be made to incorporate'dditions to the system.

The Committee recommended approval of. this change. This item IS COMPLETE

/5-462 E-28 Reactor Coolant Leak PCN 75-757.

J. Straight presented this .procedure which was revised and re-written to A-30 format.

The Committee recommended approval of this change. This item XS COMPLETE.

75+9h. E-]7 Loss of Residual llcat Removal, PCN 75-936.

J. Straight presented this procedure change. It requested in step 1.1.1, FA-626 be changed to A-20, also in step 1.1.4 after trip alarm "J-9" be added.

Thc Conm>ittcc rcconnncndcd approval of this change.

105

AnnUal Rep'ort Ill of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEH NUMBER: DESCRIPTION

~ 75-A95 E-15.1 Malfunction of Pressurizer Power Relief or Safet Valves, PCN 75-938.

J. Straight presented this procedure change'his chango was to include ncw. prcssure setpoints useful annunciators and improved idea for determining PRV leak.

The Committee recommended approval of this change.

75-49$ EM-108 Rc air of T.eak on Letdown to Reactor Coolant Filter, PCN 75-8?1.

J. Straight presented this procedure change. It was requested; Add New Steps:

5,5.1 Open Drain Valve 2237 5.5.2 Remove flange and open vent valve 2257 5.8.1 Close vent valve 2257 and drain v'alve 2237 The Committee recommended approval of this change.75-497 M-28 Removal of Pressurizer Safet Valves PCN 75-729 PCN 75-771.

J. Straight presented this procedure change. This was changed from M-28 to H-37.

PCN 75-729 - add NOTE to allow steps to be marked N/A if pres-surizer has been previo rsly purged.

PCN 75-771 - Add References; 2.1 Reactor Coolant System Engineering Flow Diagram 2.2 RSSP-11, Refueling Shutdown Surveillance Procedure, Pressurizer Safety Valve Test.

Change step no. D.3 to read; Pin spring restraint at discharge elbow.

Change st'ep no. D.7 to read; Remove pin in discharge elbow spring restrain.

The Committee recommended approval of this clrange.

75- 498 J, Straiglr t presented the two following alarm cards for additions; I

K-15 Fire S stem Tank T,o Pressure, PCN 75-9)5.

Requested: a step 4 bc added to read; 4. Verify motordrivcn and diesel driven fire pumps have, started (85 psig for diesel)

K-3) Fire S stem Alarm Panel PCN 75-9)4.

Requested to add to 4; 4. Refer to SC-3, Fire Emergency Plan, E-39, Fire Series and T-32, Fire Service Mater Syst: em.

The Committee recommended approval of these changes.

Annual Report !Ill of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITI?M NUMBER: DESCRIPTION 75- 499 A-54.2 Ginna Station Staff Res onsibilitics for Fire Protection, PCN 75"928.

J. Straight presented this ncw procedure. The PORC discussed this procedure but recommended it be reviewed further and presented at a later date.75-463 EM-140 Re lacement Of Rod Drive Housin Ca PCN75-802.

J. Noon presented this new procedure. This procedure is to describe the steps necessary for replacement of a rod drive housing cap. The Committee recommended approval of this procedure.75-464 PT-32, Reactox'ri Lo ic Test on "A" or "B" Trains PCH 75-874.

C. Hartlieb presented this procedure change. Changes were re-quested to provide steps to verify monitoring lights for 20ET and 20AST trip scheme, also Train A & B reactor trip breaker undervoltage scheme.

The Committee recommended approval of these ch'anges.75-465 M-llsl2 Isolation of Safet In'ection Pump for Maintenance or Ins ection PCN 75-873.

J. Noon presented this new procedure. The purpose is to out-1'ine a procedure for isolating a safety injection pump for maintenance or inspection.

The Committee recommended approval of this procedure.75-468 J. Straight presented the following procedures for review:

RSSP2.6 Emer enc Diesel Start & Breaker Closure Time PCN75-793.

Requested to omit step 6.2.8.

PT-6.1A Calibration Procedure - Source Ran e Channels PCN75-745 requested steps 12 through 12.17 be N.A.'d.

PT-32.1 Plant Safe uard Lo ic Test A or B Train ICN75-872 re g ardin g steps 6.8 through 6.11, IIall with logic development for the main S.I.test switches concerned logics c are too bee p laced in test position". ced RF-10 0 PCN75-605 Fuel Transfer S stem Checkout & Demonst x'a mon t' requesred soaps 5.13.1, 5.13.15 aud 5.14.5 berocec I ure N.A.'d.

PCN75-558 - s te p 5 .113 ro ba performed wish a flooding and, the first element with an RCC wwill visual dheek before the check. This > s iss to be made permanent. The Committee toreviewed bcc use used verif verify these items. This item IS COMPLETE.

- 107-

Annual Report gll of all procedure changes: (Continued) 1/1/75'o 12/31/75 Inclusive PORC ITEM Nm SER: DESCRIPTION 75-373 M-43.15 Reinstallation of Stcam Gcncrator Hanwa~ Insert and Cover Clo.,urc PCN 75-697. J. Straight presented this procedure change. Several changes vere rcqucstcd to provide more informa-tion and better guidelines for torquing.

COMPLETELY Thc Committee recommended approval of these changes.

IS

'75-469 E-22.1 Malfunction Of The Char in S stem PCN75-764. J. Straight presented this new procedure. The Committee recommended this pro-cedure for appxoval, E-22.3 Malfunction Of The Letdown S s tern J. Straight presented this new procedure, The Committee recommended approval of this procedure also the deletion of; E-22 Malfunction Of Char in Or Letdown as it has been rewritten into two new proceduxes.75-470 PT-23.5A Containment Isolation Valve Leak Rate Testin Containment Sum Recirculation To "A" RHR Pum PCN75-743. J . Straight presen ted this procedure change. It requested step 6.4 to read; NOTE: Piping flanges must be tight to insure zero leakage between flange and gasket The Committee recommended approval of this change.75-473 EM-107 Ins ection & Re aix Of Safet In'ection S stem Relief Valve 887 PCN75-640. J. Straight presented this procecure change.

It was requested step 5.2; change valve numbex to 2918, step 5.3, change valve number to 2918 also in step 5.6.1. The Committee recommended approval of these changes..

'P>>2 Reactor Coolant S stem Precautions & Limitations PCN75-805. J. Straight presented this procedure cl)ange.

This change requested new setpoints be incorporated. The Committee recommended approval of this change.25-475 RSSP-ll Pressurizer Safct Valve Test PCN75-773. 'J. Straight

~

presented this procedure change. It was requested to remove check-off lines and sign-off lines on the procedure, except the data sheets, also change Item 3 to read; "Valve Set Press,. 2485 psig" The Committee recommended disapproval of the change to removed chcck-off lines and recommended approval of item 3.

108-

Annual Report /$ 11 of all procedure changes: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITEM NUMBER: DESCRIPTION 75-'476 GS-5 Securit Guard General Instructions PCN75-794. J. Straight presented this procedure change, It requested'o; Add; 3.7.1, Maintain appropriate log sheets to ensure accountability of all personnel within the protected area The Committee recommended approval- of this addition.75-477 GS-10 Securit Guards Actions Durin A Radiation Emer encv PCN75-795.. J. Straight presented this procedure change. It requested to; Add: 3.6.1 If an emergency occurs between the hours of 0001 and 0800, inlcude log sheets and sign-in sheets for previous day.

3.7 Tf required, verify attendance reports submitted to the Emergency Coordinator to determine the necessity of search and rescue operations.

3.7.1 Verification shall be determined through a check of appropriate logs and sign-in sheets.

The Committee recommended approval of these additions.75-478 O-l. 1 Plant Heat-U From Cold Shutdown PCN75-806. J. Straight presented this procedure change. It requested in step 5.? to change it to read; "RCS Filled and Vented (0-2.3.2)"

The Committee recommeneded approval of this change.

7 48 SM-75-1.2, instrument Cable Rerouting, PCN 75-722. J. Straight presented this procedure change. Tt was requested in step E.6 to delete the word "pulled" also to change step E.5 to read; "All conduit, junction boxes,. and supports outside of containment t have been installed and cable has been pulled, all in accordance with 9.9, B.ll and B.12.

The Committee recommended approval of these changes.

109

Annual Report li11 of n11 procedure clianI;cs: (Continued) 1/1/75 to 12/31/75 Inclusive PORC ITI H NIIHBI I(: ' I'.S C R Il'I'ION 75-481 PT-5.30 I"Z-5.40. PT-5.20 PT-5.10 Process Instrumentation Reactor protection Channel Tri Test Channel 1 PCN75-807 PCN75-808 PCN75-809 and PCN75-810. J. Straight presented these procedure changes, The'se changes requested changes in setpoints. The Committee recommended approval of these changes.

l 75-483 0-2.1 Normal Shutdown To Ilot Shutdown PCN75-834. J. Straight presented this procedure change. It requested; add note between steps 5.16 and 5.17 as follows; NOTE: Immediately upon 'opening 1G1372, verify that generator voltage is less than 19 KV.

~

If not adjust with base adjuster.

.~ The Committee recommended approval'f this change.

I 75-484 RSSP-1.4 Valve Interlock Verification - Reactor Coolant S stem PCN75-824. J. Straight presented the following procedure changes.

It requested in step 4.1 a sign-off line be added, also several setpoints be changed in the procedu're along with several new steps added. The Committee recommended approval of these changes.75-491 The following SC series were presented; SC-l.l Radiation Emer enc Procedures General Information PCN75-904.

This procedure is to provide information of a general nature which pertains to Local, Site and General Emergency procedures.

SC-1.2 Local Radiation Emer enc Procedure PCN75-899. This procedure is to outline action required in the event that a Local Radiation Emergency is declared.

SC-1.3A Site Radiation Fmer enc Shift Foreman & Control Room PCN75-901.

This procedure is to establish the duties performed and the actions re-quired by the on-duty shift-foreman and operations for a Site Radiation Emergency.

SC-1.3B Site Radiation Emer enc Hmer enc Coordinator & Surve Center Assi nees) SC-1.3B PCN75-883. This procedure is to establish the duties performed and the actions required by the Emergency Coordinator and the Survey Center Assignees, SC-1.3C Site Radiation Emer enc Non-0 eratin Personnel PCN75-912.

This procedure is to outline the duties and responsibilities of non-operating personnel during a Site Radiation Emergency.

110-

Elk aport of all procedure el!angus; (Continued) 1/1/75 to 12/31/75 Inc 1 us i.ve PORC ITEM NUMBER: DIHCRIPTION 75-491 (Cont'd) SC-1.4 General Radiation Emer enc PCN75-903. This pr ccdure is to provide instructions'or actions to be taken in th even t of a General Radiation Emergency. I SC-1.5 Evacuation Procedure PCN75-898. This procedure is to outline the evacuation procedures to be followed Eor Local or

'site radiation emergencies. 1 I

SC-1.6 Ma or Release To The Lake PCN75-897. This procedure is to provide instruction for steps to be taken if a release, exceeds the maximum permissible concentration as specified'n 10 CFR 20.

The Cormnittee recormnended approval of the above procedures with modif ications.75-492 SC-1.7A Emer enc Radiation Moni.torin procedure PCN75-913.

This procedure is for the prime objective of Radiation on-site and off-site Monitoring Teams is to rapidLy survey areas downwind of the plant site in order to determine the extent and magnitude of any uncontrolled release of radioactive material following an incident.

Xt should be stressed that the initial off>>si.te survey is of great importance, decisions regarding extent and types of protective actions required wi.ll be based upon data reported by survey teams.

SC>>1.78 Field Determination of Iodine or particulate PCN75-903.

This procedure is for the determination of t: he iodine concentration so as to relate to inhalation and resultant thyroid dose is extremely important during the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after a release. The information is required with as little delay as possible. Therefore, the procedure consists of simple methods with approximate results and expected loss of sensitivity, sub-sequent surveys can be made to obtain more accurate information.

SC-1.7C Moni.torin Site Radiation Level 8 TLD PCN75-900. This procedure describes the use of thermo>>luminescient dosimeters, TLD, to determine the radiation level at the site boundary and at the site environmental stations.

SC-1.8 Post Accident Environmental Sam Lin PCN75-884. This procedure is to be used in the event of an emergency, the normal environmental sampling program is .suspended by a more intensive and specific program of sample collection aimed at deteriming, as soon as possible, the extent of the emergency and its effect on the environment. This emergency program utilizes the on site and off site continuous monitoring stations.

In addition grab samples wilL be collected from the down wind direction as deemed necessary, such as soil, crops, milk or ~ater. The nature of the emergency and environmental conditions will indicate the extent of sampling and the locations from which samples vill be collected.

SC-1.9 Post Accident In-Plant Radiation Monitorin PCN75-896.

This procedure is to establish the guidelines for in-plant radiation moni.toring during a radiation emergency.

SC-1.10 Plannin Conduct and Evaculation oE A Radiation I'.mer encv Drill PCN75-895. This procedure is to provide a means of testing evaluating and documenting the response of all participating off-site agencies and/or plant personnel during conduct of a "Radiation Einergency Plan" drill. 111

nnua cport ll of oil procedure changes.'Continued) llll75 to, 12!31!75 Inclusive'ORC ITEH NUHl)RR: DESCR IPT ION 75-492 (Cont 'd) SC-1. 11A Immediate Rc-Entr PCN75-893. This iprocedure, I is to provicc instructions for immediate entry for search and escue operations or other needs as determined necessary by the~ Emergency Coordinator.

SC-1.12A Immediate Call List PCN75-892. This is to provide an immediate call list and associated instructions. I

'I SC-1.128 Station Call List PCN75-891. This procedure is to provide the Emergency Coordinator with a list of phone numbers for station personnel.

SC-1.12C S ecialized Call List PCN75-890. This procedure is to provi e the Emergency Coordinator with 'a listing of names and phone numbers of off<<site personnel and facilities that may be required for special assignments during a Radiation Emergency.

SC-1.12D Management Call List PCN75-889. This procedure is to provide the Vice President of Electric and Steam Production and Division Superintendent of Electric and Steam Operations a readily available listing of phone numbers to be used during a Radiation Emergency.

SC-1.13 Estimating Off-Site Doses PCN75-905. This procedure is to provide estimates of the dose in the areas around the plant and guidance for the selection of sampling locations. Information's needed early to decide what action mus.t be taken to limit the exposure of the general public, In the period before state and federal agencies arrive at the site to provide assistance, steps must be taken to define the affected areas, assess the extent and significance of the release and provide data on which appropriate protective actions can be based.

SC-1.14A Accountabilit Of Personnel PCN75-887. This procedure is to provide instruction for accountability of personnel within the plant protected area in the event of plant evacuation.

SC-1.148 Scarc!'escue 0 eration PCN75-888. This procedure is to provice instructions to institute a search and rescue operation.

SC>>1.15 Ins ection Of Fmer encv F. ui ment PCN75-885. This procedure outlines the equipment required by the emergency plan and the means of assuring it is available.

SC-1.16 Transfer of Emer enc Survey Center To Station 13A PCN75-886.

This procedure is to describe the reasons for and the steps required to transfer equipment and personnel from the Emergency Survey Center to the Auxiliary Emergency Survey Center, (Station 13A).

The Committee recommended approval of these procedures with some modifications.

112

t Annual Report //11 of nil proccdurc chang<<s: (Continued) 1/1/75 L'o 12/3l./75 Inclusive P0 INC ITI'.H NlNIII',R: DI S(lit T. PT 10N

/5-502 0" 2.4 Plant Shut(lown Prom llot: Shutdown To Col(l Shu t'down PCN75-875.

J ~ Str<<igh t prescntc.d this procedure change. It rcqucs tcd tltc Coll owing changes; Step 4~7 - e1 imina L'c re fcrcnce to A- 15 acid to s tcps 4 ~ 5 ancl 4. 7 reference to TS 3. 1.2 llcat:up nnd Cooldown Step 4 . 6 not c: cl>ange 1800 to 2000 ps I g St.cp 4. 12, 5 . 8, 5. 9 not:c only cltnngc 1000 L'o 2000 ps ig SLcp 5. ll., change prc: sulr~cr no load level Lo 19. 5 and lab sea l. ~ I'o 35" Step 5 5 add, l<cfcr to 0-2. 5 i.f atmospheric stcam dump is

~

unnvn i l.nb lc Thc Commit tc<<r!.commend(:d approval ol'hese changes.75-503 S-3 . ill Prc-0 erat i onal l,i nc.-U 0C Boric Ac i(l Svs tern I'CN75-752

& PCN75-870 ~ J ~ St:might presented tltis procedure change. It reques ted PCN75-752 - stop 6 should leave valves 827A and 8278 closed also to upda te to A-30 format ~

PCN75-870 - requested to omit step 19 The Committee recommended approval of these changes'5 504 RSSP-2.3 Emer encv Diesel Generator Annual Tri Testin PCN75-941 PCN75-942. J Straight presented this procedure

~ change.

PCN?5-941 - requested under Initial Condition 4 4 to delete ~

(PT- 12A or PT- 128) change to (T-27 . 1 or T-27 2) ~

PCN75-942 - requ sted changes be made to the procedure to reflect addition of new governor boos ter.

The Commit tec recommended approval of the change ~

75-507 SC-1 ~ 9 Tn-pl nnt lincl i at: ion hlonitor in,. PCN75-963. J . Straight:

prcscnL'<<(I I:h is proccclurc. change.. 1t rcqucs L'cd a ncw step 3 l. 2 ~ ~ ~ 4 bc added Lo re<<el "Survey tfct:cr" T)tc Commi t: t:ce recommended nppr ovn 1 of th f s change .75-508 SC- l ~ I 0~ 1'1 nnn ln ( on(hie L nnd

~ I'nlu l L I()n (~l A IC<<(l lnt; J(>n I'm('.r cnc Dr i I 1 I'('.N? 5-964 ~ .I ~ 8 t ra 1I',ll L p r('.scn tc(I tll I 8 p r()cc(hlrc (:hnngc ~ T I; rcqucs L'(:cl L'(i chnngc cxis ti>>I; st cp 3. 1 t o 3 ~ 2 nnd ndd st<<p 3~1 I o r<<<<d; i

"A plnnn('(l site rn(l ation (tmcrl,cncy dr%1 1 involving on-sit c pcrsonn(.1 shul. 1 bc conduc tc.d nn>>u ( l.ly" 113 O'Ill'I I'II& A/1tlllulle Aeinwcwic ri (' (

P

)or o a 1 proccdurc changes: (Cohtinucd) 1/1/75 to 12/31/75 Inc 1'us ivc PORC ITI l"l N UM )31'.R: l)ESCt<IV'fH)N 75-500 SC-6 Action For ltn~nrclclus (,'hc.micnl S ill P('N75-927..'l. Straight:

prcscntcd this ncw procedure. Thc purpose of t:his procedure is to outline actions to bc: Lalccn in case of a major spill of hniarcious chemicals. The Commit t:cc recommended approval of t:his procedure.

item IS (,'OMPLt Tl'75-510 M-32.1 Dt3-25 l)tl-50 and DI3-75 Circui.t llrcal<er Ovcrcurrent Tri. Device Test and/or Rc laccmcnt Proceclux'cs P(,'N75-677. J. Straight prcscnLcd this procedure change. This procedure was ST73-4 changed to ll-32.1.

This procedure is to perform maintenance and ovexcurrent tri.p device test and/or repl.acement on DB-25, DB-50 and DD-75 air circuit breakers, S-2. 1 Reactor Coolant Pum 0 era tion PCN75-965.

6r 8-2.2 Pressurizer Pressure and S ray Control, PCN75-969.

J . Straight presented these procedures for the same change. It requested a new heat-up and cooldown curve page be added. Also to add a note to the procedures.75-511 J . Straight presented these procedures fox changes; O-l.l Plant Heatu From Cold Shutdown To Hot Shutdown PCN75-968.

'-2.2 Plant Shutdown From llot Shutdown To .Cold Condition PCN75-'67.

0-2.4 Plant Shutclown From llot Shutdown To Cold Shutdown PCN75-966.

It was requested to add a new heatup and cooldown curve page to these procedures . The Committee recommended approval of this change.

change.75-513 ll-6 Com onent Cool Service Service Mater Lo Flow. PCN75-837.

J. Straight: present:ed this procedure change. It was requested the alarm scLpoint be changed to 1000 gpm. The Committee recommended approval o f. th is75-513 SC-1.16, Transfer Of l'.mcr,e>>cv Survc Center To St:ntion 13h, PCN75-973.

J. Straight: prese>> t c.d t his procedure clln>>gc. It was rcqucs ted; St:eps 3.1.1.2 nncl 3.1.1.4 change "cars" to "vehicles" also to acid ncw st:epl 3.1.1.3 - Vehicles greater than 2000 cpm shall l>c cl<<cnntaminntccl prior t:o exiting plant: si.tc. Thc l'.m<<rgclncy Coorclinnt:or mny'cont:;let: the Ontario Fire (',ompnny, (lt<<t5cr t:o SC-1.12C Spccinlizeci Call List: ) t:o assist: worlcillg down of thc vchic'lcs.

A hyclrn>>t: is lo<<ntcd nt thc corner of thc plant: clrivcwny nncl Lclkc Roaci.

Thc Colimlittcc rc.comme>>etc.cl npprc>vnl of th<<s<<. chnngcs.

114-

l Annual 'Itcijicirt /tll of all procccluro cltangco: (Continued) '/1/75,t..o 12/31/75 Inc lus ivc PORC ITI H N tll'IIII lt: I Dl8 CR O'I'ON 75-5 1.4 I'CN7 ">-974. J. 'L'ra i.gl> L proscntcd tlti.s procedure el~ant;c. i.t: was roquosLod Lo insorL tlute fo 1 1 uw i.ng; 3.3 Obtain a sample from tlto sytcm or sour'cc of tltc tltat was being discharged to bc anal.yzod 'ffluent by tho chcmis t:.

I 3.4 Record tltc estimated dilution flow (for example; one or two circulaLing pump flow) and estimated quanity of.

effluent.

Renumber s tcps accordingly.

The Committee recommended approval of these changes,75-515 SC-1.7D Eield Determination Of Iodine On Particulate PCN75-975.

J. Straight presented this procedure change. It requested; add the following note after step 3.3.4 and 3.4.3; NOTE: The possibility exists that the background may be too high to determine a reading on the filter, Xf this condition exists, an alternate locatio'n should be deter-mined to obtain filter and background readings.

The Committee .recommended approval of these changes.

75 516- SC-1.14A, Accountability Of Personnel PCN75-976. J . Straight presented this procedure change. It was requested; Add to step 3.3: In addition, t: he Emergency Coordina tor will:

3.3.1 - Notify the Control Room to have tho unaccounted personnel paged on the plant P.A. System 3.3.2 Consider the possibility that the unaccounted personnel may have left the site. The guard stationed at: tlte plant:

driveway may be interviewed to determine if he ltad witnessed any personnel leaving, or possibly a tolcpl>onc call to tho individuals homo may be considered.

Tlto Commit:tcc rcconnnondocl approval of. tltoso changes.75-517 S('.-1.1~ill Srarclc Ancl ltcscuc. 0 orat:ion PCN75-977. J. Straigltt present eel tltis procccluro clut>>go. Lt rcquusLc.cl Adcl ncw st:cp 3.1.4 "assumo an I'.merge>>cy llrdical Treatment si tuation u>ay cxisL'ncl alert: tlto plant: cloctnrs. Itci',cr to SC>>1.12C, SpccialJ.eccl Call List"

l Annual. Rcport /ill of all procedure changes 1 (Continued) 1/'1/75 to 12I31/75 NllH1N R 75-518

'ESCR PORC IT1 M T.P'1'TON Inclusi.vc Cclltcr A.la 1

~

aces PCN/5<<9'/9. J. Straight r<<qu<< tcd this proc<<durr cllnngc. ll. requested to add to step 6; "To assure personnel accountabili.ty, cuter names in the emergency log of individuals assigned a>>d tile teams to which they ale assigned Also to add thc followi.ng after step 17; The following routes sllall be used as determined by Emergency Coordinator:

1; Lake Road Eas t: When wind is from the east

2. Lake Road West: When the wind is from the west

3. Route 350 South: When the wind is from the south

4. Lake Road East and West: When the wind is from the north The Committee recommended approval of these changes.75-519 SC-1.12C S ecialized Call List PCN75-980. J. Straight presented this procedure change. It requested title or names be added to some of the steps. It also requested the following new steps be added:

3.1.8 Nuclear Regulatory Commission 3.1.8.1 Nuclear Regulatory Commission 7-9-215-337-1150 Region I King of Prussia, Pa.

3.1.8.2 Radiation Assistance Program 7-9-516-345-2200 Nuclear Regulatory Commission Brookhaven Area The Committee recommended approval of these cha'ages.75-520 S-7J Transfcrrin 6 Purification Of R.W.S.T. Water From R. W. S. T.

To Refuel in, Cavity PCN75-906. J. Straight presented this procedure change. It was requcs tcd in title<<af ter last two words (refueling cavity), add "or Primary T.onp". Thc Committee rccoalmcndcd this be reviewed only and disapproved.75-534 FM-141 Excess T.etdown Linc Relocation PCN 75-1025. J. Straight presented (',is ncw procedure. 'i.'his procedure is to describe the steps necessary to relocate the excess letdown line to allow suf-ficient rattle space at the "A" Steam Generator platform. The Committee recommended approval of this procedure.

116

Annual Rcport 811 of a11 procedure changes t (Continued) 1/1/75 t:o 12/31/75 Inclusive PORC ITl'.M NUNIIKR: Dl'.SCRT PT ION 75-987.

75-75-536 SM-75-4.1 Reroute of. Stream Generator Slowdown l,ine PCN J. Straight presented this temporary change for review:

Step E. 13, Change words to read as follows:

.....Work Procedure (WP004), with t:hc exception of the tie-ins of tank which blowdown and drain lines to two 8" header to blowdown were completed and accepted by RGSE , has been inspected The Committee reviewed this change.75-538 S-4.1E Waste Condensate Release PCN 75-972. J. Straight pre-sented this procedure change. It reques ted the following be added to step 5.13:

"Ii DI's are not available, mark steps 5.13 through 5.28 N/A and transfer to WllT The Committee recommended approval of. this change.75-539 T-27.2 18 Emer enc Diesel Generator Pre-Start Ali ament PCN 75-986.

J. Straight present'ed this procedure change. It requested:

Step, 6.3.8.1 should read ....15 on scales . 8 on ind ica tor Step 6.3.8.2 should read - Speed droop setting 5.2 Thc Committee recommended approval of this change.75-541 PT-7 ll drn Test of Reactor Coolant: S stem PCN 75-990.

J. Strait;ht present:cd this procedure change. It: request:cd Lo delete Step 7 from Primary System llydro-Checklist. Thc Com-mit:t:ee rccommcndcd approval of this change. This item i.,

~corn l.ate.75-542 GS-10.l Sccurit Guard Action Durin ~

A T.peal ltatliation Emcr-cnc l'CN 75-981. J. Straight prcscntcd this ncw procedure.

This procedure is to ouL'line action required by the SecuriLy Force in thc cvcnt'f a local radiation emergency. Thc Com-mittee rcconnnendcd approval of this new procedure.75-544 E-29. 1 T.oss of Normal Feedwa tcr Not Recoverable PCN 75-952.

J. Straight presented this procedure change. Ir requested a note be added after 3,2 to read:

NOTE: If all rods are not known to be fully inserted after a reactor trip refer to E-20, "Immediate Boration."

The Comm'ttce recommended approval of this change.

117

/Ill of a11 )fruccdurc changes: (Continued) 1/1/7a to,'12/31/7a Annual. Rcport Inclusive PORC ITEM

)1ESCR T PTTON NUNIII5<:

75-546 E-ll Continuous Rod Wit)idrawl PCN 75-951. J. Straight presented this procedure change. It was requested a new step 3.2.1 be added to read:

"If all control rods are not known to be fully inserted following a manual reactor trip refer to procedure E-20 "Immediate Boration,"

Several other changes were requested to comply with I.E. Bulletin 75-04A, Item 4. The Committee recommended approval of these changes.

75- 547 H-56. 1 Removal 6 Re lacement of Penetration Seals PCN 75-1056 T. Heycr presented this new procedure. This procedure is to de-scribe removal and placement of penetration seals using ceramic fiber material. The Committee recommended approval of this pro-cedure with modifications.

75- 548 SH 75-32 Installation of Seals With Bisco Silicone Foam PCN-75-1055. J. Scheetz presented the design criteria to the Committee for review on this SH.

Paul Wilkins presented the safety analysis. The Comnittec per-formed the safety evaluation and found that the modification does not involve an unreviewed safety question and that Technical Spec-ifications are not effected.

J. T,arizza presf;nted the SH procedure. The Committee recommended approval of this SH with modifications.75-555 SM75-23.1 Relocation Of "A" And "P." Accumulator Level Transmi.t ters, PCN75-880. J. Straight presented this procedure change for review.

It was requested; For SH75-23.1 usage on LT-935 and LT<<938 change 5.4 to read; "and at bottom"pipe" of level transmitter just above floor sleeve".

Also modify weld job traveler to include the above.

The Committee reviewed this change.

?5-5'>6 S-4.1C Lic uif) Waste 1'roccss 0 eratinn A>>fl Slf<<tdown PCN75-800.

J. Straight prese>>tcf) L)fis procedure change. TL'equcsLcd Lo afk)

L'o If<itial Conditions tlfc following II'IL I;vaporati o>> is s)fuLdown for canon oL)>cr t)fan drufmalng N.A. sL'<Ips 5~2 nffd 5.9 and s ta L'e reason 1: or s)nf tt)own on (Ia ta 1 og s) fuu t" The Coffmflttce rcconfffff.ndu() approval of t)>is c)>ange.

- 118"

Annual Rcport //11 of all procedure chnngcs,'Continued) 1/1/75 to 12/31/75 Inclusive PORC D'II'I HI(IIIII'.ll: DI Scltl'l I rnN 5-I()A 75-559 hnfuL Tn'nnl:Inn 5 ."tnm Al.l. mnu:nl(l(75-957 95(I 961. 905 nn(l 9H3. J. Straigl>t pr<<s<<ntcd tlicsc proc<<<lure chanl,cs.

PCN75-956 - request<<<1 t:o rcarranl c present: st<<ps to reflect morc accurate locat:ions; I

(ls t) Auxiliary Building (2nd) Xntcrmediatc Bldg. by Sample Rm.

5.2.1.30 5.2.1.28 5.2.1.29 (3rd) Xntermediate IIldg. by Aux. F.M. Pump 5.2.1.25 5.2.1.26 5.2.1.27 (4th) Auxiliary Bldg. Gas Storage Room 5.2.1.21 thru 5.2.1.24 PCN75-95? - requested step 5.2.1.16 make V-1816 to read V-1816A step 5.2,1.26 make V-1819 to read U-1819G PCN75-961 - requested step 5.7.13 should read:

5 7 >> I s7ss I

" I sc step 5.7.14 should read:

5.7.14 878D lD SF PCN75-985 - requested to change; Steps 5.2.1.16 - should be V181.6A 5.2.1.26 - should bc VlS19G 5.2.1.27 - should be V1819F PCN75-9S3 - was an explanation of steps marked ziti> astrisk and crossed out (different: ) val.ve position.

'1hc Corruaittcc reviewed and approve<1 these cl>angcs.

7 5-.'I (10 0-2.3.2 I'illin; And V<nitin; 'I'hc React:or Coolant System, PCN75-1000.

J. Straigl>t pres<<ntc<l tl>is procc<lure <<Iiange. It Was requ<<sted to; Add to step 5.5.10; I'oot valve outlot: It.C.I).T. to vent ltea<ler outside CV Vnlvn 171(>A Opnn Tl>c Conm>l.t t<<.. recommcn<l<<d approval of tllis cl>anl;c.

.- 119-

J '>

Annual Rcport I/11 of al.l procedure chanI;cs'. (Continued) 1/1/75 to 12/31/75 Inclusive E>OI<C ITI',M NUHIII',I<: I Df'.SCR PT ION 75-5(> > 8-OA (:o>>1 >>ncnt: ( polio 'ilntcr

~ 8 stc>>1 Start-ll Anm>cnL I'(:N?5-9(>2. J, SL'ra JghL prcscntecl th J.s proccdurc change. It: rcquc" tc>I; Change 5.10.2 to read; C(>l Supply to wasLe cvaporat:or air ejector ---261? open Change exist:ing stcp5.10.2 to 5.10.3, 5.10.3 t:o 5.10.4, 5.10.4 to 5.10.5 and 5.10.5 to 5.10.6.

The Committ:ee recommended approval of this change.75-562 RSSP2.2 Diesel Generator T.oad 6 Safeguard'd Se uence Test PCN?5-999 PCN75-1011 PCN75-1020. J. Straight presented t:hi.s procedure change.

PCN75-999 - requested step 6.5.5.2 to read; "18 Pump recirculation valve AOV 4310 Open" PCN75-1020 - was to facilitate steps 6.6 through'.23.10 N.A.'d.

PCN75-1011 - .requested;

1) Test Requirement 2.9.1, Delete existing requirement and insert the following: HOV 871A starts to close in 3.5 seconds (+ 1 second) upon failure of 18 SIP to start, after loss of bus voltage and
'receipt bf SI signal.
2) Test Requirement 2.9.2, Delete existing requirement and insert the following:>IOV 8718 starts to close in 3.5 seconds (+ 1 second) upon failure of 1A SIP to start, after loss of bus vol.tage and receipt bf SI signal.
The Committee recommended approval of these changes.75-563 S<<4.2.1 Haste Gas System Valve Ali.,nment For Automatic 0 eration, PCN75-1001. J. Straight presented this procedure change. It requested a new s t:ep be added; 5.33.1 - RCDT outlet isolation Valve, ouside C.Y. Valve 1716A Open The Committee recommended approval of this cliangc. Thi.s item IS COIII I,l',rl'..
A 7 5- 5 (>7> SII75-1.2 Inst:r<m>cnt; Cable lterout:in ~ 17(.'N?5-100>'>. J. SL'raighL prcsenLcd thi: proccdu1 e change. It: was rc(Ines tcd; Step I'..9, DclcLe sign-off; of CAI Q.C. Supervt. or and ad, Delete word "contractor" Delet:c sEgn-oE'f: of CAI, Q,C. S<tpcrvlsor a>>d add sig>1-oft' for RCSI Q.C. I'.nglncer
I' w'".
Annual Rcp>>rt !Ill uf al1 procedure changes: (Continued) 1 1/1/75 to 12/31/75 Xnc 1<~~>s 7cction C.. Rc 5>>fr ol'nf>> Stcam isola( io>> Valv<.s PCN75-1005.,I. StraighL pr<.su>>Lcd L'his proccd<<rc alia>>fsc.~~
~~XL'equested; SLcp 5.1.9 should read: Replace or repair thc parts found defective. Note all rcplaccmcnt or repaired parLs on attache<1 rcport.~~
~~The Committee recommended approval of this change.75-588 M-37.21 Ins ection & Re air Of Hain Steam CI3eck Valves PCN75-1006.~~
J. Straight presented this procedure change. Xt requested step 5.1.8 to read; "Replace or repair any of the parts found defective, note all replacement or repaired parts on the attached report" The Committee recommended approval of this change.75-573 J. Straight presented thc CoLLnwing two procedures Cor temporary changes to bc'ade permanent.
1'T-25, C.ontainmcnt Air I'liter Post Accident CltnrcoaL I'l.l t<.r 13v-I'ass I'low, PCN75-I009. This requested after step 6.1. a note I>c added to read; NWZ8: If only ane unit is to be testa)i, merit o I:ba r onc N. A.
~kl-RA l)csin Ra Inca)cont A Co)))lftionin A an)i 8 Nixe)i llc)i lie) ~ inaraiirers PCN75-I010. Ct request<d steps 5.9 thro<<gh 5.9.9 l7c <mii.tL'cd, also a note bc ad<lcd to read; NOTI'. Xf it is desired to usc excess lithi<<m to raise the lithium conccnLration in the RCS thc following steps to be marked N.A.
Th<: Committee rccomm<.nd<:cl that L'hose temporary cha>>gcs b<. made permanent:.75-573 1'T-7 Il dro Test OC R<.actor Coolant: S stem, PCN75-1021.. J. SL'raight presented this procedure change. Xt requested tn; Change step ~i.2 to read "operating procedure b-l.l is done up to step 5.36" The Committee recommended approvaL of this cl>ange.
~~'3 '71~~
u <<llox't l'l, of all prucedux'e chilnl;cs: (Continued} 1/1/75 to 12/3l./75 Inclusive POItC ITI H Nl.ll'1111 It t Ol;SClt I I P rON 75-57'. Straight prosented the following ncw procedures; E- l.. 1 Sa fot In 'ection Syst: em Ac tila t:i on PCN75-865.
~~l E- . 2 Loss of Coolan t Accident PCiN75-866.~~
~~E-1.3 Steam Linc Break Accident PCN75-867.~~
~~1 E-l. 4 S team Generator Tube Ru ture Accident PCN75-868.~~
The Committee recommended approval of these new procedures.75-575 E-1 Accident Sym toms & Detailed Recovery For. Loss Of Coolant Steam Line Break & Steam Generator Tube Ru ture PCiN75-207, PCiN75-173 PCN74-720 PCN74-721 PCN74-722 PCN74-723. J. Straight presented these PCiNls for several changes which was incorporated into the new t".-1 series.
~~The Committee recommolldod approval of these changes.~~
~~PCN75-869 - requested the E-l procedure be deleted and incorporated into E-l.l, E-1.2-, E-l.3 and E-1.4.~~
~~1 The Committee recommended approval of the deletion.~~
~~75-">77 0-1.1, Plant: Ile:it:-II I:rom Colil Hli<<tilown To Il<<t Slnltilown I'CN75" 1008.~~
.I. Striliglit presented this pro<<ed<<re cllailgo. It was rcqucstcil; Aild tn step 5.6, "Tho stcam gonorator blowilowil moil<<selector switcll is i I'l tile i AIJX pos i. t on Thc Committ:<<o rccommendcil approval ol: this change.
~~75-5S1 S-4.2.1 Waste Cas S stem Valve Ali nment For Aut:omatic 0 eration, PCN75- 1029 PCN75-1030.~~
~~PCN75-1029 - requested steps 5.45 through 5.5o be N.A.'d.~~
~~This was a temporary request which the Committee reviewed.~~
PCN75-1.030 - request:ed the following clianges; I'.liminato steps 5.45, 5.45, 5.46 Chango st<<p 5.47 valve numbex from 1674B to 1875 Cllangc stop 5 49 vtllvo numbex from 16741) t.o 1830 I liminate step 5.50 Tho Committee recommended approval. of this chhngo.
~~122-~~
/
~~J t~~
I
~~'L t~~
l
Annunl R<.'port 811 of n11 procedure chnngcs: (Continued) 1/1/75 to 12/Jl/7a Inc lus ivc PORC ITI',H N))HI)I'.R: DISCR IPTl ON 75-582 RL'iP 7-..7 lie<at Tn'aaL/ou .'la(eau <: .Tlmr r:: Train A uncl ll PCN75-')96. J. Strni);hL prescntu<l tlii.s proc<< lure chan);c. It rcquc" tc<I all I..~ sec. tolcranc<.s in steps 6.14 an<) 6.33 be chan);cd as foll.ows:
~~Thc + .5 s'econ<I tolerance should bc changed to + 0 second and thc -.5 second tolerance should remain as is, The Committee recommended approval of this change.~~
~~Pg 75-583 0-1.2 Plant I'rom )Iot Shut<)own To Stcn<l l.on<i PCN75-101.8.~~
~~J. SLraighL presented this procedure change. Xt rcqucsLed to; add step 5.5.6 as follows:~~
~~4: step 5.5.6 at 100 )M close the vents from the Hain Steam to reheatcrs piping to thc condenser.~~
~~1A Reheater Main Steam Vent Closed~~
'lB Reheater Hain Steam Vent Closed 2A RcheaLer Hain Steam Vent Closed 2B Reheater Hain Steam Vent Closed Vent piping condenser isolation valve closed II Renumber existing steps accordingly.
~~The Committee recommended approval of this change.~~
~~75-5S6 A-52.2 Control of ).ockcd Valve 0 eration, PCN 75-1102 J. Straight prcscnted this procedure change, It reques.t-to add the following valves:~~
'd 4070A Condensate Storage Tan!< 9 - Makeup to Ilotwcll Op<.n 4071A Condcnsatc Storag>> Tonic A - Makeup to llotwell - Open 40718 "Makeup Line to llotwcll Drain - Closed The Conm>ittcc recommcndcd approval of this change.
E
~~-123-~~
a~
Attttu<ti, It('.po'rt j/11 nl.'t11. 1)r()cc(lure clt<tttI,'ca.t (Cont 1ttuc<I) 1/1/75 Lo 12/31 75 Inclusive' 1701tc lTL'H NIII'113 I'.ll: I)l'.SClt T I'I'ON
~~75) ( <Iqa I- ) Ih hl I annuli'f Anvil iarv~~
~ aa
~
I'((<lwal <;r S . I:('n) I'rI<)r, 'I'o I'<)wc'r
~0))) aL'Il)ll) I'('II 7'I- I l(I() ..ISI ) <)i( I)L I))u-an( ad Ii)I..': I)rUcu)IIIIL change. I.L(!q(!(!sL(;d Lo <<(I<i Lhc followlnll stol)!a:
~ 5.4. I.lh (;ondcni at'c Iltoragc T u)k I)r<)i)) V-4073 l,ock Clo'ccl
5. 5.1113 Condcnsat:c SLoragc 'I'anlc l)rain V-4072 I.nck Cl<)scd 5.8. 1 Con<lcnsatc Halccup l,inc L'o IloLwcll l)rain V-407113 Lock Closed (Locate<I in Sub-l)asuncnt)
~~5. 5.2 Con(lcnsaLc: SL'oragc Tank 13 Hakcup L'o llot:well V-4070A Lock Open~~
~~5.4.2 Condensatc~~
Storage Tanlc A Hale<up to llotwell V-407].A Lock Open The Committee recommended approval of these changes.
75- 593 O-l.] 1'lant -Ilc:atu I:rom Cold Shutclown L'o ]lot: Shul:down I'CN 7.')-1032..I. Straight prescntc<1 t I>is procedure change for rcveiw only . It request:cd the following changes:
1)clete Step 5.3.1 and move that statement: to next page under new Step 5.37.2.
5.30 Sc.t non-regenerative heat exchange r tcmpcrat<!rc control-ler TCV-130 to maintain 127 0 F on manua]..
The Committee reviewed these changes.
75- 59() 0-1.2 Plant From lloL Shutdown to Stead 1,oad PCN 75-].072.
J. SLraight presented t:his procedure change. It requested Insert addiL'ional step after Steam Generator Feedwater pump is starLed to return jumper switch to normal and rcL'urn kcy to Shift Foreman.
The request was modified to insert this st:ep just prior to the pump st:art, since thaL po. ition is necessary to sLarL.
Lhc'ump.
The ConaniLtcc recommended approval of thi.! change.
7.)- 595 0-2.1 Nor(nal Shut:<lown t'o lint: Shut <lown I'CN 75-]071. J. Straight present:ed t'his procedure cha(>gc. It rc.ques t:cd:
lnscrL'rovision Lo place blowdown jumi)cr swiL'ch L'o t:hc Auxi 1-i )ry I)o I L ton.
I he (ION ni t tee '( < c<I)lllnll n(l ( (I al pl)rovat 1 0 f I h I s chalnla(. ~
')/)
At)t)U') l lt('.pot t t/ l.}. ul. () 1.}. pl. (>c('(Iuru ct)a>>1,'(U): (t'unt I >>uc(t) '/ I./ /a L'0 12/ J }./ /y I>>C luu iVc POlt(l I'I'I H NIIHIII',ll: I)I.I>(.lt1 I' 7ON 7'>- 99(> 0-2.2 I'lan< illa>Ladwn I'rnn llnl: I'In>(dawn Ln ('.<>Iddi>>>(d>>w>> I'('.N
/5-10/0. .I ~ ~>SL'i (i I }',hl'i.<<soul <<(I Lhi.'i ploc(i(lilru ch>>>l}'e I l.<<-
q(lc!i l (a(I:
Tiicliidc: provisioii to place biow(low>> jumi.er swit(:Ii .i>> cl(:I'<<at:
si t: i.on.
Hale() sonic ml>>(ir t.'ypin}, cli:i>>gcs.
The Connni.L L()<<reconnn()>>d<<d approv )1 of. L'li<<sc cli'>>igc.s.
7."> -! '? l l
> I'-23.1 Cont(il))nii)nl lsolat:io>> V'i1ve L(.alc ItaL(. 'I'(:st in" I i (is-anr incur. Ila(i<:I'ank <'.>~shn:rl xnr I.inr. I(N 75-(0(>:i. J.
8Lra i},ht present:<<d t:h I s procedure: change. It req<<cs tcd change of; formula on I'a};c. 3. The Commit:Lce recommended approval of this clian};e.
71 -599 I'-23.2 Containmeiit Tso'lation Valve Leak It:>te Testin Nitro- ~
en Su ) ly To Pressurizer lteli<<f Tanlc Li>><<PCH 75-1044. J.
Straight presented this procedure change. It requested change oC formula on Page 4. Th<<. Commi.ttee reconmiended approval of this cliange.
75- (>00 From Reactor Coolant Sv t:<<m PC>N 75-1042. J. Straight present-ed this procedure change.'t: requested a change of formula on Page 5. The Committee recommended approval of this change.
PT-23. S, Containment Tsol ation Valve Leak Rate 'I'est in.". IICS Char, in Line ~
PCN 75-1049. J. Straight present:ed this pro-cedure cliange. Tt requested a change of formula on Page 4.
Thc Con(mitt;cc recomme>>dcd approval of this change.
75- ('Q9 1>T-23.10 Containmc'nt 'Isolat.ion Valv<<Leak ital:(i T<<" tin) Al-ternal.e Cli.)r;in; Linc PCN 75-1046. J. Straiglit pres<<nted this procedure el)ange. 1L'(.'quested a change of form<<la on Page 4. The Con)mi tt<<e reconunenclccl approval ol'his cliange.
75>- ()03 O'I'-23.}l, Co>>tai>>me>>L Tsol;)tion Vi)1ve T,cole }tat<<. Te! tin, Alt<<r-n')t:e ('.liar);ii>>; I.i>>e, I'CN 75-'}045>. J. St:raight: pres(.nt <<d tliis proc cd>>1'c chi>>1};c f t rcque. t<<d a el)aug<<o C fonnu1'i on I"i},<<5.
I hc Co)ill)litt: Qe ) ccolinn<<i)dcd a ppl ov(ll o f t:his ch')>>gc, 7 ">- (>0/> I'I'-'?:l.l2>( (.'an(nina><!nu (::<>I>>< I<>>> (>>1>>r I.ral< llaL'u, 'I'u.".I:inr I'r<."-
iii))'i;:<<); Ht <<;im S >;)<<<<S;)ign)lc, I'('.N 7!>-1041. JHt r;I I}',ht p);cs(>Ill <<(I L'his rh')n};(). TL'('qiicst.c(l n ch;iiigc ol: CL>rnnil:) oii I';>};c /i. 'I'hc) t olllliliLt: <<('. i (.'<<on)nl<<n(l<<d 'i pprov'i 1 o C t'hi!: proc u(1 (i i (> ~
-125-
A)in()i)1. ItcPort: l/11 of n I. l. lit<>c(i(lure el)a))g<<s: (Coi)L'>>ucd) 1/1/75 L<) 12/3 1/'/5 Ii)c I,lt<) ivc VOI(C I'I'IJII NllHIII'.ll: I) I'.S>CIt I O'I'TON
/ >- (>()S ' "/ ~ > ~ >>> ( o>>t'n i))m<>>t I ~ '>>1'it I<>>> V ) I v< ~
I <<')k I):) I'< ~
1
'I'<>>) t. I>> ~ "A" Il.(.l'. L't'n1 II'>ll:r I.iau I'('N 7'i-i(l(>g..l. sir>>lghl pru nnLuhl I'hi:: Inucudnru el>aunu. It ruquu ru(l a clu>ui,c ul'unsn(n on 1 ll('oll)I)iI L I'ec ( ceo[Ill)loll<I('d rov<)1 0 f L'li I s eh:i>>g(i ~
/'>" (l()(l It.(:. I'. Se:) I H(it.'<!i f.iii(!, I'l'N /5-1()/) '/..I. Sl rn I.)slit pr(ssieiil (:d t:li Is I>).oce<h>r<: cli'ii)I;u. It: r<<<I<<<<ate<1 n cli'i>>),e olor.n)<<1) o>>
Pi)go 5 s I lie Coil)Ill ).l t('.(! r<<comme>>d<l>rov'il ol: Lliis chal))I'(!.
7.'i- 6>07 I'I'-)3. SA (:oi)t:;) I>>m<!)) l Tso].:iL'1<>>) Vn1v<<. I,enl< It:it:c 'I'e.,l: I>> s C<)i)la I>>)n<>>L .'><<>n I'<<:: Irciil.:>t. Ioi) I o "A't)lit I'iim) I'(:N /5-l()51.
J, Strnil;1)L'rese>>te(l L'liis proc(>re cli:ii)I;e. Lt rrq(icsted change of f'or)m)l<) on I'nI;e 4>. 'I'h(. CommiL'Lec rccommcnde(l npl>>.ov-al of: this 'chnng<>s 75- (>08 pi23.'> l l(onto(n)sun( T.'.clot!on Valve Ice(L Snl:a 'Ihstin" Con-tni>>m(.>>t'. S>>m It(ci cu],()tion to "I)" RIIR I'<<m> I'CN /5-10SO. J.
SLrail;lit: pre <<nted tliis procedure change. 1t rc<Iucsted a el)ange in formula on 1'ag<<4. '1'hc Co))))))it.tcc rccommcnded approv(il of this change.
75- 609 I'I'-23.3 'Cont:ainm<5>>t: Tool:it:i.on Valve Leak RaL'e 'I'<.s tin II<)1(c>> ) ~
I!nLar to prossuriror ilel(uf Teal< I'('.N 75-.!052. J. Iitrsight presented thI.S procsdnre chango. Ot regna.",tcd a change in for.-
mula on Page 4. The Commi.ttee reco'mmendcd approval of tliis Cll(ll)ge a 75- ff1 I PT-7 ll dro Test: of Reactor Coolant S stem PCN 75-103/). J.
SLrnight presented this procedure cliange. It requested:
Change 6.4 Lo read:
Close RIIIiS LeLdown valve IICV-133 and Normal Letdown orifices 200A, 2008 and 202, open AOV 427
'I,'hc Committee recommen<led <ipprovnl of this chan;;c.75-619 CP-209 Cnlibrntion of Area Radiation Honit:ors TA-62 Detec-This procedure describes the steps nccessnry to calibrate the area radiation monitors with TA-62 'detectors. Thc Committee recommended approval of tliis proc<<dure.
'.75-620 PT-14 Circiilntin ~ Water Pumis-lli li Hater Tri 3 Lo ic PCN 75-1040. J. Straight presented Lhis procediire change to incorp-orate computer print out vcrificatioll. The Committee recommend-ed disapproval o'f this request, ns it was prcvious1y done, 126-
Annual Rcport t/l.i oi nil procedure changes: (Continued) I/1//a tu'I'//Jl//a Inc lu'.I ivc ~
PORC ITl'.H NIIHIIi'.R: Di:.HCR J.P1 TON 75-621 H-55.2 Maintenance Removal or Re air of. Reactor Ilcad Control Rod Drive Cables and Assemblies PCN 75-1152. J. Straigltt:
presented this new procedure. This procedure is to provide thc guidelines for thc maintenance of Reactor llcad Control Rod drive power feed cables and assemblies. The Committee recommended approval of this procedure.75-625 RF-8.3 Core Loadin Periodic H ui ment Status Check PCN 75-815. J. Straight presented this procedure change. Zt re-quested:
Steps 5.11 and 5.8.3 to read:
5.11 Refueling Communications:
Voice communications have been established between the Control Room and manipulator crane in containmcnt whenever core geometcry is being changed."
5.8.3 Refculing surface falls running (as needed)
The Committee recommended approval of this chango.75-626 RF-9.9 Control Rod l)rive Shaft Unlatchin Tool 0 cratin ~
, Ins Cruet ion PCN 75-.817 75-8/66. J. Straight presented thc following procedure changes. They requested:
PCN 75-817 Add a sign off blocl't thc cnd of the procedure as follows:
.Date Completed:
Shift Foreman Date: Nuclear Lpng i>>ccr or A1 t.
PCN 75-846 Add sign off lines fur initial conditions Add signiture block to and for procedure Thc Committee recommended approval of these changes.75-629. Fuel hsscmbl and Core Com 7onent tlo'vcmcnt Prcre nisi tea and Precautio>>s 1'CN 75-816.,1. Straight pre ented this pro'cedure change. It requc"ted (1) Step 5.1.16 to read:
I Refueling Communications: Voice communications have been established bctwccn the Control Room and the manipulator crane in containment whenever core geometry is being changed.
(2) Eliminate Step 4.3 The Committee recommended approval of these changes.
127-
Att7tunl llrporL'lI.l of all. 11rucucluru cl>>tnl,uo.'(Ccdntinuucl)
I
', I/1/'/5 tu 12/:Il/'/5 Ittc 1 us ivu I)I'.8(:It 1 I'I'ION 75-631 J. Straight presented the following procedures for review of t:hc temporary cltangcs:
M-11.12 Tsolat'ion of SafcL Tn'ection I'um for Haintc nance. or Ins ecLion I'CN 75-958.
S-3.41'oron Itcr. cle Process Si><<t'down PCN 75-1154.
S-3.4P Trans fcrrin Conrc.ntratc.s Prom Boric Acid I?va orat:or Peed 'I'anlc to Mastu I:.va 3orator I'red Tunic for 1)ruimnin I'(.'N 1068.
S-3.413 Cas Stri rr St:arttt 3 PCN 75-]063.
T-48 M)in Perclwatcr S: turn T.jncu I'CN 75-1125.75-632 PI'-33.0 Start>> Test: Pro rom PCN 75-1128 75-1129 75-1131, 73- 1133. 3. Stroi1;ht preeantad ihcea procodure chnnpac.. They Ieqoee tad:
PCN 75-1128 Change s te p 6. 6 to read "Mark step 6. 2 througl> 6. 5.4 "N/A".
PCN 75.-1129 After Step 6.7, 13anlc D was borated out to 160 steps and reactor was then placed in llot shutdown mode.
PCN 75-1131 Add new step 6.7.1 to read Return reactor initial. Increase to 3% power and take flux map. Return reactor to liot Shutdown.
The Committee reviewed the above temporary PCN's.
PCN 75-1133 Add to Step 4.2:
'Ensure that power range channel that is supplying input: to the reactivity computer is placed in the defeat mode per appropriate General Deieat procedure of CP-41, CP-42, CP-43 or CP-44 Series.
The Conmiittee reviewed thc above temporary PCN 75-1133 and reconancndcd that it 'be n>ade a permanent revision.75-633 J. Straigl>t presented ti>e following temporary change to be macle permanent.
SH 75-32 Installation of PcnutraL'ion Seals Mitl> 13isco Silicone I'nam 1'CN 75-1120.
Thc Committ:ce reviewed tl>u above PCN and rcconmtundcd tint r tl>c temporary cl>ange be made permanent.
128-
~
Annual It('.port: t/il oi- a J.l. pr(>cc(lux'e el>at>g('.tt: (Cottt'lttue(I) 1/1//a Lu i2/3I.//5 Inc luo ive POItC I,'I.'I'.II NIIHIII It: DI'.SCIt I I'I'10N 75-634 S-2.1A Pre-Start:u> l,ine-u of Reactor Coolant Pum s, PCN 75-984.
(1) Change SL(.p 5.3.14 to read:
Parts 5.1.18 through 5.1.26 must bc completed.
(2) Chang(: numbers at checkoff space also.
(3) Change Checkoff number at top of page to S-2. 1A:5 Tltc Con>mi.t:tec rccommcnded approval of thyrse changes.
75-1335 Tn>>nediatc II(>rat inn I'CN 75-1037. J. Stra ighL'rcscntcd this proccdurc change. it r<<quesLed that thc following NOTI'. should be added after Step 3.7.4.4; NOTI'.: Valves 878-A and 878-C arc normally clos(.d at power per Tech. Specs. 3.3.1.1 - g. and the breakcxs are off with control power fuses removed.
The Committee recommended approval of this chan'gc.75-636 PT-33.2 De<;i n Check Tests PCN 75-1127. J. Straight prcscnted this proccd<<rc change. lt rcquc" tcd to:
Change St(.p 4.3 to read "at or about 200 sLcps" Thc Connnittec recommended approval of t:his change.75-642 PT-22.15 Hecltanical Mani fold "I" Leakratc Test PCN 75-10S3.
J. Straight presenLed this procedure el>ange. lt: requcsL'cd Lo:
Change St:ep 6.9 to read:
Allow pressure to decay for 15 minutes Also add - psig on sign off step 6.10 The CommitL'<<e ree(nnmcnded appr(>val of Lhis chang<<..75-643 O'I'-2.3 S;> fc'uar(l Va1.vc 0 >erat'i(>n PCN 75-106'I. J. SL'raight pr<<scnL'ed thc following procedure chant;e. lt request:cd L'0 l3 1
add the following to Step 6. 5. 3 HOV 878A Safety Inject:ion Discharge to 1.oop II Ilotlet; HOV 8/8 A.
Status Light HOV 878A Open 6 IIOV 878A Closed D MOV 878C Open 13 MOV 878C Closed D Tlte Committee r(.eonnnended approv tl of this el>ange.
Annual. I(epor t II LI ol ail. Iirucccluru cliangca! ((;unt l>>uccl) (/ le /a to
~
'll/3 I / /a
~
Inc lua ivc ITI H 'OI(C NIIHIII'.I(: Dl'.SCR T IITTON 75-644 PT-2.2 Residual Ileat Removal PCN 75-106/6. J. Straight prcscnL'ed this procedure change. It requested to change:
Stop 6.3, Change. MOV 825A to HOV 852A 4
The Conmittee rcconmended approval of this change.
4 75-6/67 0-1.1C Pre-critical Tcclinical S ecification Chcclc SheeL PCN 75-1159 75-1.l.60 75-l.118 75-1119. J. S tra ight prcsentcd these procedure changes. Tl>ey requested:
PCN 75-1)60 Add the following valves to Step 3.3.3 of. PCN 75-1119 MOV 700 Valve Closed MOV 720 Valve Closed Brealcer Open Breaker Open Fuses In Fuses In MOV 701 Valve Closed HOV 721 Valve Closed Brealccr Open Breaker Open Fuses In Fuses In PCN 75-l.159 Add thc following valves to Step 3.3.2 of PCN 75-1118 MOV 896A Valve Open Breaker In Open'use:s MOV 89GB Valve Open Breaker Open Fuses In ECCS Tech Spc:cs PCN 75-1118 Add to IniLial Condition."..'he following valves are in the Open Position, Breakers Open, Control Fuses in Place.
MOV 856 Open MOV 8788 Valve Open MOV 841 Open Fuses In Breaker Open Breaker Open Breaker Open Fu"es In Fuses In EIOV 878D Valve Open MOV 865 Open Breaker Open Breaker Open Fuses In Fuses Tn
,PCN 75-1119 Add to Initial CondiLions:
The following valves are in the closed posiLion. Brealcers open, fuses in place.
878A Closed 878C Closed Breaker Open Breaker Open Fuses In Fuses In The Conm>ittce rccommendcd approval of these changes.
l.I 'i ctlil>>gi'll'I'(l)ltI t)ucct)
~
~~Alit)u')L tt<<IIvrL'l J.L ut. t) LL Prc)celt<<re C"~~
) I./ LI l'2 Li> I d/ J Ll I'.>
Inc lua iv) l)I',SCIt T I'I'lON 75-GG9 S-3.21):] Tra>>spcxri>> Natex I'rom CVCS lhit tl L'o RUST or
~
SI'ICN 75-1075. J. SLraighl: prese>>ted this procedure change.
It: reqlics t:<<d:
After Step 5.2.2, aclcl a step t:o direct op<<r:it;or to close the CVCS ta>>lc discli:lrgc valve op<<ncd in Step 5.1.4.
Thc Conunitt:ei rcconnncndcd approval of tliis cliangc.
75-G50 SC-I R;idiatio>> I',mcr <<>>c Pl:)>> P(',N 75-1097. J. St:r;lil;ht pr<<sa>>t'ad this alla>>l;a, Tile pl:l>>>>ow conforms morc closely with L'Ilc US NIIC g))idclincs. Thc Conunittcc r<<conmiciidcd app1ov;il of tliis clia>>ge.75-551 ~SC-3 Pire Emer~enc Plan PCN 75-1239. B, Snow presented this procedure change. It requested changes to comply with IE 75-04 and 75-04A reports. The Conunittcc xcconuncnded approval of these, changes.75-652 E-l.l Safet: In'cct:ion S stem Actuation. PCN 75-1161. J. Straight .
pxesented this procedure change. It requested to add the follow-ing stop 3.6:
I Upon actuation of SIS and as directed by. Control 1<corn personnel, an operator s ta tioned in the Auxiliary Build ing shall open t: he breakers fox'alves 852A and 852B. Control Room personnel shall advise the operator to do this as soom as 852A and 852B have opened. If corn)nunieations cannot be established with the Control Room, the operator in the Auxiliary Building will pcrfor)n this action - 5 minutes after SIS activation.
NOTL': ~ 5 min<<tcs vill allow sufiicient time Lor 852A and 8528 valves to at:tain pxoper position.
Tlie Commit:tce x'econunendcd approval of t:his change.
75-f>53 H-l.2, T,oss nf Coolant: Accident PCN 75-ll62 75-1163. J. St:raigl)L presented tliis proccclura cliange. It rcqucsLcd t:n add Lhc follow-s ing st cp ~) o3 lil
~
When 10; INST level is approached (NOTI;". Indicatio)i is av;iil:)l>le in Auxiliary, 13))ildi>>g l3:)sc)nc>>t:);)ncl cliiri>>g Lr.a>>sf',er to rccir.e-
<<1:)t) o>> I)l)ase, in oper;itor. stat;iona>xi li.:)ry Biiildi>>t; vill p<<t: l>rc')lier..') for. 896 i 6 I39613 b'i<<lc ll'i ans<<re Lllu v:lives 'll.c closed a>>d pull t.'lic 1>r<<nice!r:).
lf co)iun<<>>icl)tio>>s wiL'Ii Co>>Lrol ttc)o)n is>>ot ilv')il.:lhl<<, LI)is:)et:io>>
vill 1>c doiic wlie>> Lliu 81S pili))ps ill)<1 l:ha I.'lilt pl)i))ps i)live st:opt>i'(I (NOTI'.: Thi.) ill t>>) l>>ilia)it ion Lhilt Co>>t ri>1 Itoonl parsi>>>i)el i)1'l) randy Lo ci)nmic>>eu ) <<<< Ircul;)L'll)>> pl);isa Tl)a (,'o>>u>>it Lcc rcci>>iu>>al<<lail:)nt>ri>v;)1 of l.li la aha>>I,'c witl) i C).cat; i))>>i; ~
131"
l Annual l<<<port: fl 1.1 vf Ial,l. Iirocciluru cl>aul;<<tj: (Cu>>t:1>>ued) 1/1/'/z tu 12/31//5 Inc lua l.vc POItC 1TI'.H NtIHIII:.It: l)llSCIt I O'I'10N 75-658 A-2. 7 Calculnt:in Core uadrant Power Tilt PCN 75'-ll95.
J. Straight presented this procedure change to comply with Tech. Spec. Definition 1.9. The Commit:tee recommended approv-al of this change.75-659 PT-2.3 Safe unrd Valve 0 cration PCN 75-1196. J. Straight presented this procedure change to reflect HRC's attitude critical Emergency Core cooling valves. The Committee regarding recommended approval of this change.75-661 PT-6.2A N.I.H. - Intermedi,ate Ran e CIianncls Ali. nment and/or Bistnblc Ad ustmcnt l'roccdure PCN's //75-1170 //75- l171. J.
Straight presented tlsis procedure for review of thc following temporary changes:
PCN 75-1170 Steps 5.2 througl> 5.21. 10 to be marked N/A.
d PCN 75-1171 S teps 5. 2 through 5. 21. 10 to bc marked N/A.
The Committee reviewed tl>esc temporary changes.75-662 S-178 Addit:ion of 50% NaOII to the S ra Additive Tank PCN 75-1074 75-1099. J. Straigitt presented tltcse procedure changes. They request:
PCN 75-1074 N/A Steps D. 1-2-4 Change Step D-3 to Local Level Indicator (delete the word "Manway")
Change Step D-13 to Local Level Indicator (delete the word "Manway")
Change Step D-14 and D-15 to read "Truck Fill Vent Valve" The Committee reviewed this temporary change.
PCN 75-1099 procedure change requests
/'his to make this procedure more flexible for increasing NaOli concentration as to raise level in spray addition tank.
The Committee recommended approval of these changes.75-666 RSSP-1.1 Valve Interlock Verification Residual llent Removal S stem PCN 75-1035. J. Straigl>t prcscntcd this procedure change. lt requested:
Ini,tial Condit:ion 4;3
'Add tlute followi>>g: ...or plant in process of heat up witli RIIR Sy.,tcm availablc for service.
a Iirucc<luru cliangca: (Continued) l./1//z tu 12/3l.//5 Inc 1us f vc PORC ITI )'I IIIIHIIIiII; I) I;"HCI( I I'I'ION A
75-666 0-1.2 Plant From I)ot Shutdown to Stcai) I,oad FCN'S /k 75-1,164, 75-1172 75-1167 ?5-1186 75-1188 75-1190. J. Straight presented thc following procedure change. It rcqucs tcd to re-word Step 5.4.1 to read:
PCN 75-1164 Selec t the highcs t reading power range channel to the NIS re-corder and insure the power range over power recorders are in operation.
Thc Committee recommended approval of this change.
The following temporary changes werc presented for review.
They requested:
PCN 75-1172 N/A the rest of. procedure starting with Step 5.3.3 PCN 75-1167 >lark N/A the following steps:
5.3.6, 5.4.6. 1, 5.4.6; 7, 5.4.6.8, 5.4 .6.22, 5.4.6. 12, 5.4.33, 5.5.22
'PCN 75-1186 N/A the following steps:
5.59 through 5.511 5.5.12.2 through 5.5.22 PCN 75-1188 Step 5.5.7.6 Valves 4147A and 4147C are tagged. and held closed for ST-7'5-3 HSR Vent Condcnscr test. Request that these valves not be opened per 0-1.2 so that ST-75-3 may proceed PCN 75-1190 Add to step 5.5.12.6 CV-243 CV-25 CV-258 Stop 5.5.17 correct "Use 7106" by changing to U-7016.
Thc Committee reviewed t)iesc temporary changes.
r 75-669 PT-32 Reactor Tri Lo ic Test "A" or ".8" Trains PCN 75-1078.
J. Straight presented this procedure c)iange. It requested:
Steps 6.10 and 6.11 Undervoltage and Underfrequcncy trip logic cannot be generated according to existing steps.
The Committee recommended approval of this change.75-670 P-9 Precautions I.imitations an(l Sct oint. P-9 Radiation Honitorin S s tern I'CN 75-1193. J. Straight presented c)iangc. It requested: Lhis'rocedure C)iangc setpoint of "R-20 SFP IK Service )biter" from 15,000 cpm to 20,000 cpm Thc Coaimittcc rcconimcn<lcd approval of t)iis cli;ingc. 133-
~ \o )
Annual Re>>vrt ilk). vl a11>>r()ceduru cl)))))g(.0: (Conti))()Q(l) ', 1/1/75 L(> 12/:J1/75 I))c lua ivi.
1>OIC I.'I'I'.H N) )HI I)',I): I)I',SC)t )>>'I') ON 75-675 Rp-2 Reactor Refuelin Outa e 0 Qrations and Acti ities PCN 75-943 and 75-820. J. Straight Presented these Procedure changes. They requested:
PCN 75-820 Change the procedure to provide a more positive method of head alignment with guide studs.
PCN 75-943 Add a new S tep 5. 13. 1 to read:
I&C disconnect reactor head Accoustical Emmission detector.
Change Step 5.98 to read 5.98.1 Add a new step 5.98 to read I & C reconnect reactor head Accoust-ical Emmission detector.
The Committee recommended approval of these changes.
S-(c.h S~ant Rosin Paaoval To Shi c inr Cns~kc PCN75-17(iO.
J. SL'raigl) t presented this procedure change. It requc:s tcd to;
'change st(.p 3.4 -----"150 ilR/hr to a setting to permit'clearing the alarm" The Conn)ittee recommended approval of this cl)ange..75-690 PT-12. 2 ).'.inner~('Qnrv l)iese I Clenera t<>r. I.I). )'CH75- 1.252. J. 8 traigl) t prese:need Lhis procQ(l<<re chc(ngc ~ It wcls re<luested to ad(c L'0 thc NOTE after. step 6.2.4, "and 6.11 N.A ". Tl)Q Committc.c: recnnm>e>><le<1 approval of this change. Tl)is item IS COH)').)",fl'.,
75> 691 PT-33.0, Start<>3) '1'ast Prohras>r PGN75-17(i7..1. Straish(. Pra.':ontrd this taaporary shool;a Cos roviov. It roqnocto<l; "delQLQ sl:Qp 6.11, marl< N.h. on proc<<<)<<re" change sLQI> 6.12 t<) rea<l ")t a>>prowl)))at()ly 760 )1H'I'"
The Co))vllittl Q reviewed L'h).s to)lip(>rc)l. y (!I)a<<Is() ~
75- (>93 )1- r' ')
I
)is
) ) <:) <<.<:di() t() I.a)));Q CI):<<>))<'.) s', )VI'l75>- )
~
260.,)
p)'ocud<<r(; cl)a))I;Q. IL' <'.(I<<(:st(5() Lo a(l<l to st(5 6~ /'
NOT);: If ")))))1)a Qa 1 Qvo I ))ils ll0 L ) ( (I <<co>el I)) ) L' t
)s ) )lg 5
.Cl!s:
)nark steps 6>.7 tl)r.u 6. 11. N.A.
Thc: Co)n)ni,ttc.e reconr.;;Qnde(l ap)>roval of tl)is c))anl c:
8(,- ~l i.rc. )5)nerp(:>>cv Plan, )'('V/5-83?. J. St) aipht pre"())t d t) ."
'(.
~
'< <<). () c is)ages XQ<I<<QS
- ) " '
L aS thQSQ CI
) hQ Col)mliL('e<'. ) Qco)1)))1('n(le()
Qh'ln(',(5c") hav()
rs I ll disap)>r<>v()
a Q(((ly l>een i))('.01.'por() Lu(1.
1 () f L'I) >s c
"334-
It('.I)orL Ji J.l ul nil I)r()cc(l(rr(.'l)rlr)I,'('ir: (((rr)L'J))uc(l) l/l//z L'o JZ/.Jl//a '72'nnunl I)re l(rrr J,vc POltC I'I'III N I/HllI'.It:
EN-142 Level Transmitter LT-462 In.,tal.led In >lace.Of LT-461 To Cor)trol LM-463F 7c LC-400 PCH75-3.300. J. Pari presented this new procedure. This procedure is to install level transmitter LT-462 inplace of LT-461 to control LM-463F and LC-480. The Committee recommended approval of this procedure.
(9-71<) Bl:-G.l On<~BY Gl<~ Foci. Lon<3inn Cc<iuonnn An-029.
J. Btr:rifi)t p) encl)Lc(l 'W)is pr ncc'du)'c ct)atlp(.'. I'I, w<rs rcqucsL<<d Scq>>cr)cc bc rcmov(.(1 from thc tJtle, al o cvcral minor <<1):)rrgcn correct.int, tern)i.r<<)lotg. Thc Comrnitt:<<(. rccomrn(rndcd appr nval of these cI);(r)p<<s.75-725 SM75-23 In.,tallation Of Penetration Seals With 1'(isco Silicone Foam PCI'l75-1263. J. Straight present,ed this procedure change for review only. Xt requested aft,er step 5.77 to add sign-off for R G 7 E Engineer 5 Date. The Connnittee reviewed this change.75-726 0-2.1 Normal Shutdown To Hot Shutdown, PCN75-1225, and PCN75-1242.
J. Straight pre. ented these temporary changes for review; PCN75-1225 - requested steps 5.11.3. 5.21 tL 5.24 be N.A.'d.
PCN75-1242 - re(D)estcd steps 5.1.2 thru,5.12 and. 5.15 thru 5.24 bc N.A.'.
The Conunittec reviewed these ten)por xi.y changes.75-727 PT-6. 4 Excorc/T))core Hcc:)1J.br ation, V('N75-1260. J. Straight:
pre.cnt,cd this procedure charrgc. 1t requested scvcral rrrino) changes for review. 'I'hc Cormnitt.cc ) cvicwcd these changes.75-728 0-1.2 Plant; I'r pm llot. Shut(tow)) 'I'o ttt.<<:((1v Toa(1, PCN75-1;?G2, 126I),
>('::t()(l .".I,ct) 5. I).32 N.h. I'Jg. O. 1 . lh r)nl. <<t.t;(rct)<<(1 Lo any 0.1.2 I'CN75-1264 - r<<q<<cut;<<(I; (1) add Lo ut cp 5.5. I2.1 ")(rr(k<<::ur'(7 bin()I(ir)t; (IcvJ c<< i"
)'Ilr) ))I>orl v:ll VU 342' 135-
r Antul>>1 lt(.I)crt //1 l. of (>ll. I>r<>ce()ttr.'ci chtt>>gur>: (Coht i>>ucd) 1/1/75 t:u 12/:)1/75 It>c 1utt i.ve I'OltC I')'I H NIIHIII',ll: ))I'.HCI) l I'I')ON
~7" '!'A ((,'rniL. > I CI)75-.1 26)l (2) a<i<1 I,o nt;ep 5. p,i2.r". 'll>:Lit<) sut'(.')locki>>rr (I(:vice i'u>>
t>))on v(xlv<<34?6" (3) u(bl L'o "tep 5.5.32.3 "m:.Lke sure blockir)i d<!vice i>> run upon vrxlve 3427 (4) ad(] I;o "tep 5.5.1.2.4 "rr>rtke sure 1)lockirlt; (levicc i s rl>n riper> valve 3)l28 PCI'I75-3273 PCII75-1&41 PCN75-3.253. PCS)75-3.25A and P(:N75-1261 were all temporary requests for review only to facililxtc step>>
NA'd The Committee reviewed the temporary chant.es and requested approval PCI)75-1262, PCN(5-1264 and disapproved PCI)75-1259.
ni:in i nr).'UL~<<l'nni'rnrr r 'i'j,l,l, pi'~7~, Oi
~~f. Dt,rrtifrht preset>t.ed thi" ))rocedurc cl>unpe for rcvi(w.~~
lfcvet'al <'.hrxrtg~cs werc made to comply with Te<:l>ni<<tll O'I)ecificat..i'<)rts d< l'irt,ition 9. 'I'llc Cot<>mitt<>e reviewed t)>i')>:xntrc.
'(',)-7 '0 Cim< ri~ i'i'ii7~i 10<<)- I':. )3e<L).lry f)t'c>>(trit,ed I.itis I)t'rior:<l<>r'< <:ll<ttlf:<).
~

~~i l>i l J)r'()CL(litl'() wtxt I wr'i t',I.rn t;o:irl(!Or I)ot'(L(.(! iI-It. I II, t,llc Iir()L<~~

t'i fer I I)<! "II" t,s(r>k. 'I'ltc t;orr>mi t.t.<.:c rec()>a<<On(le(l:L))I>t ()val, <)f',l>i" ))roc(!<It> r<;. 7t) 7 r() I fl-4. l.Y I,:mmiry I':rni: Hr 1.r::r::n U: ini'.'immi oni. iirni n nacht iI)'illi'(i '39'(.- )3eat,ty l)x'<<;:;!>>tc<3 thi.s new proced>l>(.. T)tr. i)ut po::(! of',l>.is procedure i" to <3escrihe t,he vrll.ve 3i>>e vp l,o sot<>))1.e I;I>(. 'I:xundry I;(xnk, <>>i<1 to disc)>rxrfre it. I;o I.hc carlal (Lt'tcr a re1.(.a-c form ha>> bc(!rl pr<)>ared, uninf. <:h(!mical <lt'rxirt tank. Thc Cot<><rti.t;tcc rc-colt>men<I(!d ai)i)roval of'his procedure. 'f 5 fl>1 CP- >6)l).2, l)cin::t.:Ltr 0('A" '.3tet>>r> 0<!>>Or<xtor ),(.v< 1. C)l:<<>t>e'i 6)t", ),. )teat,t;y pt (.sent,<>d t;his l)ro<)e<lu> ch:Lt>f;(). 'I,t, l(.qtl( t>t,<<d tl>><l<<r i>>>>t.l in <.. ~ ~l"I'CN'i-I;!', t:- t iol>s ltd<< I'ollowi t>I',; p.4 OI)ct'l(tio>>t (!heck nol tr>.xl level indi cttt'i.ot> 46i,, I)l:Lcc IIC-466 1):t<'.k it>t.o l,hc At>lot>r:Lt, ic rtrod<). Oper Ll,i.ot>>> I'> i I. i t>1 5.5 0))()r ttt I(!tt>> l>la< (. t)><. I)yp<L::..: cot>t,> o3 l,(L'IC-4)IO I't'<)m rmlrtl>;L'I I.<) Atlt <)trltLl.i (r L I d<<lr.l. t'<<!() ~ 0))(.>'x(t,i()tl>> 'I tli I.it>i 3 ll(. ex i t>L3 t>t~r .': t <.'I)>> 5. 4 t.)lt'll 5. f mttk<',)lem: lrrl)>> ',i. 6) I.)ll'll p, <) ~ i )lc t ()ttltrll I I <.e t'LnL'()rl<rr><:t><I<>Ll t>I)I)t'ov't I ol l.ll('."e <r)tr(ttr,('n uw Incl.usi.vc 7h-Yiie. tnp-h6p.l. Dcl'ar>C o!'n" i io:59 Ue>>aralor !oval Chr>9>ncl. "h('>e" F'(,'H7)-13li>. !.'.. Bunchy pre-ennea I,hi.: p>'occdure cha>>re. 1C racp>o.".Ce>1 unar ,In:: Cru>Lion- a6i>i ihc following; 5.3 Opera!,.ionn place JJC-400 fcedwatcr bypa"s controller from automat,ic to manual mode. Operations initial 5.4 Operations place JJC-466, main fceedwater valve for loop "A" from automatic to manual mode. Operations Initial The existing steps 5.3 thru 5.7 make them steps 5.5 thru 5.9. The Comrnittce recommended approval. of these changes.75-743 CP-461.1 General Defeat Proccdurc "461" Steam Generator Level PCN75-3.320. E. Beatty presented. this procedure change. It requested to delete steps 5.3 and 5.4. The Committee recommended approval of this deletion. This item IS COIJPIETJ:. E. Beatty presented the following two procedures for temporary changes, for review only. 0-2.1 Normal Shutdown To Hot Shutdown PCN75-1.30l eras to facilitate steps marked N.A. 0-1.2 Plant From Hot Shutdown To Stead Load to change step 5.5.7.6; PCN75-l302.'his requested. V4147A from open to CLOSED V4147C from open to CLOSE!) The Committee reviewed these ternpoi-rrry changes. ~75 7ii A 0-1.2 Plant From Hot Shutdown to Steady Load PCN75-1327. 1326. E. Beatty presented these procedure changes for review; ~7 6-'5.4.54>> be opened leave these vaves closed 5996,4 7 4 at this time 5 except 3996. The Committee reviewed this change. PCN75-1327 requested to change step 5.5.7.6, tJre Committee reviewed this request and recommended disapproval as thi" wns previously done by the above PCN75-1326. -137-' I hnnun1 I(aport //11 oK n11 I>t'<<call<<xi cl<<i<<I,'a'.ll: (Contin<<all) 1/1//i tii I.2/31//> Illa 1lls l.va VOIlC 1.'I'I H Hill'III I'.I(: I) I'.IJCH I I'I'ION ~7-751 PT-6.4 Hxcorc Incorc Bccalibration PCN7 -1 305. E. Beatty presented this procedure chango. It rcqucstcd the following steps bc changed to read; 4,3 190 steps 6.4- approx. 175 step" 6.6- approx. 175 steps 6.8 approx. 190 steps 6.9- remove "zero" and add "a stable value" The Committee recommended approval of this change. ~7-754 0-1.1C Pre-Critical Technical S ecification Check Sheet PCN75-1323 1325. E. Beatty presecte<l this prcceeure change. PCN75-1323 requested in step 5.1.3 to change 4th item to read; "S/G primary to secondary leakage <Oel gpm" The Committee recommended approval of this change. PCN75-1325 relIuestcd the same. The Committee recommended disapproval of this PCN. ~7-7 5 PT-22.10 Mcchanica1 Manifo1d "C" Lcakrat,c Test, PCN7"-1332. E. Beatty prcscntcd tlii procedure change for review only. It was requeoted; (1) Change step 6.4 to read "allow approximately 30 minutes for temperature stabilization bc-fore continuing with tcp 6.5" (2) Change step 6.9 to read "allow prcssure decay for at least one hour" The Committee reviewed this change. Annuni l(('.p()rL'I ii oi nil pr(>co(lur(: (:libel(>k,('n: (Co>>L'lnuc(l) l i/l.//a L'o iZ/.}i//a Inc I.us kvc VOILC lTIM Nl1HI ) I'.R: l)I eICR11"I'10N '75- (56 PT-5.30 Proce.,s Instrumentation Reactor Protection Charm(.l Tri Test (Channel 3) PCN75-1322. E. J3catty prc"cntcd thc following procedure changes; under Instructions add. the following steps; 6.71 Operations place HC-480 fcedwatcr bypass controller from automatic to manual mode Operations Initial 6.72 Operations place HC-466 Main feedwater valve controller "A" loop from automatic to manual mode. Operations Initial number the existing 6.71 step 6.73 and change the number on re-maining steps accordingly until old step 6.78. Add the following instructions which will be numbered as follows 6.80 Operations verify proper indication exists on LI-462, Steam generator level. With normal indication, place HC-466 main feedwater controller "A" loop to automatic. Operations Initial 6.81 Operations place HC-480 bypass controller to position desired. Operations Initial Number the remaining steps accordingly. The Committee recommended approval of these changes.75-757 PT-5.10 Process Instrumentation Reactor Protection Channel Tri Test Channel I) PCN75-1321. E. 13eatty presented this procedure change., It was rcquc ted under Instructions to; delete steps 6.65, 6.75, 6.76. Number remaining tcps ~ accordingly. The Committee recommended approval of this change.75-758 PT-2.3 Safe e(mrd Valve 0 cration PCN75-1310 1313 1331 and 1312. E. Beatty presented these procedure changes; PCN75-1310 - re(iuested step 6.5.7, add a place to sign off after st;cp PCN75-1313 - rcqueslcd to add 'ign off line for note.",: 1 thru 0. PCN75-131.1 rc(iucstcd steps 6.1, 6.2, 6.3, G.~i, 6.5 ((ll need space" provide(l for sign ofi'i'he stops. PCN75-1312 re(iucnted to add sign off step for not;c before step 6.8 on page 11. Thc Cotmnitt;cc recommended approval of thcnc changcse Annual Report 811 of all procedure changes: (Continued) 1/1/75:-eo-i//'31/75 Inclusive PORC IY.I M NLIHIIIIL: J)ISCIt T. P7TON 7*;;, 7 7 f ~75-75 PT-16 Auxiliary Feedwater S stem Flow Check PCN75-1304. E. Beatty presented this procedure change. It was requested; 6... is to be left closed .4. ) 4 7 6... ( is to be left closed ) 4 6 The Committee recommended approval of these changes.75-760 0-3 Hot Shutdown klith Xenon Present PCN75-1306. E. Beatty presented. this procedure change. It requested step 5.1.1 change on to or, so statement reads "time of trip or shutdown" The Committee recommended approval of this change.'5-765 E-10 Failure Of S ent Fuel Pit Coolin, PCN75-726. E. Beatty presented this procedure to be eliminated, as it has 'been incorporated into E-18.1 and E-18.2. The Committee re-commended approval of this elimination.75-704 A-2.4 Calculation Of Critical Rod. Position PCN75-1347. E. Beatty presented this procedure change. This vas a revrite to clarify the procedure. The Committee recommended approval of this rewrite with ~ modificatio'ns.. ~ 75-766 .4. >> ' Beatty presented this nev procedure. This procedure provides the ~T->>'. method for calculating the Hot Xenon Free Shutdovn Margin. The Committee recommended approval of this procedure.- ~75-7'6 ZM-143 Re lacement Of Non-Controllin Alarm Bistable PCN75-13 7. E. Beatty presented. this nev procedure. This procedure is to outline repairs or replacement of Bistable used only for alarm purpose. The Committee recommended approval of this pro-cedure. This item is NOT COiilPLETE pending post-maintenance review.75-770 E. Beatty presented the folloving procedures for temporary changes for reviev only', 7 GS-21.0 Site Access Control (Securit ) II Personnel Identification, PCN75-13I3 requested to suspend section 3.5 thru 3.5.6. 0-.2.2 Plant Shutdown From Hot, Shutdown To Cold Shutdown PCN75-134 This PCN was to facilitate steps marked N.A. T-4F Restorin 1B Feedwater Pum To Service After Maintenance PCN75-1285. This PCN was to facilitate steps marked N.A. 0-2.5 Plant Shutdown From Hot Shutdown To Cold Shutdown When Condenser Steam Dum Is Unavailable PCN75-133 134 ~7- ~75-4 to delete the procedure. -140- hi>rivi>L lluport II I.L uL rr J.L 1>rr>co~lure cliniil oa: (Cr>rrt Jiiuirl) '/I//a 1iic iiio t I vc r> L//.'JL//a 1'Ol(Oil I. I'I'ION 75-770 Tlie Committee reviewed thc steps N.A.'d and rccornincndcd dioapproval of thc dclcl.ion of tlie procedure. 0-1.3D Prc-lleatu Pl.ar>t Bcr ii'ircmcnt Check I>int PCN75>>3 3Jr:I. requested to add steps 3.1.3 a" follows; "plant otutuo io ouch that,0-1.1D i" being performed in con)unction with 0-1.1C" M-37.20 Xno ection 5 Be air Of Main Stcam Isolation Valves PCN75-13J>0 and 1381 requc"tcd several temporary stcpo be added to document the modifications for review. The Committee reviewed these temporary change requests. ~7~7 PJ'-0 Reactor Tri IJrcr>kcr:r A II PCN75-3,1'(Jr. Jt: E. IJcatty pre.,cntcd thio procedure change. It requcoLcd to eliminate procedure for testing Reactor Trip Breakers A and l3. The Committee recomrncnded approvaI of thio change. This item IS COMJ I,ETE. 75-7'(6 PT-17.1 Area Radiation Monitors B-l B- PCN75-137 re-quest,ed;
1) in steps 6.2.5.5; 6.3.5.5; 6.4.5.5; 6.5.5.5; 6.6.5.5 5 eliminate (.) period after the word "indication" and add6.7.5.5 the following to each step (AS INDXCATED WITJI SELECTOR SWITCII IN CHECK=SOURCE POSITION).

2) in steps 6.0.5.5 5 6.9.5.5, eliminate (.) period after the word "LOCAL" and add the following to each step. (AS INDICATEL>
WXTII ALARJ1 SLi'TING LEFT IN "OPERATE" POSITION). The Com>nittce recommended approval of these changes.75-77B E- 8 Reactor Coolant" Leak PCN75-1316 requcotc<l to charigc stop Jr.5 to .1 g1>rn. Tlic CoirnnitLcc recornrncndcd <<pI>roval of Llri change.75-779 I",. Jar>atty J>rc"cntcrl Lhc followirig proccdurco f'r dclcLion; I'M-1 1<c ~ >I.rrcorn>.nt Of'.lot.al>3c for V(,'T Jcvcl. Conti'ol I(.'V-ll,"C EJ>l-6 A'l' >ari Ad ur;tmcnL PCN(5-1352. HM-7 Bcrnc>viii B An III," I'ower Ban c Clianncl From ".crvicc P(!N'(5-1353. IlN-IB ~B>:>>>irin> >in koi I",.n.n!: .On Bl!II Boturn OI>nok 3!nl>>o 'I'o !3 I>>o> ~l o !I67I.I ~ I OII7 i I "i'5.,'- I.'M-13 Work On An Reactor'oolant I".l.ow Jho>lulc (Onc Cliai>ncl At A Time I'CH'(5-1356. IN-l." Ilc >ru:k I n Of Prconur.incr > ra Ual.vc R ao I'CN75-1357. nntl>>1 ltc)iort (t11 oi n1). )it>>cctlttrc c)utn)',t'.rr: (Cu>>t:1>>uc~)) ill,/75 (:u 17./:IL(75 Iuc Ititl ).Vc POltC ITI H N(IHIII lt: I)I'.ll(:I t I I'I' ON 75-779 EM-16 lte ositioninrr )Iarton Fccdwater Flow Meters f.'CN75-1350. PCN75-135 EM-21 Hi,h Head Safet In ection Check Valve Installation PC)l75-'.". EM-22 Be air Of Part Lenrth Drive Conoseal I-5 And Rcilaccment Of Pres"urizcr Safet Valve Flan e Gasket PCN75-1361. EM-25 Procedure To Chan e T Protection Component TI)-405R 3 Sec. Filter PCN75-1362. &f-27 Emer enc Conver ion From Sealed Reference Lep To Onen Reference For LT-428 PCN75-1363. EM-28 Re lacement Of Power Suoal For Pressurizer Level Channel LT-426 PCN75-136)t. E4-2 'eturning lA Reheater To Normal Line-U After Inspection And Possible Re air PCN75-1365. EM-32 Secondar E.M. Procedure For Weldin Union On LAH-2084 PCN75-1366. EM-30 Re lace Beneater" In Reactor Protection Channel" PCN(5-1367. -EM-~3)tccovcr v Of Irradiation 0 eciman )3asket PCN75-1360. EM-47 Be laccmcnt Of Bein PC-402AX Located In SIA1 Hack Com iart, ment; 1 PCN(5-136i EM-40 )tc ilaccmcnt. Of Distablc PC-402A Loctttcd In Pl'ot.cct.ion Rack 132 PCN75-1370. 1%-.53 Bctrirval Of I'ot ei.,n Ob cct In Bcactot Core PCN75-1371. )JI-54 Mo<li fication To BCC Tr <<nn ort; )3<<nkct PCN75-13(2. EM-63 I'ower Barr ~e Detector Br ilrtccmcnt P('.N7'-1373. EM-7Ci ft<<nti aint; Removal I"rom T>>r)iinc Control V.'tlvc 346i2 f~ 3)t63 I'CN'f 5-137 i. EI1 8Bc-novnl. Oi'iCC Fin cr I'roni .",l.ornrc Cnn Zn "pvnl: i'ccl Pi t; )'CN'(5-131'(5. EM-10 Wc.ld ),"nd Ovcrla Of Valve.. 287 209 and 2 0 I'CH'(5-137'(. 1".M-10)t Va'.Ivc Wall )3uil<)u An Valve 053)3 PCN75-1376. S-4.1A ")3" Loundr F Ilot Shower Tank Helen c To ))inc)iar e Canal )'CN75-13'(0. Thc Committee recommcndcs. -142-' T. lt 'llAI Arrrr(rrrl It(rlr(r( t: It I.I (il: nil. Irr(>c('.(I(rrc clrnrrl,(rn: (C(>rrt;l.rr(r(.(I) 1/1/'15 t'(r 12/31.//,'i 7 llc 1(lfr I y(! I)l" (:lt I'I'l(rN 1 ~7-780 EM-2 Bc laccmcnt Of Bistable 431-8 For Pres rr e Control.ler PBV-431C PCN75-1.351. E. Beatty presented t;his procedure change. It requested; Add ign-offs for each step on Initial Condition" and Instructions. Change 1985 psig statement in 4.15.1 to 2235 psig and 1935 psig in 3.2 to new set point. The Committee recommended approval of these changes.75-781 E)4-ll5 Cleanin and Insnection Of The Containment Personnel Hatch E ualizinp Valve For The Intermediate Side PCtl75-1346. E. Beatty presented this procedure change. It requested, to change step 5.6 to read.; 5.6 Perform leak rate test on the containment personnel hatch and verify that an acceptable leakage rate exists. Results Jr Test Tech. The Convnittee recommended approval of this change. ~7'-788 T-lrlA Ali,rrrrrcnt Of Auxiliary Fcedwatcr S ."tern Prior To Power 0 eratiorr PCN75- 90. E. Beatty presented these procedure changes. PCN75-'998 request;ed step 5.)rl change V4031 to Vl(301 requested stop 5.52 remove Y-4007 OPEN ~l7'- 'l-step 5.52 add MOV in front; of 4007 add MOV 'in front of 4000 step 5.29 add MOV in front'f 3505 step 5.30 add MOV in front of 3504 Thc Corrvnittce rcconvncnded approval of these clrang(.s. 8-2.2 Prc:;nuri rcr Prc sui'c 8 S >ra Contr ol PCN75-1315. I'.. Beatty prese>>tcd thi'roccdurc change. t;o change the sct;points to reflect t;hc ncw prcssure "ct;points. lt was requc t;cd The Cormnittee recommended. approval of thi., change. This it;cm IQ COMPLETE. ~75-7 0 ll- l.. presented this procedure change. INITIAL CONDITIONS; It wa requested to add urrdcr NOTE; The gas decay tank t)iat is liner) up to receive gas must not be lined up should have'ufficient volume to receive all t,he gas to bc vented. If not, swit;ch ~ -Ai" Anrturr1 ltcport: tjl.1 rrf rr11 lrrrlcc(lure clrrrrrl',crr: (Crrrrl irrrrcrl) 1/1/'/5 t'>> 12/31/'I"> Illc1rlrlLVU -1'Ol(C 1.TI H l4INllI:lt: Dl ! >Cll l l'!' Of4 ~75-7 l S 4.5 Sluicinr Mastc Condensate Polishin . Demineralixcr S ent Resin To Shi in Ca..k PCll75-1.223. E. Beatty prc. ent;ed this procedure change. It requc ted. to change tep 3.8 to read; "the cas)c line " not "lincsr'hc Committee recommended approval of this change. ~ 75572 S-8A Comnonent Coolinr, Mater System Startu And Normal 0 cration Valve hli nment. PCN75-1250. E. Beatty presented this procedure change. Xt requested step 5.1.12 should read "V-lr617B closed". The Committee recommended approval of this change. ~75-7 3 S-16 Safet Xn ection S stem PCN75-130 . E. Beatty presented thi" procedure change. It requested; Step 3;4 change 351 to <65fs Step 5.lr - change Value to Valve Step 5.8 - change 1800 to 2000 The Committee recorrrmended approval of thi" change. ~75 7 li S-16A Safety Xn ection System Alir.;nment PCN75-10 3. E. Bcatt;y present;ed thi procedure c)range. It was rcquc"ted; Step 5.1.27 delete fronr tcp thc following word" - - and rcmove fuses siss sorus Fuses Out 75-705 PT-6.4 Hxcore/Incorc Recalibrrition PCN75-13 l. H. Beatty presented t,hi procedure change. This change wa.s to supply proper rod po"ition a" required by reactor load and axial thi" tilt. limit;ation". The Committee recommended approval of ~ changes 75 800- M-11.5B'a or Mccha>>ical Ins ection Of Auxiliary Motor Driven Feed Pum 1B PCN75-1.344. H. Heatt,y pre.errted t.iris proccdur c change. It requested t,o clrange step 5.6.3 t;o read; "tiglrt;cn pump casing stu<ls until secure; making a final pass to ensure all st;uds arc tigtrt" Thc Cornmitt<<e ) cconnncn(lcd approval of t,his c)ran~,'c. -144- AnnunJ. 1<<.1>>ir t //I.l, >>I: nI,i I r~ en~1<<rc cli>>>>I;cn: ((",i >>1;Ji>>i<<~l) I,/I//'i I:>> 12/3 I./'/a J nc 1>>s J.vc I'01((l. 7.'I'I II Nl It I II I I<: I) I lII(lII I I'I' () N 75-803 SM75-10.1 Installation Of Groundin~ Cable For Auxiliar I S. Spcctor presented this new procedure. This procedure describes the steps for installing a new section of grounding cable for grounding of the new auxiliary building addition and to allow removal of section of existing grounding cables temporarily for caisson installation. The Committee recommended approval of this procedure. 80 1> B. Snow presented the following temporary procedure changes for review only; M-37.16A Ins ection 8 Maintenance of Manual Onerated Grinnel Dia hra Valves PCN75-1396 requested steps 5.5.1 through 5.6 be marked N.A. PT-2.1 Safet In ection S stem Monthl Surveillance Re uirement PCN75-1303, requested step .2 be marked N.A. RSSP-7.2 Calibration Procedure At Power T Avera e and Delta T S an Ad ustment PCN75-1421. Request,cd under Initial Conditions step 5.1 replace "or slightly" with >>STEADY STATE" also step 5.3 replace "secured" with "as directed by clicmist". The Committee reviewed these changes. ~7-807 M-37.2 Maintenance Of Pressurizer Relief Guard Valves PCN75-10 4 ~ B. Snow presented this procedure change. The Committee recommended disapproval of this PCN as the procedure was updated prior to this PCN request. ~75-80 0-1.2 'lant From Hot Shutdown To Stead Load PCN75-13 2. B. Snow presented this procedure change. valves 4007 & 4008 from open to It requested step 5.4.54 to change CLOSED. The Committee recommended approval of this change. -145- Annua1 l<<'.)~or(: //j I ill: nl I (it<>ccrlurc chnn~,co; (C~ii<Llnuc~l} 1./j./'/'i hi 1 d/3l./'/.'i ] nc 1<<:; j.vc )'OH(l III H NllHItl R: l)l"('I( lq'()g 1 P M-37.16lI Ins ection 0 Maintenance Of Cha man-Crane Pressure Seal Tiltin Disc Check Valve For Valve PCN75-1415. S. Spector presented this new procedure. This procedure is to describe the steps necessary to disassemble, inspect and repair and reassemble these valves. The Committee recommended approval oi this procedure. M-11.5H Removin The 1A Motor Driven Auxiliar Feed Pum From Service For Maintenance PCN75-1 14. S. Spector presented, this new procedure. This procedure is to describe the steps necessary to remove the 1A motor driven feed. pump and associated valves. The Committee recommended approval of this procedure. 75- 812 M-llJ Returnin The 1A Motor Driven Auxiliar Feed Mater Pum To Service After Maintenance PCN75-1423. S. Spector presented this new procedure. This procedure is to describe the step to be used to restore the 1A motor driven auxiliary feed pump to service after it has been held for maintenance. The Committee recommended approval of this procedure. M-37.16J Xns ection And Maintenance Of The Motor Driven Auxiliar Feedwater Puma Recirculation Control Valve PCN75-1422. S. Spector presented this new procedure. This procedure describes ~ the steps necessary'to disassemble, perform maintenance and re-assemble Valve 4304 or 4310. The Committee recommended approval oi this procedure. 't5-G>5 M-37.20 Xns ection Re air Of Main Steam Xsolation Valves PCN75-103 ~7'- ll. 8 ~7'->> valve internals and main 5.2.8 inspect teom header internals as necessary for cleanliness. Q.C. Xnspcctor PCN75-1398 - requested to add words at end of item 5.2.14 as follows; -and that the valve strokes to its proper full open position. The Coimnmittcc recommended approval of these changes. -146- v/.c t ufo , c)1< F I hn<u<nl llcliorL'ill. <il! nil l>r<ic(!<1(!rc ch<<<il',<.<<; (C<i<<LI<<<<<<. l) i./l./%> 'I:>c 1(<!< J vc iyOIC I.TI H N l)IIIII'.ll : Dl',y(:II l Il'lQN '~HI )F) N-hll ')tvvt I I.I:uu u Ilntl IL)lt)l.r.rutnr:r. Fll'l rl)'rut1lc . n)tl)l)r t".: << I'CNF'i" I'!').I F litt)'i ~ h. I'nou Ncu::urtt ut.l Lha:Lo I))'ocr:tlu)'c chil)ICc<< ..I.L )nu; I'utlttr:"Lctl'ly<lraulic l>nul>b< r fr.isL'al;<. M-i<0:4 - H('.Il<ovc aGL(uric (") on Fll-05 (<n<l MS-22, cliarigc FM-04 Model t,o read llSSA-PO Siign Off on Pago M-40:2 Add. line for PORC Bcvicw Date k PCN75-1405-- requested another v((lve number be added. The Committcc rccommcndcd approval of thi" change.78-818 B. Snow presented. the following procedures for changes. It is requested the procedures be made applicable for A B Motor Driven IF Auxiliary Feed Pumps, For also to add a NOTE: "If installing new rotating impeller Pump, shaft assembly mark associated steps H.A." M-ll. B Ma or Mechanical Ins ection Of The Auxiliar Feed Pum PCN75-1416. M-11.5C Minor Mechanical Ins ection Of Auxiliar Motor Driven Feed Pum PCN75-1417. The Committee recommended approva1 of these changes. SC-3 Fire Emerpenc Plan PCN75-1412; B. Snow presented this proce-dure change. There were severa1 word changes rcqucstcd. to reflect actual policy and clarificution. The Committcc ~ ecommendcd approval of these changes. 7 >-821 h-2v 3 Maxim<<<<< ling t Powe> I'CN75-1411 ..B. Snow prose>>ted tlii:: proce(lure chu>>gc. 'I'licse cliangcn werc I;o "upply daL<<<<h(.cL, curve:; and Lablcs for calo!.imctric wil;li procc<lu! e. 'I'hc Co<<uniLLee reco!<<<<<cade> chang<<. 7 >-Al~.< LI-IIFI~III)II'F))il It: ',It)I)I)l))'t'it)II; III'IllrlvnI III))I llc In::I.:)U nl. Inn I'i o< e<l<<! < TI<l i Lc<'<<-l'al.<.r'o<<PCII75- ll!<)1. l3. ll>>vw lii <<ci! I.<:<l ~ < I.h!!i fi<'0<.'<!d<<<'<! ch>><<I',c IL'c(lu<!>>Lull L'v reillov<. (ll<irgcn tilt<;r<<0>>) 1 l'r<)<<< Lh( LiLlc <Ll>>o. l,o (@i>>> "tcp 3.4, "NuLLI'y (L.C. Dcl)L. ". 'I'hr Co))u))LLI.cu r).c)>))v))uF)rl):)IF )pl)rt)vol ol'h:i<<(.h<uw((.. <<147" J'e<. l Attnut)1 Rcport //11 of n11 procedure c})()nl;cs: (Co))ti)tuc(I) 1/1/75 Lo 12/31/75 Inclusive }701(C ITI'.H NIIMIIIlt t ))I 8(!O'I l'I'I'ON 7J-JJ'J< M-I)0.2 H (I) t<))l'j,(: <Ir))lb)J(:t'lr) I I, Tn>> >(!cLiot) I>> }I(.'(<ir)'o('.(.'(l))t(. ~ ~ l)r r cn Iial,c)"oor) 3 I'(.'W'-) ~ ~ (a l?(J. . 13. Snow >r(.nu) L(:> }loin:;tal1 at}on Ol'VCH R(;lief Valv() //20 PCN75-7'7. B. Snow prc"cntcd thi" procedure change. It rc(puca%cd to t(()d
Reference:

2.2 RSSP-12 Tcstin ~ Of Prirnat l'>> Secondary R<.lief Valve.". On Test, Star)d.
The Committee recommended, approval of this change.75-026 33-11.5A Romovin<< The 1B Motor Driven Auxilier Feed Fumn From Service For Maintenance PCH75-1))13. B. Snow presented this procedure change. It was requested to change purpose to; L.l "To describe the steps necessary to remove the 1B motor driven feed pump and. associated valves from service for maintenance" 5.() delete the word "Locked" Add signoffs Maintenance Encinecr PORC Review Date The Comtnittee'recommended approval of this change.
7 5-J327 M-55.1 Rc air Or Renlaccmcnt Of T e II-2 Breaker Ccontrol Switches PCN75- 25. 13. Snow presented thc fol.lowing proccd)tr c change. It ) e(1ucsl;ed to change sign off from "Maintenance Foreman" to Shift; )'orcman. The Cotnmittce recomtncndcd approval of this change. This item IS COMPLLVI,".
75-0'>0 l}-50.3 I" olation Of //12 Trar)s form('.r I'CN75-1105. B. Snow I)rc:,cnLcd this p)'occ<lurc cl!ur)gc. IL wain rc())tosLcd t,o add 'Lo NO'I')." aJ'L((r 5.7; NO'J'I'lt Relay::ct I i)tgs slu(ll t)ot be cl)a>>gcd without apl)>>oval.
oi))c Mal>>'I,on(<>>(.c Pt)L;Jt)ccr T})c ConnnitLoc !'cconnnon(lcd nl)pr ovt('l. ol'.l)Jn c}tar)go.
14-40~> 1!:()1(<I;.Int) OJ'3un 17 I'CN75-).01}). B. II))ow I)'r'c>>util,cd L'))it: l)t o<.(tdttr( cl):u)gc. 1L t(.()uc>>L<:d I'o c))(<t)(F(! "Lcp 5.6.1 I,o rc(!d I "OJ)ct) ttt)(l ))ol(l tn(Lit) it)comit)(r bt'cak('r ot) i)us .},7 on MCC l(I, ))()>>itiot) ))M"
'J'hc Corn)nit.I'cc rccommc)tdcd approval o'f t})in c))r)t)gc.
-148-
'4 I\
(r I'
<<r) 1 II('.17(rrt ll I. I 1 1 Ilr'( (.'('.(I((re el)>>r(I',(!r(! (C(>>r(. lr)<<(:(I) I / I./7'I ('<>e I.<<>> I v(.
((l 7.'I'I H HIII I(: I)l (:(:I( I I I I(IN
-031 M-37.13 ~It<: 'I>>r:.inr'~Or Rrl'~n.'.11r>'l>>l>le> 'e'>1 7>> P>>>'r'e~&>>~>~y And I.,'xkr(u(>>t V>>I vc>> I'CII7>-70( >. 15. Sr(ow presented this l)roec(Ivrc change. It rc(I>>cstcd to ad(f I;o tk(c purpose:
"or scat adjustmcnt. it If is only nccc"sary to adjust the seats I'kren non-applicablc steps may be markeQ N/A" Add to title: Replacing "or adjusting rubber scat" The Committee recommended approval of this change.75-033 - B. Snow present,ed the following procedures for change. It was requested the following note be adQed to each of these procedures; NOTE: Belay setting" shall not be changed without approval of the maintenance Engineer M-48.2 Isolation Of Bus 14 PCI'I75-1110.
M-48.4 Isolation Of Bus 16 PCN75-1113.
M-48.5 Isolation Of Bus 17 PCN75-1109.
M-40.6 I olation Of Bu .1.8 PCN75-1100..
M-60.5 1A Ernerpencv Diesel Protective Relay Ca3ibrr(tion 8 Tri Test, I'CN75-1112, requested to add Precaution 4.2:
"Relay settings "I(all not be changed without approv((l of tkrc mairrtcnancc en(;ir!ccr>>
M-60.6 10 1',>>>ue>!e>>e Dir" ol 1'r oLeol.ivu Ilel(> 0: 1i1>>> l ir>Re>>n>i .'l i~>>
Test PCN75-111..".. r c(1!rested sync as above.
Tire Corrvnittcc r(!conrmcrr(led approval of tlris charrgc.73-833 SM75-27.1. Installation Of A Ke Switch On The D.C. Power 1"or MOV8 6 A & B PCN75-lk(31.. B. Snow pr'esent,cd t,hi.s new procedure.
This procedure is to de cribe the step., necessary to in-"tall a key switch on the D.C. power and verify proper isolation by operation of the switch for valves 096A and B to reduce thc probability of a passive failure of the valves. The Committee recommended approval of thi" procedure.73-836 .
SM75-33.1 Installation Of A Kcv ..witch On The D.C. Power 1'or ov 0 52A and 17 PCN75-1.433. C' B. ~no!r pr csented tkrxs new procedure.
Tkhis procedure is to describe the steps necessary to switch on the D.C. power and verify proper isolation of sa(nc bykcy i((stall a operating t.he switch for valve." 052A and B to reduce the probability of a passive failure of the valves. The Committee recommended approval of thi procedure.
-149-
>>>llli> t('.1>(>1'1; II J. J. (> f. nI J. 1>x(>cc(1>>xc cJ>>>r>I',(.'n! (C(>(rl: L>>(>c(l) I /I /! ',> t'(> L2 I:I J.I7 ">
1(rc Lu': I vc I'OltC I'I'I M Hill ll)1'.ll: J>I'-'lClt1 1'1'1ON
'<)-A.;I S-l3A RIIH Syst,cm Lincur> For Saf'ct;v Xrr cct,ion PCN75-ll>J>7.
B. Snow pr cse>>t;ed this procedure el>antre. it rc<Luest;e<t; St;cp 5.2.l aft;cr HV deluge Valve add 852A Key Switch OFF'OY 852A closed St.ep 5.2.1 after RV deluf,e Valve MOV 052B closed a<b1 852B Kcy Switclr OFF TI>e Commit,t,ce rccor>m>c>>ded approval of thi.s ch;(>>g~c.
A-16A ."afelv ln, .(:Lion liv.'.Lc<<< i!i.in(((<(r(IL t't:)17')-:t)<AA. A. Al(<lw pro::onl;a<l thi:: p(occdurw ahanf(.. It. ro(tue:;La(! cfear; 5.1.2.20 ((dd; V896A Kcy Swit,ch after 5.1.2.2l add; f)t'f'896B Kcy Swi t;< h Of'I'he Co>>>>>>itt;cc rccomm(>><<lcd <I>>hoval of tl>is change.
0 1.1G, prr-Ori air (I'1'<< t~nioa1.'l'acii'ie (t ioa <'heck ."1(<< ttr t't'.ll'<')-.t.)<!<<). D. 'n<(w pra.u nL<:u Lh.i:: t(r<(<;(:<tui w chant;(.. ii.
1'o(illa:(Loll 3.4, 'Lcp MOV 09&A Pc B nhoul(l rc>rd as follows:
MOVA<$6n Open'reukor Olaoc<1. I"(rses I>> K<y llwi I..I>
cal<cr Cio::c(l Kcy l>witch <jf'f On'OV0~)(F13 Open 13r I u"<>( Xr>
Tire Com>>>ittcc rcco>r~cndcd approv;Ll. of this el>a>>fc wit.h >>>odificat,i or>s.
I A-A)(O H-l.2 I o( .. Of Coolar>t; Accident I'CW75-1450 ~ B. S>>ow present<<d this proccdur c chant.c. 3:t re<?uested to add NOTI". aft,er tep 3.1.4; NOTE: To close MOV 852A or B operat;or must place D.C. closir>gr power hold switch labeled 852A or B "Key Switch" in the ON positio>>.
Add NOTE after 0968 of step 4.3.1.2; NOTI.": To close 096A or B, the D.C. power hold switch labeled 096A or B "Key Switch" mu..t, be placed in the OPFAJ position.
Add,Note before step 4.4.5,NOTE:To cxerci.>>e valve 052A or B opcrat,or must place D.C. closing power hold switch labeled. 052A or B, "Key Switc)r" in the OH position.
The Committee recommended approval of these changes with mo<tificctiorr"-.
-150-
. Ly

~j .;...'- ~

Arrrr!rnL lt<.ir<)rL PLL <rf nLL Irr<rc<<. 1<<re clrrrr!I;err.'(C<r>>t:lrr!r<<: I) L/L!'l5 t<<LRI3LI'I5 Tnc Lrr:r I.ve I'ORC LYIM Nllllllllil: I)llii('ll11 "I'(rN 78-84' E-l.l Safct ln ection System Actu<<tion PCN75-1 51. B. Snow presented this procedure change. Xt requested to change step 3.6 t 0 read 2 3.6 - Upon actuation of STS and opening of Valves 852A and 052B assure both valves have opened and the D.C.. closing hold switch labeled "052A Key Switch" and. "8529 Key Switch" arc still in thc OFl" position.
Thc Comnrittee recommended approval of this u
change.
A-2.4. 2 Calculation Of Cold Shutdowrr Boron Concentration cedure provide" the method for calculating the Cold Shut<}own Boron Concentration. The Committee recommended approval of this pro-cedure. This item XS COILIPLETE.
~75- 8 2 M-40.4 Visual Leakar e Ins ection Of Hi! h Energy Pi in!v PCN75-1408.
M. Backus presented this new procedure. The purpose of this pro-cedure is to outline a method for visual leakage inspection of the high energy piping outside containment. The Committ;ee recommended approval of this procedure.
V. Backus presented these procedure for deletions; ST-71-3 Test On Cut%in A Diesel Gencratinr, Unit Free From S stem Vhen Carrvinp; Auxiliary Load PCN75-1175.
ST-72-2 Xenon Oscillation Test PCN75-1176.
ST-77-3 Part Len,th Rod Removal Test .- Safet Evaluation PCN75-1177.
ST-73-3 S ecial Load Test For 40 Ton Auxiliar Buildin Overhead Crane'ain ilook PCH75-1176.
S'i'-73-5 Xenon Transient Test PCN75-117 ST- 3-6 Ifcasurc Radiation Level Of Thimble Plu ..in Irrscrt PCN75-1180.
ST-73-10 To Tent I'ntc ritv Of Control Air 8 stern To Stcrrrn Tine Power Relief V<<Ive>s PCN75-1101.
Pt'-74-1 Rc<<c tor (.'or e l)cc<<Tc".t PCN75-1182.
GT-74-Il Mov<rablo I)ct,cctor Rcn 7on::c Tc.-.:t PCN75-1104.
'i'Irc CormniLt,<re rccomrnc>>dud r<pprov<<l qf the c <}el<<i.iorrs.
5 Arlr M-)1.5D Tlt<.<<t.rlc<<1 In:: rccL}<err nf lB A>>xilir<rv M<iL<rr l)riv< r Porn 7. I.N75-1 r27. M. l3<<cI<us pr'c::cr!Le(I Llrln }rr'<r<rc<trrr'<: <<lrr<r w<<<<.r rc<}rrrst<)<} Lo cir<<rrt;c the tiL:Ic t.o rcr<<};
"Electr'i.c<<l lrr.rpcctionrr oi'ire MoLor Drlvcrr Auxl.li<<ry li'<reI (> N(l'I'I". ui:Lav 1>u:Lvuaaiu>>a. 'I'l>a (.'ua>>>>lLLuu v~ao<>min< u(vuL~
-'7 %1
I'Ol<C 1'I'I H i)i'.!1(:ii LL'TLON NLLHILNIL:
rr
~
I~->lo.i 'J.-.rilut Loll 0! 11n "A Lhr."~o:: L'I!Lr(~ LLLyi N pro!:cnLcrl LI)i>> proccrlr)re r crine"ter! lo ndd H0'1'i', uitu,.
5.22 to rcud; NO'L'I'". Lro'Luy -ut!ind.,"..)!urll nol; be chunic,ui I;ho.ul, uirproval oi'hc Lhrintcnunce 1"n! inecr The Comrnittec recommended approval of thiis chungc.
~7~- '~> I"M-I)5 Rc air Of Blcrrd 8 stem Valve FCV-llOC I'CN75-1002.
M. Buckus pre"ent;cd this procedure change. It; wu" requesLed the procedure be changed from Efl-45 to M-37. The Committee recommended approval of this change.
J >-0'~ RSHP-2.7 Safct'n ection Se uence Timers Train A & B PCII75-960.
W. Backus p?'esented thi" procedure change. It requested step 6.21.5 be changed to read 52/CF1C, steps 6.26.6 should read Containmcnt Fan lC. The Committee recommended approval of this change.
~75- RSSP-10.1 Conditions For Main Steam Srfetv Valve Test PCII75-1134.
~c U. Backus present,ed this procedure change. It was requested step 6.1 be changed to read;
".Reduce T avg to about 543 F by use of atmosphere steam relief, SjG blowdown rate, or by condenser steam dump" The Committee recon)mended approval of this el)ange.
~7a- o RF- . , Control Rod Drive Shaft, Llnlatchin; Tool OncraLin ~ Instruction PCN75-1280. 11I. Backrrs pre..ented t,his procedure change. It reqrrc::ted to add to data sheet, pages 7-10; Date Cornpletcd:
Completed By:
Thc Cornmittcc r ceo))unended upprov;rl of I;iris chango.
75-A(i0 M. II>>ckrr>> I)).r!st!))Lcd L'Iri.:r pr v<'tv)iur'c r:hrrr)gr!..ll r'utlrrcr)Lc)I .i>> nl,cp,l.4 t,o clrur:gc secor)rl -cnLcrrcc t,o rcurI; "euoh Lduu:c ru.".1:r<<uiuu rrhoniri itc -"
'I'l)c Commi LLcc rccorn)rrr>>)lcd ui) prov))1 of Ll)i: clurrrgi!.
<.1>ot't: .L <<f. >>11. 1>r<>c('.(1<<re cl)<t>>t,t.rr: ((,'<>>>L'l>>)re<i) L/I./'/.'> t <> 12/:31./'/.'i 1 tic1<<r: 1 vc 1'Olt(l 1'1'1 M H U I I II Ill I: l)l">(lit I"I'l()ll 1
BY B linn( I or Bnl'nu'I,;I~t> 'nl:lr~uO n.'rnl lr>n:: hnrl ljnl,ln j I. Ir;,".
~
1'(ltt75-3'!Hl . M. D;icl:u>> 1>r'(>i:0>>t,<.<'1 t.lii>> l>t'0(:c<tu)'<<. :1)a>>gc. Xt, wtis r(.<lu(:>>t.c(t stc>> 5.59 bc cliangc<l t,o rc(i<1
"(sunlit.'y Coiit,ro3.. Xn:;>>ection>>rcc3onurc rclorul vcrificat;ion i,ri accordaricc will> ((CL1'-2" Tlic Committee rcc:orruncn<lcQ a>>prov:i3. ol'li'i>> cliruigc.
M-3.l.5F Instrument And Control Xns ection Of Thc Motor Driven Auxiliary Feed. Pumps, For Pump, PCH75-it)25. M. Backus presented this procedure change. Xt requested to add to tlie data sheets, pages 5-10; Date Completed:
Completed By:
The Committee recommended approval of this change.
75- t16tt M-11.5F Instrument And Control Ins ection Of The Motor Driven Auxiliarv Feecl Pu)n s For Pump, PCN75-l 25.
M-ll. R ittcrs 1 Xns c.ction Of Motor Driven Auxiliar Feed Pu)ncs M. Backus presented. these two proceclures for changes. Xt was requested tlie tit;les be changed, also to have Sl)ift Foreman and PORC Review D etc addcQ to tlic sign-off s. Tlie Conunittcc rcconuncnded approval of these cha>>ges wit h iliodiflcat.ioi)G ~
ltF-B. i Ftt(l 8 C<)t<. (,'<>)>>>0>>c>>t, Mov<)nct)t; 1'n 'i'lic 0 >< nl. 1"u()l Pi.t, 1'(;N7'.>-1430. H. 13<icktin pr <<>>crit.()d t.lii>> piocc<lut(. cli:ingc. il. i()-
<it)cnt'cd t'l)<. cx.ist.it)g u>>p<.)i(1 ix A bc )'(.)ttovt.d tu)(l i'cpl:roc<i. wLt.l) ri nc'w onc ~ iil >>0 t 0 tit f t Otcl) loc\1 biol) >>lie,'ct 0 n>pci) 1"il<'3. Pi t'or t i))i ol'it)<it.iorl Oi)ly. Tltc Cur)unit t(<) rcco)mn(ndcd appi ov:il. of 1:Ii'L:;
('.1) till(.;c n f5- f)()(i 0-'> ~ 1,0:t<1 1>>>> )'<'.)l"0>> p(.'N75-1 432. l<. lttt<ikt)s prc.>>crit,<!<1 t.lii>>
proc<<: ltir<<cl>>tr)g<'.. 3.l. rc<1uc" teil; l) Cl)t>>ttrc stol> 5.7.1 to r ctt(l: Il' lie. <(v('1'<lire tixiril. l'.Iitx
t <<ttci <1( viat.o:. ft'c in i l;'>> t.ttt't.;0 1')ii)ul, i'(.<lite<< i'c<ict.o)'ow( r t.o Io:t>> t;1): ~ i JOAN 01 t'rttec<l pow<.')',
2) A<l(1 to 5.7.2 ta 5.0.3, if t.lir. couil>tit;cr'>> oiil. <>f . <<rvi(.c.

3) 1,'l.imi>><il,c L't'o)n rite>> 5.0.2 - ci t t)ct'tnrnc<li<),t ()3y ttik(i;i 3)ttrt.i(tl flux nnip p(ir rt(l)ninL>>t,r at,ivc pt oc:<<. lui 0 A-2.30.1 or A-P.10.2 or ---.
Thc Cornn)it t.o<) t'ccotnnt<'ri(l(.(1 ttt>1>t'ovr)'.L of' II()"0 cllrltlf,c>>. -153- <Ig r%s w <> -- ~ il. Itcliort; ill.l. >>f nll. lir>>cciliirc ehn>>l;c>>'. (C~>>ill>>>>cd) i./l.l'I'i t>> L2I:tl./'t'i iiic his l,vc l)t",l(;It I l'I'ON "II" Ierl<s Iin<! >I !~airs".s (O<<t::><le Co<<(min<><:nt) 11>-137, PCNY5-'.I.27(>. >f. .",loom Backus prose>>t'cd thin procedure ct>>>>itic. 'l, req>>outed;
1) Add t,o precautions; 4.5 Rien weld repairs, grinding or cutting are made on piping O.D., provide fire protect;ion devices such as fire resistant blankets in the area of repairs.

2) Md step 5,li.l; Q. C. Cleanliness Inspection of piping ID in area of weld repairs (If no repairs are made on the ID of piping welds, this step may be marked H.A.) Q.C. Inspector The Committee recommended approval of these changes.
75- t jiA EM-140, Re lacement Of Bod Drive Housinr Ca, PCN75-l274. M. Backus presented this procedure chang, . Xt was requested; add new rccaution 4.4 -,Provide fire protective device.. such as fire resistant, blanket when grinding and welding .3 << utilizing fire resist,a>>t blanket or equivalent in, the work area to retain nictal chip. or grinding. Tlic Coiimiittec rcconnneni3cd approval of these cimngcn. ~(i" Q( I'>I-lOB~ llo <<lr Ol' < nl< On I,ot<lo<n< 'I'o Bcn< Lor ( col:n<t I'l < M. l3iicli>>s prc!>i!>>t,clt tti.l'> procciiiii'c cl>>nitro. 3 t w!>>: rcquc tut; hdd proc>>>>t,;ion 4.2 3'roviitc>>ilcquat,c fire lii'otcct.ivc (lcv.ice>> f !iuc)i >>s> iro rot,ard>>>>t til>>>>ki t,n, iin >>ceo>>>>iii'1>', when grinding, cul,l,.iiit: >>>>i3 wc1,it i.iit;,. Adit n.w: t;cp 5.7.1 - C:l.oaii gciicinl. >>ro>> ol'lldct>>'.i.>> t'i'om wtil.it.i>>t.; aiid ter;i iid i.rit; Tlio Coinini t.t.cc. rcconnni >>it>>d>>till>>(iviil ol'.lio",c cl>>uitr>o>>>. I i Annun1 Itcl))))'t I/11 )>C nl,l, I)rotc)I))rc cl)))))I',)'.t): (C))))tl))))c)I) 1/I,//',i I:ii 1.2/3I./'/'i J )ic 1<<:) I. vc I'(Iit(l 1'I'I H NI I I I IIIIII) I)I S(;lt I I'I' ()N l)iu )oct.lo)i ~(t .i)t,rill ltc I i.r I')) 1 vo IVI'( I'(,'ll'('p-9:74. >I. II))ci'.u Ii)'cuc)) t.)'.SI'-1:? "Tcstir)g of Pri)r))n)'y on<I Secondary I<clicf Valves on Test, Stan)t". Change Procedure t;o M aerie" (M-3'() The Com)))itl;cc rcco))U))ended approv'~l of thc'c cliangcn.75-872 RSSP-2.1 Safet Xn, ection Functional Test PCtI75- 23 PCII75-8'(8. M. Backus presented thi" procedure change. PCN75-923 was to facilitate steps N.A.'d. PCN75-878 This was disapproved as changes were previously done The Committee reviewed PCN75-923 and recommended disapproval of PCN75-878. ~7-8 'I EM-144 Power Su 1 PS-1 in 1AC Rod Control Power Cabinet. PCIII75-1456. C. Edgar presented this new procedure. This procedure is-to describe the operation necessary to check and/or replace Power Supply PS-1 in the 1AC Rod Control Power Cabinet. The Committee recommended approval of this procedure.75-875 E. Beatty prcscntcd the following temporary;.roccdurc chant;cs for review only. All PCN's were writtem to facilitate steps N.A. 'd. 0-1.2 Plant Prom llot Shutdown to Stea)l T.ond, PCN 75-.1472 0-2.] Normal Sliutdown to llot.Shutdown PCN 75-)474. ST-75.4 Turbine Plant St:;irt-u i Pro.r:)m Pollowin; Plant Tri of 09.'iG llours on 6/l7/75 )!CN 75- I473. 1"l'-2.3 Snf) u;)r<l V;)lvc 0 ir:itiou I'CN 75-.I464. PT-33.0 St))rt<<) Ti st Pro rnm, 75-1410. i'. PCN RF 5 II I'I II'N I 5 IIi ~ I3.'.- RIIO I R CO1(". C()ill I(llli'ii L'ilV'.liiUllI' Ii Ill I I L VII0 I ~ ~ -155" ~ t'S I Ao>>ua). II<'1>ort; I/). I, <>E>> l I, 1>r(>c<<<l>>rc cl>>>>>I,<>><: (C(>>>L I.>>>><<: I) I./I./7'i I:<> l2/3)./'I'i J>>c l. >> < ),v< n )'0110 I.'I'I Il NIIIIIII:,It: I) I'.! i('lt I I'I' I) N 75-876 Stl-/.'>-33. I l>>st<<1 i>>I..i(>>> <> E A Ic'~>wi tch 0>> Lh<.').C. I'nw(<r 75-1440. I'.. Ilc<<tty 1>rose>>tc(I Lhj.s L'<<m-I'or Ilt)V 1152A c(. Il I'CN por<<ry proc(:(Iur(1 ch<>>11'<.'or rev i<<w Acid I>>itial Coo(li tion: 3.4 Prjor to holding a valve, all valves in L'hc <ysL'cm Ll>at: provide thc <luplicat:c f>>>>etio>> sha'l.l l>c tcstccl to dem-onstrate opcral>ilj.ty Add Precautj.oo: 4.2 No valve may be inoperablc for a period exceeding 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months S ~ Add Instruction: 5.1 Gycle Valve 8528 for operability Renumber Steps Accordingly Tech Spec. Sect. 3.3 The Committee reviewed this change.75-878 GS-21.0, Site Access Control Security and Personnel Identifi-ca'tion PCN 75-1435. E. Scatty presented the following procedure changes. It requested: Also some minor changes to correct typing errors. Thc CommiL'tcc rcconm>en<lcd approv<<1 of th<<sc change...75-879 GS-31.0 l)o(>r A1;<r<<> Svst:cm, VCN 75-14(i3. I . ))catt> 1>re: (>> t<<(l this proccch<rc ch;1>>I;<<. Xt r<<<)ucstc(l SL('.I> 3.)3 be cl;<>>go>'< Ht:>>L'io>> I'.ve>>t ltcport (A-25.1) 7.'i- Bt) I) 75-27~1 1n::tnlintion~o< Switoh on tli(: t.('.. I'owot HH I'o>. Itt)V U.)6 A fol)owi>>g t'l I.'CN proce<1>>l.c cl>a>>I~<<Q. '1.'i-)4 A I(< I. I . Il(.<<L'ty pr<.s(>>>L'ccl TL'c(lu(:sL'Q(l; L'hc InscrL>><<w Step 5.20 as follows: To conL'i>>uc pr(>ccdurc for V-U~)61) >.cfcr. I>;<clc to Step 5.) thrn<<gh Step 5>.8, l>cforc co>>L'i>>ui>>g with Step 5 2) . ~ After oe<<SL'cp 5.20, renumber thc rcsL of sLcp con..ccut:ively. The Commit:Lcc reco<<<<>>coded approval of this ch;1>>gc. -156- I >u I Atnutnl R<>ort I/I I. <>I nl]. I>r<>c(.<lure <<hnt>I,<.ri'(C<>>>>t:I>>u<<: I) I/I./i << >> Ir./ II I/.>> ]nc lun I v< ~ I'OIIC 'I'I'I'.H NIII I II I'.Il: I) I It: It I I'I' t >N 75-882 E. 13eatty pxesenLed Lhc following new CP'. CP-5.0 Cn]ibration Aliinment of T'Av and Delta T at 7cro Power Channel ] I'CN 75-1442. The. purpose of this procedure is to verify thc calibration oi Lhc T'Avg and Delta T ampli-fiers at zero power using thc actual R.T.D. measurement and calculating a true, T'Avg and Delta T value for Dana Amplifier zero. CP-6.0 Ca]ibration A]i snment of T'Av and Delta T at 7ero Power Channel 2 PCN 75-]443. The purpose of this procedure is to verify the calibration of the T'Avg and Delta T ampli-fiers at zero power using the actual R.T.D. measuremcnt and calculating a true T'Avg and Delta T value for Dana amplifier zero. CP-7.0, Ca]ibration Ali nment of T'Av and Delta T at 7cro Power Channel 3. The purpose of this procedure is to verify the calibration of the T'Avg and Delta T .amp]ifiers at zero power using tlte actual R.T.D. measuremcnt and calculating a true T'Avg and Delta T value for Dana Amplifier zer'o. C]?-8.0 Cali.l>raLi.o>> h]i nment of T'Av and Dolt:a T 7e> o I'ower cha>>nal I). Tha purpo a of <:his p):caesura. is to vcri.fy <hn col il>ra<:ion oi tha 'i'hv8 a<>>n<l l>altn 2 aus)li fiars at taro povur using thc actual 11sT.I). m<<asuromcnt an(I calcu]ating a Lru<<T'Avg and I)<>] La T vnfu<<. for Dana Amplifier zero. Thc Co>mill tL'('.<'. r(!c(>mmended apl>roval of']lese proc<<dules. /5-883 8-I2.2~0>o):>tor AcL lan 'In 'I'l>a Rv< nL. of: In<licaL'ion of ~sf)1 liciuni':. ii>crn:):nu ln i,cn<<l<n~< I'(.'ll 7">- I <>33. II. IluntLy I>>'u::<nL'<<: I LI>I:: )>> bc tel<<<n in thc cv<<>>t: of a signifi-cant incrcas('n leak(tgc o>> any of our ]<<nk dcL'cct:ion sys-tc>>>s. The Co>m>littc(. rccomm< ndcd approval of this procc<lurc. 75 "8IIA 8-I2.'3 <j)>arntor Aali<>n Y<>r. ~Si. nifiannt 1~col<a c 'I'hnt CnnnoL. l]e ],oc:t~t<<<l I'CN 74-1436. I'.. 13enLLy 1>r<.s('.nt<'.d L'his n(.w pro-a cedure. This 1>roc(.dure describe., th<: sL'<<p<n to b<<Lnl<en significanL increase in leal(agc cann<>t be identifi.cd u..ing if S-12.2. Thc Co>mnittcc rcco>mnended approval of tlti.s procedur<< witl> mo<li fications>1 I'-] In ]AC lto<l C<>nL'rol Pow('.r Ci.rcui 75- 145<) PCN 75-1470. I,". 13caL'ty 1>resented these proced-LCN ure changes. PCN 75-]459 Add St.eps 5.5.1 and 5.7.1 as f'ollows: 5.5.1 Install jumper from PS-2 Terminal 4 to Neutral 13us. 5.7. ] Rcmove jump(.r ins tal1ed in Step 5,5. 1 l A>>lull)l. Il<<port: II].]. Ol'l] l. l>r<?c(.dllr<<<:ll,)111,< n; (C<<IIL'i>>II<<. I) l./l./'/'i t'<> ]2/3l./7 "> 1>><< l.u.: l.vc P(ll((! I.'}'l H Nt lHI)l'.ll: l)li!'(:8!l'!'!!!H 75-886 PT-2.3. Sllf<. nard Valve 0)cration PCN 75-1454. E. Beat;ty prcsentcd tllis procedure el)ange. Several. >>cw sLcps werc added under Precautions. Tile Committcc rcconnncndcd ilppl oval of tllis cllangp. 75-88? A-2.2 ]/H Curves PCN 75-]458. E. Beatty presented Lhls plo" cedurc c})ange. It r<<qucstcd to revise ]/m plant in thc pro>> ccdurc. Tile Committee rccomnlcn<l(d npproval of tllis cllangc ~ 75-888 E-28 Jtcact:or Coo1lllL I.<<a]c PCN 75-145>2. I . J)r aLty prese>>L'<<d this pro<<cdurc cll;lngc. It was requested in !>itcp 2.4.2 L'o change words "pressurizer relic.f valves" Lo 1 Q<ld conLa dcprcl s<lri ration vnlv<<s." The ('.Onln)i tLQQ Qd n p pro va 1 I.nnlcllL'ecommend of tllis <<II'I>>ac 75-h'f>9 8-4.1(: l.;II>>I<1).v 1:Ql.ense p(.'N 7 ">-1~15'). l:,.Q;Itty prcsQ>>L'<<d L'llil proc(>dure <<}I:I>>}<<., it was rc(lucst<<<} t:o c]lant Q Step 5.19 to read "st<lrt'nl>>ldry pump eontro11cr for. t:ll(. scl<<ct(.d tunic t:o bc release(t." Tll<<ConmlitL<<c 1< connn(llldcd applov<ll. Of tllls c]l.<n}',c. 75-tV)() )-1..2 1,oss <>l.oo]'>>lL Aeci(lent JCN 75>-1462. L'. l)Q'Itty pr<<sc)lt(!d t:ll l.s ])ro<)cd>>re cll sill,c ~ IL was rc<lucs tQ<l Lo < Q].QL(. !lL<<J> I1.3.1.1 <<nd rcn<<nlhcr '1<<cordi>>8]y..')1)<<Connnitt:<<c 1"Qeonnncndcd .(I pl>I'oval of Lllis clio>>gc ~ 75-G9( Abnormal Occurrence 75-3.2 Failure Of'Undcrvolta e Belay Durinp Vionth3 Surveillance. Tost. C. Hartlieb reported to the Colnmitt,ee that during the performance of the ))onthly Surveillance Procedure, PT-9, "Undervoltage and Underfrequency Protection"on July 25, 1975, upon opening the knife switches for the solenoid coil of primary undcrvoltage device 273/llB, itits'e- was dis-covered that the device aramature did not drop down to energized position. As a re"ult of this failure to operate, the Reactor Trip Undcrvoltage Protection signal was not generate.c1 thi" relay. The Committee made the following reconnnendations: 1} All four undervoltage relays be cleaned
2) Upon returning to service procedure PT-9 be performed again J. Mitte presented Corrective Action Report, 1029 covering t;hi.,
abnormal occurrence. -158- h>>>>u >i f)rl>>>rt: //l. l. >>l nl l. I>r>>ccr)urc cl>>>>>I;i'.n: (C>>>>I b<<>c>l) I)I:."CII I I'I' () Il ~7g-0 0 E. Beatty prcscntcd the following ncw procedures; M-11.13 Xns ection P M:Lintrnanrc Of Goulds P>m>>s PCN75-150.".. This procedure i" to be used for thc inspection and n>ain),cnancc of Goulds Pun>3>s, Model 3196-STD and 3197-8)'D or similar ccntrifugnl ~ units. CP-5.10 Cali)>ration A] i,n>ncnt OI'>Avt;. 8 l)ella T at 70>'ower or Grcatrr I"or l>oo A Unil; 1 I'CN'(5-i A. Th.is procc<)urc in to verify thc calibralion of T'Avg. and DelIa T a>nplifiers at 70/ power or greater using the actual 1).T.D. measure>ncnt then calculating a true T'Avg. and Delta T value. CY-7.10 C:il.ibr:>tl.on Ali <>>>ncnt. of 'I" Av PI Delta T At, 704 I'ow<r Or 0> c:>V r For I no > B Unit, 1 PCH75-1467. This procedure i., to veri.fy the ralibration of T'Avg. and Dc1ta ')';unplificrs for l.oop 8, Uni), 1, at 70@ power or greater using t,hc actu;>1 R.T.D. mca"urcmcnt." then calculating a true T'Avg and Delta T value. CP-0;:IO C;Qibration AliInmcnt Of T'Av Pc Delta T At ~ 70/~ Power Or Greater 3"or Loo B Unit 2 PCN75-1468. This procedure is to verify the calibration of T'AYG and Delta T amplifiers, Loop 8, Unit 2, at 70$ povcr or greater using the actual R.T.D. measurement thon calculating a true T'AYG and Delta T value. ST75.5 Monitor Six Steam Generator Levels Simutaneouslv From All I'our Reactor Protection Channel'CII75-1439. This procedure is to provide information thru recording of six narrow range steam generator levels as requested per <Iestinghouse. The Committee recommended approval of these nev procedures. This item XS COIIPLI";TE. 75-895 E. Beatty presented the folloving temporary procedure changes for review only. 0-2.1 Normal Shutdown To Hot Shutdown PCll75-14 4 to facilitate steps marked N.A.'d. ST-75-4 Turbine Plant Start-II Propram Followinp Plant Tris> Of 0 56 liours On 6/17/75 PCN(5-1493 vas to facilitate step 4.2 N.A.'d. P-9 Precautions ) imitations And Set oint P-9 Radiation Monitorin>> S stem PCN75-1481. requested R-12 alarm point is 30K, present reading <27K alarm should be raised to 35K. The Con>mittcc reviewed these changes. -159- Ail>1(li:il. ('i(ir': 'i )I('(it'I; //!..,I. (>I'i! I. (i .: ' c}>r>rr},(i>: ((:(>>>I.I>>>>t.(') Iir<i(:(.'(I(rrc ! /I.!'I'i t:(i'. Iiic 1.<<r> I vc ' 'i II(}It(t I )'I'.I l I}I t'('ll I l'I' () tl Hill'illI'.ll: \ 0-1.P. Plant Peart Hol: Shut>town Vo Steadv Load PCN75-l}r 5 ~75- 00 E. Beatty present, cd these procedure cliangc . ~5-. 'ead valve MOV 4007 closed. k T}>is was t;emporary for review only. PCN75-1492 - re<}ucstcd sign-off liiies be a(b}eQ to stcl>s 5.4e2 ar>(} V.r,.u. The Cori>rnittee reviewed }'(:N75-1495 and recommended approval of PCN75 11>92. 75-906 S-23.2. 2, Cont ainmcnt Pur,e Proced>>re PCI}75-1408. H. Beatty presented these procedure changes. lt was requested; Add step 3.3 - "A containment release permit has been completed by ltealah Phy'ica Ur>de> step 5.2 - elimiriat,c "RlOA on containment " ndd; In"call r>ev filbcrc on I'110>t (Not.icy II.P. Tech.) add; It-lOA valved to cont:>in>n<:nt vent sample line (not.i fy II.P.'I'cc)>i>tc.ian) U>>der>>t'c}i 5.3 aftc> "c,'l.ost. I'I,'UO" a<}d; "chant c filL(.rs on ltlOA - Not.ify )).P. '1'ecl>. I"1'imi>>aL< ol(I >>ppc>>(tix a>>d ad(l n(.w one. '}'lic Con>nil t.t,c~.<ic(innr>(!r>(}< (I <<p}>i'ov:>.L of L}>I~Dr.'h<<l>[.;t.":. ~ I-l.ll'1 Pr(:-!I(atop!'!prrra ltrrLrrirrtrrrcnt Ghccl; I,j;;L Prltt'I>-it+<<I.. I'l. Beat.t.y lir(iso>it,(>(1 tlii>> procc(lu>'c c}>r>n(P( . I t, i cqiic>>Lc<l t,o <<('Jd 't.(.11 3..'1..3 to rc<<Q; "Pla>>t; at liot, sli>>t;down fo') lowi>>(y, i cacLor tri}> aft;er turbine trip" 'I')ir: CornrrriLLcc rr:comrnciidcd aplir ov(il of tliis c}>an(;e. 75-91(> 0-15.l. Flux M:>> > >inp Normal Pro('<'<}>>re, PCN75-:).490 1409.'"'. I]catLy pr'cser>Lcd thc c procc(}u> c c}>an(;es. PCN75-l409 rcq>>outed step 5.54 be deleted PCN75-1490 requestcQ step 5.25 to a(}Q "NoLe: Detector A, Pat;h I/O is plugccd., For thi" path only, 'DO NO'I'Y-PA."y.', 'I'urn Detector A path selector to'at}i I/O and Lurii Qct.cctor A op<.r<<t;or select:or to OFF. I'or pass I/3 t;urn detect,oi A pat,li a<>lect,or to pat}i //3 and tu>'n Dctecto>', Oper'<<Lr>i Qcl<.cLor t,o Normal" -160-nt>rtttt!Itn<<tlr ttitrrtvyt 1 <<(7 Atttt<<I)1. I<<>rL ~ (jll <>f <<11. 1>l;<><<((1<<r<.'llt)t>l;<tn: (('.< IIL}IIII(.<l) 1/I/I>'> I'() ).2/'j /1'> 1 'I tlc 1.<<!I I v<. I'OII0 I'I'I I I Nill1(i(:k: IIIII'(:I(11'I'ON 7(-OI.7 ri'-(>.IO O'Lli'l>v>l.:inn Alf,><rnvi>(: of'Ifly', 7 f>uIL<r 1'(; fog I'r>yvv Ov Ovont~cr I,no A, I(nil; > P(:N7>-lich(i. i . Iiontty prv)o>>l vd Lhi:: tl<<w pt'<)('(!dltt'<>. I'ot')<')La 'l'rt<) 'l" hvg, ~ lfr(<n for HoacLotrol,o<:Lint), C)tat)it(.'I 1'I. 'I'}I(> Coltuni.LI,(.'o rocormn(.'tl<l<:() (t}>pt ovttl of >I,'ll i 1)t'o(!('(It<I'(:. 7> r)1c) 1"l'-16 h>rz i 1.'i ar T"o(:<Iw!<L'(.r,'> .",L'<.'m } low C)tool( }'(if}('j-1'>lit ~ E. })crit.Ly pros(:nt;od I;his f>rooodur(> c)I!<Iti:<!. J I; roqtto:.:L<<<f in stop ().1.10.1 MOY )I007 1)urnp (lischar(yo valve clo'od. Thc ComtnitC(.o rccomrnondod appr(>vol of Lhi: ohangf'. io bo lefL 7>-<IPi> M-37.16J Xn.,noctinn Pc Maintenance Of Thc Motor Driven Attxiliar )"eed Pwn .Hecirc<<lttti.on Control Yalve PC)}7'j-.l)IO2. E. i)cat ty presented this procedure c)lan);o. It was re()treated under Initial CondiLion>s to chance step 3.2 to read "Secure air "upply to valve positiotlor (tnd rom(.vo s(nsitt(; l;ine" Step $ .0 under Inst.tuctions: Change'tep 5.13 to read; "Sensitt(; linc. installed and (tir supply l'o positioned turned on" The Conunittoo recommended approv;tl of tho.:e c)tat)fr(.'.<. . ly-9")I J I(id-i .1(<fr< lor Ih I'ur 'I L>>~(I<>(!c '~r: 0:rnl i n>:: flnri f<r I jyji I I'('.ll'f'>-.IO I'f 'f'>-I Ifi.> Ii. I,r:r:::r prr><:r <luru oh ccc(',o::. 1'C)I'(y-1.0<)7 r'(:<III(::Iod Ilwo llew "I cp. I)(> itl(r()!'I)oral,od itlLo .t)ti" pro<<od(tr( . Stop 5.'jg.l - I!tv<!I)Lory fuel irt col.o )>y <>ompari::orl Ttq~o to Fuel ULaLu:; llo<<or<la of'ido SLcp 5,100 Tnvct)Lory fuel irt:;pen(; fuo'I. piL )>y vor ify:ill(; t)!ere i>s a fuel an"(.mbly irl each local,inrl indicated on the fu(:1. sLat;us I ceo) <1: by corn})arit>(y fuo1 t<ssontl>ly rlwnbor ttnd l.oc((l,ion apt!<inst tho 1"uol, BLaL'u!: )I(:cords. The Cottunittoo r(:commended tq>f>roval of I;hone it;em c)ta>>(.cn. '.:ontov <'nrh>r r < 4:<c>i< . Il. <7<1>r Lull:<lit',t > I I o clul c L:::<L<'I:: 6.() l.lll'll (1. ().0:<IIII it><<<>t Ii<>l;ll,t) I.)tt ouuu(.lltl<<: I t<f>l>t ov;l.l ()I',l>i:: <<II:lll;v< . ~ '('>-< I; '<) 1"I'- C~('<>tt(.alt<tilt III. !')I':tv I'Ilm 1::-htli) II!I(tll A(it)i l.i v< !!y::l.i ul:: I'CN'(')- l".> I 'i, Il. ltt 'Ill.I. y I >I't ".:f 'll I. ~ 't'1 'I I << I'1 ' I I. I'<'till('!: I.t'tl I L <') I> I< )ul I I -c y i l>t' tt('ot'l>t>t'nl.<<' I lll.<> I.ll I!: I>I'0('I'l >'<' I'1>v!I I t) I'.i>i:: <',ll:It>tv(., Ilt<'1'<ilfuttt!I<lit'> >>>I<<'>> lr >> >'r ',t>'t it!('tl>>>'t' l)i '>(I. I.y >-t) 1() I> I ) ~ ~ ~ r ( t>>> ~ I (~N (,> I p I 5 ~ I'r ~ J>) ( at(>>l ( tl CI>> I>> ot t tl>>> t ( l>>(>>I I ~ I I> ) ( tl>> t >> lr( (I >ul<l lo .:Ct!p 5.1 0<('I(:u'I:(l.it>>> wi'l 1 l>t < o>>>1)lt l.l!tl lly ~ lit!(lt,l> I'l>.y>>it i>>l, o>> ('(1>>l.:(i.>>>><<!>>C J>u>'Ivt! >'t'I ( >(>>( I'<l>>>>>>>>1>l! I i I tl l>y ll. I'. ~ ~ (!I>a<>(P,c p.2.1() I.o r(.ad: "J>Ion il,o>'1-10A, Il J'c 'I.v> to>><(l 'i 1'y CI>al; p>>>'Iv<>><(l.i>>I'3<: > rcl canc l..imi C>>. J(ccord J(-lOA, 11 Fi 3,'>, w.i.nd sJ>(!<.d <)nd (i.i.>(!<!Ci<>n on (d'or>C<(ir>m<!>>L i>urp(. !'<:3casc f''>>><<
3) Ch(i>>p(! 5.3.9, Insert J(3.0 b<.l,wcc>> "Besel, a1ar>>>"
The Committ,(!c recommend'ed approv(('l of'?>use 'c?>anpcs wi.I,J> modifications. T?>i " .item IS COblPJIJ".J'I". ~(i- 31 (JG-21.0 Site Ac<:esn Control. (Sc<<ur Jtv) Ar<<4 Per.",onn<!l. Ide)>tific:d,ion I'CII75-1527. I,". Beatty presented this procedure c?>a)>(ve. It reque t,ed in step 3.5.1.1 to chanfve with escort to witl>out escort. The Committee rccommende<J approval of this cJ>an(,e. 'l'his item IS CONJ'JJ.".J'I". ~75-< IP I". ~ Beatty presented thc fol3.owin(: procedure'or dcl.ction RSSP-7.3. 'lcro Power T Avera(ve and Delta T Alir>>ment PCll75-1501.. RGSP-7 2 e At POwcr T Av . lc De3 ta T 'S an Ad ustment PCJI75-146 HT-72.1 Hvdroven Paroxi<le M<iil:ion To Rea:tor Coolant D<rrin Cool<lo<rn PCII75-1506. ST-73. 4 "DB-75 J)J1-50 and DB-25 Ci.rcu) t Bragi(cr Overcurrcnt'ri Device Test and/or Re lacement" PCil75-3.503. ST-73-8.1 Vibration Testin>v Propram Isolation of >tea)>> Dump S ste>>> 1'or V:ibration Data A ui" ition PCN75-1504, ST74.3 I >coze P3.ul. on 3" Servi(.() k!(>ter 11eturn 2'ro>>> Thc Ilotor Cooler.". C.V. Panel;ration Cooler D !:avatv in,'ration Pre<a< llonrin.: Coo3.er, i'(;N75-1.505. Tl)e Committe( )'ccomm()n(lc(l approval of these (Jclct:lol>(). ~75- 33 Etl-145 Immediate JJoration Intc,rator YM-113 PCH75-3.534. D. J"rancis pre"entcd this new procedure. This procedure is to provide maintenance on YM-113. The Committee re-commended approval of this procedure with modifications. "162- Au)10<) l. It<! po r t II I I, of n I ) pi <I<'c(l<irc elis ii)s i!n: I ~, is< (0<>)) t. l l>ii( c).iin I vu ', ':f4@"* 'I2/.)I // > I'OI(C I.'I'I'.ll NIIHI)I'.ll: I) I'.S(lit I I' I ( 1 I" ~75- II'3 A-l Radiation Control I)anual~PCI) 75-15))2. E. Dcl4eritt. presented several changes to u))date the manual. Thc Conunittee rccorrunendcd aPP<<val of these changes with )ninor modifications. (5-<?I<'i A-2-.3 Maxi)noun Uni t'ow(.l, )'CH 75-l5<".I). S. )3ul)oc)t pre:;crit;cd thi" p)'occd>i>c (.h(<>>I;c..'It; re<IucuLc(l: Hcmovc ln::C three lilies f>'o>n Put;c 2 (C<<lori>n()L'ric ?hcoL): Q.C. Review;. 1'cceivc(l Cent:ral Iiccnr<)s; Non-)?cr>:<anent Di.spos it ion D;iL<<. 'I'he Coin>nitt<<c recoinm(.nded a))prov:xl ol))is procedure. 75-948 SH 75-15 Auxiliar Buildin Ventilation i)i.h lladiation Tnter-loclc. G. Canori of Engineering prescnLcd the Design Criteria and Safety An>lysis,for t:his S)i. Thc Conunittec performed tlic Safct:y Evaluation and found that the modification does not involve an unrcview<<d safcLy question and tliat: Teclinical Spec-ifications are not: affected. 75-9(' Shf 75-30.1 ))eactor Tri Undcrfre ucnc ProL'ection Bus 11A I'CH 75-1553. II. Cunt prcsc<ltc<! tllls IICI< procc<luru. I'I>c purpose of'his procc<lurc is to out'linc tl>o sl:vps for rc>>>ov-ing a>>(l replacing protection relays 811/J.IA and 8]2/llA witli a new niodel I'1" relay-.-t:o-r(:d<ic(. 'pro)):>bility oC a relay m:ilfun<<- 'Lion. '1'lie (',o>)llnitt<)e lecolluncn(lcd ap))r<lv(>l of Lhis proc(!diir(!. gg-<) 5() 7,-'III.? I,'vn(<< I< v 'I'v(3> l<<><l< rfvvul>><<:>~v. I'>'ol<<:tl<>> ).i )i~I(:W /'>- I 'I') >. I). ('f:nL>>l ('n< )>I:c(I Llii.: ))ow )?) (?c(:<1<<l <<. ~ '11<<>>>>r) <>ae <? I Lliin>>ro<:<<()i)re in t:o out.l I)>( t.'li<<, nt.(>>a I'or rcnlov J))); (ii>fl rcp)<)<>i))}; pr(>L'(:cl"i v<: r(:1:)y!: )311/I ) 8:i)1<1 8'l2/I I Ll> ii ))cw m<><lel I'I'u) ay, Lo r<<diic<rol) ib I ) y o I a )'<<) <)y it I'i ina J, I ii))el I o>)u T))(: (:<nnini Lt(:(. )'( co)i>n><<><()cd <)>>pr<)v<) l. o I'l>i s >>r<)<<(i(I>i)'c, 75-953 S-4. IE )<as te Condensate Release PCN'5-) 523. E. Beatty pre-sent:ed this temporary change for review only. It requested: On Page 2 following valves changed: 9108 Closed 9110 Open 9107 Closed 9109 Open 1771 Closed 1794 Open 2612 Closed 1773 Closed The Commit:tec reviewed t.his change. 75-955 )tI'-28 Dis osal of Trradiat<<d I'low 1')i vers )'CN 75>-1533. '1')ie p<<rposc of; t:liis E. l3eatt:y presented t:liis ncw procedure. procedure is t:o descril)<< t;hc steps n<<ccssary to move irradiat:- ed flow mixcrs from t:lie spent: fu<<1 pit: Lo sshieblcd w!iat:o ! hip-ping dr<<in. Tlie Conunlt tee rccoimucndc(l approval of t:lii.s procul-ure. -163- A))))u:)1 R())()rt III.I ()I' f,l. ))r()e(<lure cl)a))I a: (Cf)<<t.l))))( <I) ~ > ~ I,/I./75 I ).2/31 /7', l))c).<<> l.v<< I'OR(l I 7 I H NIII)BI'.R: 1>I ! >I:I( I I'I' I II I 75-958 M-)1. J9 )ns )ection and Maintenance of Cr:)no-l)emin )'<<m)s PCN 75-1517. I.'. BcatLy presented Lhi.s new procedure. This procod<<re is to bc used for thc inspection and mainton:luce ol Gr<)nc-l)cming L>umps, Hodol.3361 and 3065. T))e Cormnitt<,c recommended approval of this p roccduro. 75-959 M-11.18 Ins ection and Maint nance of Bulfalo For o Pum s PCN 75-1518. I . Beatty presented this ncw procedure. This proccdurc is to be used for tho inspection and maintenance of Buffalo For)",e Pumps, Model 3 x 'g AB. Th<. Committee recommended approval of this item. 75-960 H-11. 1 7 Tns ection and Maintenance of Meinman Pum s. PC)N 75-1 519. E. BcaLty presented this new proc(.dure. This'rocedure is to be used for the inspection and maintenance of Mcinman 1'umps, Model Ml'.3300 U and lz-21CB-2A. The Committee recommended approval of this item. ?5-961 M-11. 16 Ins ection end Maintenance of Durco-Dunrion Pum s PCN 75-'1520. B. Beatty presented this nau procedure. This procedure is to be used for the inspection and maintenance of Durco-Dunrion Pumps, Model 3X2S - 10/74, Thc Comm'ittee recommended approval of this proc ed<<re. 75-9ll2 H-ll.15 'ns <<ction'and Haint<nanco of Pacific Pumis, PCN 75-152L. I'.. BoaL'ty present<<d this new procedure. This procedure Ls Lo bo used for thc insp<<ction and maintenance of Pacific L'umps, Model 6L-S)I(:. 'J'hc Com>nittcc recommended approval of this procoduro, f5-9I)>') I)catty lir<<- aunt(d thi: cl)anl,e. JL reque" Led t<) cl)anl;c I>>)),e 6 Lo a);roe with thc proc<<dure. 'I'1)c II)')<.part>))cnt will review J'-9 'for ad-cq<<acy o) Lhc al )rm sotpoi>>L an<) ()1()r)n ba" i(. 'I'l)e Com>)) i L t ec rCC()mmcnd(.d aPPrOVal. Of th'iS Chan);<<is 75-965 A-2.3 Haxitm))m I!ni t I'ower I'('.N 7")-152>'). I, BeaLty pros(:n>:cd thi: procedure cha>>I;c. 'ft r< q))ca ted L'o add: SLcp 3.5 r<<bardi))I; co)nput<.r bei.>>b out of service. T))c Committco recommended approval of tl)is chan);e with modifi-cati.ons. 75 967-0-1.2,BeattyPlant )'.. I'rom )lot Sl)utdown to Stead ),pa<i PCN 7"- I~J presented this procedure change. Et request<<d: On Pab~o I), under socond "PRI:CAUTION", third line, change 9% d, K/K (900 porn ) to . 5% + K/K (500 porn) The Con)mittce rcconuncndcd. approval of Lhis chango. -164- nnu>> It('pot L (.( <<r(. c I >>>I',('.a: .(7>>t: J.>><<(:( /5 t() 12/ 3 J.//'>>c I.u>> J v( I'0ltC 1.'I'II'I Nlllln Kll: I) I 8(,'lt I I'I' OI I 75-'968 H-11.13 Ins ection and Haintenance of Goulds Pum s PCN 75-1532. E. Beatty presented this procedure change. It requested: On Page H-11.13:3-Add Hechanic Foreman signoff. The Committee recommended approval of this change, 75-969 PT-23.24. Containment Isolation Valve Leak Rate Testin Reactor Su ort Coolers 1nlot and Outlet . PCN 75-1536. E. Beatty pre-sonLed this procedure change. It requested to make minor changes to update the procedure. Thc Conunittoe recommended approval of 'these c)changes. 75-970 PT-23.30 Cont:ainment: I.,oint:ion Valve Leak Rate Testin Auxiliar. CoolanL 8 stem I:.xcess I,otdown S<< ilv and )tot<<rn) PGN 75-1537. E. )3oat:ty prc.,cnted this procedure chango. 1L'oquc t:cd t:o make minor c)ranges to updaLc the procedure. Thc ConunitL'cc .recommended approval of these ch>>nges. 75-9/ I. )'T-23a19 Containm(.nt: Tsolation Valve I.oalc ltat:e Tostin Sa I'ot In'oct:ion S stou( I't:N 7.'>-1540. I'.. 13oat:ty presented Lhis procedure chango. lt: request:cd to malco minor changes t:o upd>>Lo thc procedure ~ Tl>o Conuni.t:tcc roconun ndcd approval of Lhoso changes. 95-972 1'T-23:50A Cantainalant 1."olation Volvo I.talc Batt Ta.",tin Contain-(no>(t Po.,L Accident Air Sa(n)lo Clean Tnt. Bl(l . PCN 75-1541. ~ E. Beatty present:cd this proccd<<rc change. TL requested Lo wake minor ciianges I:o update tho procedure. Thc ConuniLLc(. rcconunonded approval of these cha>>gcs. I 75-972 1T-23.40 Containment Tsnlation V((lve Leak Rate Tcstin Auxiliar St:earn S(>> 1 and Condensate Itcturns PCN 75-1544. E. I)catty pxo-sentod Lhi.s procedure chango. Xt requested to n>akc minor clianges to update the procedure. Tho CommitLoe recommended approval of these changes. ~ a 75-974 S-4. 1Y Laundr Tank Release Us in Chemical Drain Pum PCN 75-1545. E. Beatty presented this procedure change. It requested Lo make minor changes to coxrecL the procedure. The Committee roco(mnended . ~ approval of these changes. '75-975 PT-23.5)B Containment Isolation Valve'Leak Rate TcsLin "B" llvdro-en Rocombinor (Pilot and Hain PCN 75-1548. E. Beatty pxosontcd this procedure change. lt requested to make minor changes to updat:e the proceduxe. The Cormnittce recommended approval of these changes. -165- A>>>>ual. Rc ltc>> L' a pl t>cc dure chs>>l'cs 'u>>('uc't l. /5 tu 12/31//5 I mac lus lvu I'ORC lIEH III!8(:I(I I' IOII 75-976 0-5.1 Load Reductions pCN 75-1460. E. Beatty presented this procedure change. It requested: Delete steps 5. 6 (all) and 5. 7 (a 1 1) Add in place copy of Tech. Spec. sections 3.10.2.9 - 3.10.2.12 .The Committee recommended approval of this change. '5-977 0-5.2 Load Increases PCN 75-1461. E. Beatty presented Lhis pxo-cedure change. Et requested: Delete precautions in step 5.1.4 Delete s tcps 5. 7 (all) and 5. 8 (all)- Add in place copy of Tech. Spec. sections 3.10.2.9 - 3.10.2.12 The Committee reconnnended approval of this change. 75-983 S-23.22 Containment Pur e Pxocedure PCN 75-1556. E. Beatty pre- ~ sented this temporary procedure change. lt reques tcd: Step 5.3.9 N/A Lhis step. The Committee reviewed this change. The Contmittee reconunendud the proceclure be changed to allow performance of this step as directed by the llea 1 th Phys ic is t s. 75-982 SC-1.7C Nonitorin Site RadiaLion I.evel B TLD PCN 75-1558. E. Beatty presenLed this procedure change. Xt reques Led: Change 1 igurc I as new marlccd copy Adcl new Table 1 on Site Environmental Locations. The Committee xeconnnendcd approval of this change. 75 983- SC-1.78 E. I'icld Determination of Todinc or Particulate PCN Beatty pxcscnLc:d this procedure change. T.t requested: 75-1557. Step 3.4.2 Add, Remove end cap, to beginning of senL'ence SLep 3.4.3 Remove ("} and substitute 4.5 x 10" >'t bottom of page can be removed. The Committee recommended approval of these changes. 75-98~i A-54.3 Cuttin and Weldin" PermiL PCN 75-1525. J. Noon presented this new pro"edure. The purpose of this procedure is to outline the authorization and =use of the Ginna Station Cutting and Welding Procedure. The Committee recommended approval of this procedure. / -166- llllll I~ c' >(> f>t <I( ~ (i(ftiri c i 11>}'>>(!ll: C(>tlt. f till<<' I I'i t<> Ii!/'ll/7'i 1 ii<< Iti.: I v< ~ I'()ItC I 'I'I H N lit I II I'.ll: III"('lI O'I'II)II I ~)-<)<)0 I "1'-l l'" I".rtt~<'r '<'I)<:y 1) t(>>i<..] (l<)<tet" t.ot' li PCII ('>-1 yAC i(iti i ovi cw c>>il,y. 1>>.'. 11<or(1,l,y I>> c>>onl;(:>< c <It<re. ( It<it)tr<>> 1'icf4'f y- I yOC> rci(lii(".:I,<>> l.c ll>> C>. 1 I> l,li!'()ii,".Ii C>. l?3 tttt<l t.(:I) 6. 13 1>< ~ marl:rcl f4.h. it>> (1'tt.<c rtttrrtt>< ~ )'>> it<>t: I;t(V< n itn I,ftc y (I.i(l nol; ( ont;j>>tic w'i t.li 1)i cnc..l (l<.>>l.t;tt,(>t ol)<ii;il.ion. !'I,opi)(.>(.l. C>c.nc.rittoi'et'I.li.t liytt(>> e t,o lttt>> .'1.7, Pc14'fi-3 p0<l r<<lit< r:I.<<:1 nt.<:I)>> C).'ill t,lti'<)ttl;It C>.23 ~ b( imtrl'.c (I H.A. (tt: ort,'Ly c:1<>>>lit'0 0( Ifll>> ~ I.C> br< rtf:( I wit>> I,<>>;t,c cl. ~ '(',i-<)<g I I'-,'?) I( (:>iir. i<>>i::, I.iirl'i I.rct. iF>n>>:iii<1 ~ >><'+I ~ >n'>>>i.ii 1'- ~) II<><l i.<ll' <>>i M<1>>i I.c>t'iiir'ay::I.< ,C ~ ril, I'tiff'('.l-7'>r'I I . Il. It<<: tl, t,z rc>>util,<> cli:>>>i<t ..e>t'oc(.(Itic'<: 'r< view nii.ly. 'l.l, r <<ta<,F>>t.(.<l; a) chili'>(re<> I:cp 2.3.2.3 i't'orit a,imam>><:tt..irrf; of 3X 1.0'pm to 3.g X .10II cl><A b) cli(tnIF< pape P-g:6 un<l<ir 14-12 alar)A nctpoint, from 3. x 10'pr(t to 3.5 z 3.0I cpm 3:t waa rccoimr>cndc(l by PORC that t,hin be i<ra(tc a peri<it),nent chanpe of octpoint to 35K cpm. Iicalth Pliy'icn Dttf)orvinor .".I<ted I;hat I<0K cpm woitl.(1 b<. ai)pro:<imat<.'3y I'1'C. ~7a- 9? H. Be<atty prc"(:nted t'2ic followintF new.CP proce(lure CP-33..0~C((3>b)'at;i<)n an<i/or li intenaricc Of ~our(.e lkanr<c fl-:31 ~ PCII jr> 3 <~-(fr Ci'-31.1 Ooneret Dc.Cent P< one<lure For N-31 PC!I75-157'. CP-31. 2 Oeneralno'.n"..tnto ,Prone<I<<re For N-3l. PCI!75-1 575. CP-3l. 3, Cal.>b):iC:ion Of ottrce F)itn><;c. 21-31 PCH75-3.576. CP-3l.fi. C<alil)ratio>> Of >>>our.cc Bar.ge 21-33., Hi.,t:abl.c Rel,(ty Driver" PCII75-l57" C?-32.O Cni i.'bratfon ac<>r I<a!.>>!.munro Of.'"ourrc. Hr<<>>f n N-3?n I'Ci'l75-'I 572 CP-32. 1. Gct tcr'al. Def c:tt Pz c>c edit t <. For W-32, PCI47j-3. y71>> e CP-3?. 2 Oc n< r:>>1 I!efn".tel < Pron<<lure F<n. N-32 PCN75-.'Li'(0. Ci>>-32. 3 Cnl il<rnl,:i o<<OI ."<xn oe !In<~>>,<: II-3? PCII'(5->.5(>>9. CI>>-3l!. <, I,':<'I II>>r(<! Ion Ol'!onrec: F<nr<<;,. II-,." III:1>> nl>l < llel 1<v llrI<< PCI4'('.>-l. 3C>0. '1'ficii>'o< r(I>> t c n r ol> I:1( c<1 I "J.'6. 3 R. TI I<'collltil,tI, I.o< cn('All>i<I(>>ll(>rL I/J.L ol. <) J.l. I>) t>cc(l<<) c cl)<)>>f,< r): ((:(>))L I))ue(l) t L/I//y t t) LZI'JL/Ia I))c 1>>n I.vc i'OR(: l.'I'I',H Hi)HI)I'.It: I) I:.t>(', ll 1 I'I' ON '('i-')9.$ ) "1';C>. I h ('.:).I i I>> >tt I ti)) I'>'t >( t tl>>')'t't>>>>'( <'ta>>+<'. ( ll!>>>>>t!1>>, I'(ll)7'.>- l.'.>ll(>, ~ ~ J'a ~ I I< ! L L'Ly ))I 't!>> (!>> L ( r I I I j>> p ) ' > <! t!t I >> ) ~ ': .I I, w< u) ) ('(I >> t! ) l'e ( t l L o rr!vJ>>r! t.))i>> 1>>(>t r!<Iuit: l.o h- I><t., )'()ll(: ) <<< enon<<))dr tl <)i>>al>p) (>vll') OJ L'h)!> ) t 1>><<>t'<!) ( ))( w ( I <)r>) l( h<l a 4( en wl,>.LL( n Lo .1 el>l<<( t l'l)i>> J>ro(('<1)tt't.'. J l. w)>>> ) e(:o>>> n('))tlr'.t) J.I> I>> 1 >'t>(.'e(lu)'(! l)u ( 'I in)>>i >>r>t;('tl ~ ~ .'('g- < ) >)(e () (>> r)) ~ t ~ >'r>l, >t>>> h>>tl f >'r ~ t ~ t ~ !:!; It~s>>) I (>> >>>(~ ~ J ( II ( > I p >I, I'e, I.'<'>tl,t,/ I>)'> "'('>>I t'>I I.I>> '>)'l>t't't) >> >'I I>>>> lt ~ ~ ' l w>>>> )' 'tl>>t'!: Lt:t l l,t > .'>t.r>>r l.it>>>>>: "))o nol. <!z<;r!(>>:.)>>)'e li)>>i I >> t>n II > r ool() of'.V f>.-..id nr t>o>>tlr>>>>>>l,r; (:orbal r!)'>f .10 1>':.I(I. I'J'r'r't>>>>)a)'y r> d>>( r I(>;><>" )ter(no>> I'rrr l,l)in Jn to I>) evt:))I; (Irv>>r>pt. I,o cool cs.".. '1'h<! (.'!>>>>)nits.r<: recon)!!>()ndt!>ov!t.'I r>I'.))i" c)<ar>pc. ~75-r O7 )>'I'-", (lontai>>)><<<)l, >T)) rsv )'>>mn>> />n<1 I!a011 hr'Idil.'ivr! ~y'.:t em, 1'('il ('j-l tj(>0. I'l. IleaL'I;y )n<.: t nL(><1 I:1)Js pror:<<dure ch>sr>fr(. lt rc<)nest<'(I t,o rc- )nov o sL(!p (>. 3 . 7 <) n<l )> skc .; L( p fr.3.. 0 ncw 6. 1.7. Bcason for t I) i:: is Valve Aj?!! n(:eds to 'I>(. lefL clo:)eQ for austin;,'!aO)i >>y't,(m operability. Va)ve ir. o)>(-;n<y .".tep C!.13. 'J'1)c Co)nmit.t<<e re(!o)n>ncnd d a)>proval. of'-L))i.n eh<tnt'e. 75-r)r) tI B'>llP-&.2, ))i e>>t!1 (Jr r>em t.o) 1>,o'>rl hnrl S>efr-.r.u >rrl S>~ >>u('ncr ' 'I,, PG)17'j-l, ~7(I. ). Be>>Lty prr!se>>tc t;))is>>) occ<iurr. ch<)n(:e. J't, was s equc..(.e<1 un(lcr l))i.'I,:i.:<1 Conditien:: L'o ad'>>s volta(-..cs >)nd t,he oper<(tion.; of t;he Oaf'et(nard train e<)uip)nenL'" TYpll I'OUI)'. USED DA'J')" Chi. I PI!MT)!I) Beason for this chant;e i., to improve pro<<ed>>re flexibi3.ity. T))e Co)n)nit()ee reco)mnentled al>L oval of thi; chan(re. 75-9()() BSSP-... j, .I('1'v')(r! 1lal <<r P>>n)i> Ainr I>.'(<v;e Chr cl( V;)1vt">>, )'('ll (j'-l. >(>7. L'. )3caLty prost ntt!Q t;))i>> ))rout!dure <<))a>>l;e. 1t. wr)s ) (!<)ue!;Led Ll)t! followinL~ be n(tded ((I; e))<l of procedure to uJ)d:)L(! I he L)roc(>Qu)'(:. ~ "Bcv.i<<w/Ag)u ovn.l P()1)C T)>e Con>n).il:t<<e ) (.'co)>t>>)o>>(lcd '))>I>)'ov:).'L oi'L'l>i>> cl)<tnt',e. -.,168- >am-> a ... I'( At)nu() 1 Re)>or L fl I of )a a 11 l>roccdurc c))t) ))f>cs: (ConL inucd ) I/1/75 I:o. 12/3l,/75 Inclusive" PORC D'L'H NUHI)I ll 1 Dl."SC I( I I)ON 7'j-1 0()() l)ol>l'>>~..6, I",n)1'.C))< V ))i< ".< 1 ",lit'I fi l)i'<'.i);<.i1o>>>>t'< 'fat)>><., I ( W ( ~ I <<Il . I'> ~ )fc<LL Ly p)'( u(.lt Ir<'(I Lll.>,i'r f >1'<>L.'(1'<f >> >'()litt>f,>> >,I I. re<)ll< >> Lc>l Lo i.tt <'1'L'z ))cM .",L<)f> )ii<<lct',Ini f,i:(1 C<>>><li Li<>>t:: I.o roti(f; ~ 'a I).)t Vlui,coz'(1(:t') c(})<iv(<l<)it. u.".<<: I l,o u< cut'c vol L';>f><1 (.)':i<<< . TYP)ef I.I')"I'I) , 1)h'I'I! Chf>'I')(Hh'I'I".I) Al!:o Lo u<1<f >(I, $ .)t<a ()i>>l ofI)< )>1'<>(.'('.(Iui <a "I'()IIC )(<;vi<>M 'I'l).i.n 1 (:ili)t.nl,,i,n I.o )t)>(lnl.(1 I;ll<: l>l'>)<<('<)>>t'<.'. J Il('foll<lit)I.I.<<: (.olllill<'ll<l<.'f'>1'<>vai) (>I I.)>>l'>>a <:I>>: ilf >'n> 'f '>- I )) I 0 1(al'>I'- r'!.'(, a"t>l'r I ~ J>>j<<:I.i< 1> fi<<<g>><:1><<>. 'I'l>t< >'." 'I'>><1 )1 A 5 )' > I'(")'('i-,)gal)r". I". Il< <(f,f,g I><'< ">>< t>I.>>f I.I> I:: f>r>>>><1<f)>>'<. >'I>>i>>>>< ~ XL 1'< <)ll<;nrf,<<:) tt>><)<:1'1< if,.i><l (.'<>>>>f I I;.I<><i:: I<> u<l<f::I.<.f> )t.'.> ~ to rc>uf )I g Y t.:;in<>Z d<1) O) C<)u ia>:(3 <:nl ~ u.".CQ t'Or n)cni I,O) .i.n(; i )i<)i C(iL icr):: ~ 'J'Y)')'"Q)) fi'HI"D CA) DA'J').'A)>XIJIlhT).".)> a T)i.iu i.: Lo up<ltd.c f.li<'. )>roc. (I)ir(.. T))( Co>>.tn.i.LL(.(; rcco)IJA<;l)(1<'8 t))>J)t ovt(J of)ti;: clt()ng;c. 7'i-l00" h'>,'>!'-'(.~0 (,'o)>Lrol. )Io() Dr~@> 'J'():~I, T'(!ll'(>-1'505. I'. )3c~f't y prc::enf,c(1 thi'>ro<<cd<<>.c <<l)(<n(;<.. ILcquc"-L(.d (<fLcr step )t.'j to in:;erL; 'l'YPJ.'F )'l()f)l)'. UliRD DATE >'I IMEA>I>)>;D 'J'l)zn io to ()p(1a'L'(1 t))c J>roco()ure. The Co)ttinitLee recc:ntncnd(:d ap)>rove.l of thi 'ltcttce. la) '(5-100li A-~.)l.l i.'. )3e()Lty pt'ci Cn1.(.'u1.;it'i.on <'t)L<~d Of'fo(, tl);I Xct)nn Free Pi)>uL(lo))n I):tt in )'Cf) 7> pzoccdut e cftii>>((:. 1); re()uc t< d to; r,, '-]"~( 0 DelcLc "NoLc" (Lf'L()r Lcp 3.Q.3 > Ifenu)ttbcz Fi(;. 3 Ln 1"i(.. 1 lfe)>>>)n)>c) )':ig~. )1 Lo )'ig. '>Lcp 3."..l. ) cf'c) Lo )'i(;. 1 OL'<)p 3.f>:r~ rc("<.)'(> )"if'.. f)Lcp .S..L ~ rcJ'< t'o I" tg. J. l>('>>uot) a a~ J or ( )l ill(;< 'i.:: Lo r(')i)lull >('r I i ('il t'( n:i<<<)il>>ii).'Iti I 1 y I <> (' I nt I n(l < (lily c(>il I )1 "> )Ol) ~~ ~ 'I l>a'r(>>tv>t'i L I.<< ol>>ll>> ') >) >1'OVai I (>I I I) Ir 1 <1< > <.Ital)If,<a ~ r'169" of <)11 I>rocc(}ulcc c})<)))i,c<>: (Co))L'inuc(}) '/1/75 Lo 12/31/75 I uc 1u8 ivc PO}tC XTI',H NUNIII'.ll> I l)I'.SCII II'TON I-'[a llr>s llh>> I.>h'uo Ill L[i /1>>u>> I'r'r'1> iil. I'(.'ll'('>-'['>ll[> Ih>: I'r>l'lu>> lrrj', Irr'r>or>in>'rI>L>>i>'r'l..ll. wn: > I'rr'r".:r'>>[a>l u[ro r. Iir >I I'o c}><ill(',(! LI><'0 l,.l(iw,i ilf', >:I.<.'I)!i I.o )'<!n(l;
us I>>(! I) I>. ~ Al.,le:i::I, - r'>sy~~ AK/IL s3 Ir(!I) s rP s ~ )r }I( n.: 'I.l>ii)). s>. I> i',ru his/li fILrp ~ P ~ I 0 <>r Is<'<<'(I <'I' I)<ill ~ ~ Il,i/J AKL/K Bc<a'.:o>> I'(si Lli'ii) <'I):s>>>ws'.: I.li>>I; I'.il;i)i'r '.3.;ln-i'>>ii) L>>}>(:)> oiii. nl' C()ill)'i <'>il sill<<'!.i I i<'iit.i(sii::. 'I'I><', C<>uivii I.l..:1! i'<<:<)nvvs'iisls'[I >)I)I>> [>v:<1
<'l)iiiiiw<' <>I'I)3 "s O 1r>r)7 ,J I>K lis!1 <:;i:: i <>i< II<>n'i I oi 'I':I:sl; 'I'o I) I::<'li:i >'<'. ('ii<>;(1 I '<!I!'f'i-1 '~(i'( . }". }IcaLI.J $ )l'<!><!nt.(!<1 t,l>i.:: pr<,",<!(I)>) <: c}>a>>is<1. 'I2>'i:> w<a.'. >'(!w)',i,t.l.(.'>> 'LO <:On!'Or>>> I.O A-,0 fur>[><)i an(l M><: prO<:<.>r<: r<>ViCWI:II. 'I'liC Co)nmi.tl i.e(! r<!('o>r<><><>>de<'.:(}>L>rosI!LL of I;lii.:: (:})(<>)ps<!'. COII}'I I'"I'I 7y-100ti ~l[-l.r Dlo.".!1 nina>alon lies>in>r>>::naca P<BI7'i-[gill.. I,'. Ban[Ly Inu:;cnhr rl hci.", prana>[are ah>>>[,c; llaw>:rnl. o>>nnl,o- wa> r: nnrlo Cr> Lha 1>rona>la> a to updat>> it to confor>a to A-~0 formut,. The Comn>iLtcc rccovv>>c))<'<.[1 a3>prov(il of Lhis chang,'c, 75-.1.00(> T-l.0}3, T<)r2):i.n(! II;L'jn '.I.'"o<) .",I,s)), Valves '>"~.".t., 3'CII75-l.p:.)n. H. }IcatLy p)'c.".cn'L'(i<} t})i: proee<1>>: e e}>antre. IL ).eq>)<.::I:<>(I. " note bc added betwccn 'Lcp;. q.'3 i>>(3 'j.i'o read 'r HOTH: If th(.: t,e.",t; i." to oc pe).formed usin<", test circuitry, perforvi st.cp:: 5.}> throu'h 5.8 and>>>ark step.", 5.9 to 5.9.26 il.A. If I;h<. L'csL i" to 1x performed>>)ech-';nira1,ly, steps 5.}> throuch ~z.S may be >Aarkcd N.A. ai>d proceed to step 5.9 a1~o to a(1d ))cw st)ep:; p.9 t.o 5.g.26 to 4})e p>wocedure to }>c'r>>it te"Lintof t}>e L>>rl)i!')e stop valve() wit})out uninp I;op valve tc L cir<.uitry. Tlic Cor>v!)it,t.ec )ecoimv(.ndcd app)oval of thi.". c})ange. 75-:I.01.0 3'".I'-lP..2, R!>>( r~>cncv Dies( l. tl(!>>e>'>.I.o> 1.0, }'CP75-'L593. R. 33c)LLty p) cs(!>>tcd ti'>i" pr(>ccdurc r})anI;<) I'oi'cvieis. Tl)'i.': ):<i'o (}or>>n>(')>L wily >t cp 5, s, I 'wsL',s ><>a)'}(c(} W A ~ } ll(. res) >()n w ia L}>s<L L)ic d i csc I wan >)ot'ui) for I/:? )>our, bi)t i.';in ) iin oniy Io))g enouI;}) 4o ch<<:I; brc()k<)>'l.onu) <) on Du'6. Tl>c C()>>>>i>i't.ts'<: reviewed L}>in ci<<()<<;<'. s -170- ~ C hnnunl R<<f>orL'f11 of n11 pr<>ccdure cl)nngcsl (Co>>Lin<<c<l) 1/1/75 t:o 12/31/75 Incl<<sivc )>OIIC ITI H NllMllI'.ll: DfySCRI)>'f 1'ON 75-1013 LC )731 PCllt>-1600. J. ).arms presenteQ thxs new procedure. Thi* procedure is for changing out steam generator level controller LC-I)63F/or LC-473F. Hea on is to isolate feedwatcr control problem on A Steam Generator Loop. The Conunittee recommended approval of thi" procedure. EM-3.))0 Level Transmitter LT-I)61. to Control LT-I)63F and, IC-l)00 in lace of I'evel Tran mitter LT-462 PCN75-1614. Mr. Pari" presented this procedure. The purpo'sc of the procedure is to Qescr ibc steps neccs ary to accomplish the reco)nmendations of PORC Item 75-1016. The Committee recommended approval of this procedure. 755>.OIl. 0-5 lu .iond Reduction.". POR75-1610. R. I!catty presenteil this procedure change. It uns reque"ted to correct.ed a typing error in otep 5.9. '" The It should read "- refer to 0-5.2 load Committee re-co)))mended approval of this change. 75-1.020 HF-l)6 8>ccial Nuclear Material Ph "ical 3'nvent ~r PCN75-1.601. E. Beatty presented thi" ncw procedure. Thi" procedure is to conduct a physical inventory of special nuclear material possessed at Ginna Station. Thi: proccdu) e is to comply wit)i 10Cl"H 70.51 (Q). The Committee recommended approval of this procedure. '5 )")'-~16 Auxi li;)) y F<.cilw:it<.r S>v:;tc)>) Flw~ Clicck PCf<75-3.601). Es llcatty pi ci)cnL'c<f l,lii: Lc)))poru).y chiing<. for i cvicw oiily. Xt re<Inc tc<) iii <it<>p 6>.1.10.1, MOV l)007, pump dinch>>) Lrc va3vc is to be lcfL c3o'i cd. Bc>i:o>> i" for tl)i" Xh<: ) ump <)is<.'))<<)'g'. cl)<)ck valve i" lc<)king c<<unl))g )>u)>)p cu::i>>;; to li<iaL ul>. M >L<<:ini>>g )1OV 4007 c3o::<<) 1>3,ocku ol'1'euk>)g<> I>;il.)i t,o cu:.inl;. T)i)m)ILL<:c rcvicwc<1 'Lhis change. 75-1020 P-9 Precaution" L'imitation" J>nd Setr>pints P- Radiation Monitnrin> System PCI'175-3.607. E. Beatt.y presented this proceQure ch<<nge. Xt was requcsteQ to raise H20 alarm to 30K. The present setl>oi.nt. of 20K gives inter)nittent alarm as bacl<grounQ i 10 to lgK. Bacl;ground. activity. increa e is duc to plate-out on Sl'P heat exchanger takes. The Co)>)>>)iL'tec reco)>))<)ended approval of this change. 75-1030 ~Ro Incomont Of Under Voiture Relays On 4 KV Rn".. 11n S llD. J. Schcetz presented this Design Criteria und '>ufety h>>ulysiu to thc Co)<)rnittce. POHC reviewed aiid recommended approval of thi" Design Criteria. Thc Committee performed the S<<f<.ty Evalu<<tion and found that the modifi<<ation does not involve an unrevicwed. safety question and that Technical Specification" ore not affected. -171" , Wu'ki'hI, I Annual Rcport //11 of all procedure changes: (Co))ti.nucd) 1/1/75 to 12/31/75 Inclusive PORC ITI I'I NUI'ffff lt: DPSC f(IIrf'ION 75-1040 E-14, Hi h Reactor Coolant Activit PCN 75-161.3. ')B. Snow presented this procedure words II is ' change. It requested i s t cp 3 . 2 . 1 to change the returning" to "has returned" as a it t ).s the Specifications that activit be withi requirement of thee Technical h e hours The Committee reconnnended approval of this change 1'urs. ange. (5 j0 ri-3 Cor)t;ai)i)ncnt I )'a Pl)nl) anr'I IfaOII Arlditivc Synt,c)n, PCH75-16)l5. 3 3now prcscn I,ed the::c procedure changes. lt; wa. requested to zccorrcet. steps under "Containmcnt Spray pumps and HaOII Additive System" as ir)dicatcd below; 1; Step 6. )e3 in rci'ercnce to "NOTE" - eliminate 6.3.4 and insert. 6.4.4..
2. Step 6.7.7, in"ert sign-off linc which is missir)g from step.
This is to correct typing errors. The Committee rcconunended approval of those changes. 75-1044 GS-10.0 Security Guards Actions Durin A Radiation Emer encv. PCI<75-1623. 13. Snow presented this procedure change. It was requested to add step 3.1.5 to read; "lock security office entrance door upon leaving for emergency survey center" This is to comply witl) change to SC-1.3C. The Committee recommended approval of this change. 75 101)rp GG-11.0 Pecuritr GunrQ Action.", Durin, A h!eeicnl'mer,cncr, PGI!75-1670.
13. Snow presented. this procedure cha))gc. It. re~fucsted to add new step; 3.4 - All ..ccurity pc>sonnel involved in thc cmcrgency must carry a walkie-talkie This i:. to imp)'ove conununication'uring a medical c)ncrg<<n<<y. 'i'he Co)nmitt.cc reco)runcnded approval of this change.
~5-1 () I) (~ GS-12.0 Sccu) ity Guard Actions D>>) inrm A 1'iree 1'CII7r>-1C)21. 13. llnow prcscr)t;<<d tl)is proccdu)'c cl)ange. Xt'crfucst,ed a ))cw step 3.lf bc added; 3.4 All scc))) ity personnel, involved in thc e<nc)'gcncy must ca)'ry
a. walkie-tallci<<.
'I'hi:: i.> to inrpri>vc comnn)))icat:ion:: du) ir)g << firoe 'i'l)o Conunittoc rcconuncndod <<pi>> oval of thi.'. cl)<<))(;c. -l72- ,<<csrs << Annua 1 Rcport f/11 oC a11 procedure clrnnt,cs: (ConL<<inucr)) 1/1/75 to 12/31/75 Inc lrr>> ivc PORC ITI'.H NIIHIIIII: Dl;."iCltTl'I')ON Site Access Control (Sccurit ) And Personnel I<'Icrttifical,ion~ GS-P1.0 PCI)75-3.63.0. B. Snow present;ed this procedure changre. It request;cd to add ncw st.cp 3.1.1.5 to read; "Vi.,itors to the site must read and. sign ltthe visitor instruction form at 'the .,ecurity office I Corrnnittcc recornmcndcd approval of t)ris change with moQificationo. The "-:!'5 P P. ('r>>>t:>ir>>>>c>>l. I'>>rl >>: I'r>>r>>>: I>>r>. I>CII'('I-I(>o(>. ~ II. 'nou pra:;c>>ta>I thc.",a I>race>lure cl>nnI c::..It rc>lucian>1I ~ to udd !'t.cp 5.2.5 "Scl, R-3.1 rLlrrrrrr oet, point, at: -l. X l.0 c)nn Sl;ep 5.2.7 c)range to rear); "ROll and H03.2 This io t,o comply with P-g and ncw computer addresses, Thc Committee recommended approval of these c)ranges. 75-l.055 0-6.2 Wain Control Boa>rl S stem Status Verification PCN75-1656. B. Snow presented this proccQurc change. It re<)ucotcd in st,ep 5.4.3 to change AOV 200A from clo: ed to OP)Pi'r as rlc ircd. Thi" i" because t)re procedure specifics all orifice. valve." to be closed; Thc. Committee recomrncndcd approval of this change. 75-1056 PT-5.10 Proca.,s In.,trumantation Benctor Protection Ch>>nnel 'irin Te.",t Cl>n:>>>el 1 ) PC(I'1630. (5 B. Sno>> p raasntc>l thi- p race>iure change which re~iuested two ncw step' be added to incorporate the fact t)rat the Controlling Transmitter for the A S/G feedwatcr level. controller (LC-463)") was changed from Transmitter LT-462 to I'-461. The Committee recormnended approval of thyrse changes. 75-1057 Pl'-5.30 Proces>s In.trurnenl:ation Reactor Protection Clranncl Tri C)cannel 3) PCN75-1637. B. Snow presented these p> ocedure charrgcs. It requested .,tepo 6.71, 6.72, 6.00 and 6.81 be deleted. transmitter for Thc reason for t)ris change io that t,hc controlling the A S/G feeQwatcr level controller LC-463F wa . changeQ from tranomittcr L'I.'-462 to LT-)r61. The Cornrnittce recommended approval of t)rene change... ~7"-1058 Eh(-1)r Check Out Lift Circuitry For Control. Rod G-5 In 2 BD Power Cabinet PCN75-1685. C. ):Qgar present,ed this new proccQurc. This procedure is for c)reeking the lift circuit of Rod G-5 in approva1 Rod Control Power Cabinet 2 BD. The Conrrnittec recommended of this procedure. -173- 'fr" rrll 1/1/75 to 12/31/75 ,>>gh Arm>>nl Rcpor L //11 o): procedure c)in>>);cs: (Continue.,d} Inclusive )h0))C ITI M NIIMI!IIR: Dr:SCRI V r10N 75-1062 PT-12.2 Emer cnc Diesel Generator 1.8 PCI)75-1643, E. Beatty presented this temporary procedure change. It requested to change the procedure to check operability of Bus 16 breaker. The Committee reviewed this chango. 75-1064 M-40.5 )1 draulic Snubber Unit In".. ection )h: Be air (ITT Grinncll) PCN75-1676. E. Beatty presented this new procedure. Thi procedure outline t)re necssary steps for di.,assembly and rcas ernbly of thc hyraulic snubber unit" for purposes of in pcction or repair. The Cornmittcc recommended approval of this procedure. -1 0 (i(> R-2.)I.2 Calculat,ion Of'olcl Shutclown )3nrorr Concontrat ion )CW75-1607. J;. Bcutty presented t)ris proccdurc change. It was rcquc< ted to c)rurjgc steps 3.3 arrd 3.4 to; ")6'ay/MTu, to N) Quy/HTu us thc abbrcviution wa" incorrect". Thc Committee recommended approval of this chungce 75-1069 E. Beatty presented the following CP'S requesting the same changes be made on each; CP462.1 Defeat Of "R" Steam Generator Level Channel 462, PCN75-1642. CP462.2 Rein'state Of "A" Stean Generator Level Channel 462 PCN75-1641. CP-461.2 General Reinstate "461"Steam Generator Level PCN75-1640. The change requested general defeat section of the procedure to delete steps 5.3 and 5.4".as the controlling transmitter for level control changed from LT-462 to LT-461. The Committee recommended approval of this change. 75-1070 L'-23.1 Malfunction Of //1 Reactor CoolantPorn Seal. PCN75-1Ci52. E. Beatty pre ent,cd, thi" proc<<dure change. It requested a change to shul thc penp down in 30 minutes instead of existing 24 Irours when /ll seal fails. T)ris is to conform to litcstinghouse recommendation on control lca)cage reactor coolant, pumps. Thc Cctntnittce rccommcndcd approv!cl of t)11s chango e 75 107n, CP-17.l. Cnl!1>rnl:ion Cf !Iran Rn>li>>Lion hionltnrin 'J .;Ice> Ihotoc~lor:: ~ Bl-))9 )'CN75-1 170. J>l. )3c..u).ty pr cscnt<<d t)ri>> I>> occclur<< for dele) ion. Thin procedure wus succccclcd by C)'-209. The Comtnittce rccomuicnc)cc) ap)~roval of this c)clot'ion. -174- Annual Rcport I/11 of all pzrrccrlurc clrarrttca t (Continued) 1/1/75 tu 12/31/75 Inclurrivc PORC ITI M NUHBlR: DESCRTPYTON ~1073 1'.-6,1. 1 on<< Of'orn roncnC Coolin D>>rin ~ ~ 1'ower 0 rrrat,ion ~PC>17'-.16.">>. I",. J>catty pronentod thi -"procc>hire change. 1'h rcqucstc<l step lr.5 be clrangcd from 42/ to 50+~ u F-0 sctpoint; is 50/. The Committee recommcnQcQ upprovul of this change. ~7-107>> It-11..10 Mn or Tnc ccl;ion Of gcrvicc h>ntor Pom PCI>73-16(72. 1". Beat;.Cy prc"cnted thi'crnpornry procedure change for review only. This FCN was to facilitate steps marked N.A. as this proccQurc wa" used for minor inspection and lubricut;ion. .The Committee reviewed this change. ~7"-1073 M-40.2 ll Qraul.ic Snubber Unit Ins ection And Be air Procedure PCN75-1677. E. Beatty presented this procedure change. It requested that in the NOTE under step 4.3 a spelling error be corrected from "it it," to "if it". The Committee recommended approval of this change. ~7-1076 E. Beatty presented the following M procedures for changes; M-ll.14 Insaection Ec Maintenance Of In ersol Rand Fumes PCN75-1663 75-166 - requested to change step 3.4 to read; 3.4 Notify Quality Control for maintenance inspection on component cooling water pumps (SN 0567-318, 319) and containment spray pumps (SN 0667 - 154, 155) ~ ~l75 66 - 5. seal leakage. Step 5.8 should read; "Lubricate pump bearing per manufacturers instruction" Reason for this is not all.pumps are equipped. with seals, not all bearings are oil 1>>bricated. 6 M-ll.17 Ins ection tI Maintenance Of Weinman Pum s. FCN75-1664. This requested, step 5.0 be changed to read; "Lubricate pump bearing pcr manufacturer's instruction " This is because pump bearing are grease lubricateQ. M-ll.l0 Ins ection I Maintenance Of Hrrffalo For ce Furr.">> PCN75-1665 rcquc tcd st;cp 5.0 be changed to read; "Lubricrrtc purrrp bearings pcr Brrt'f'ulo 1'orcc B>>llet;in 3321-1"," Clrrr]rgc step 3 1 2 t;o rc<<d e s glarrd lc<<it<<go, '1'h j. is as bcrrr'jrrg',r are grease lubricated, glandJ rrre packcrl witlr packing. M-11.10 Inn inch<on a h>i>t>ito>766ncc of Cran>-Dcinin; 1'767775.", 17C>I'-1(i(i(i rcqlrcntcrl step 5. bc c)range Lo r crrrl; "Lubricrr't:c prrrnp bc<<r'irrgs pcr nrrrnufrrctur cr'<< inst,ruct;iorrs" 'Tt- '/1/75 ~0 ~ e nnuu1 Re17ort I/11 of o11 procedure clio>>geo; (Continued} Lo 12/31/75 inc 1us ivc PORC ITI'.M NUNIItR: III,"SCIIIV'fION '.l7i-!el. prcscntcd this proccclurc chcu)gc. Thi" change rcqucsCcd several steps be udd<<cl to Chc in" Cructio>>" to improve ccnd clu ify Qic proccclure. 'i'hc Comnti CCcc rccowncnded cci)provccl of Lhis change with modificat,io>>". ~7-107, ~ NS."P-2.2 Dicrel Generator Load d Sate uard Se uence Teat, PCII7B-lti53. E. Beatty presented this procedure change. Xt wus requested to have several steps added to update procedure and. for improvement of instructions. The Committee recommended approval of these chungcs. ~7-lOBO E. Beatty presented the following CP's for the same changes to page 3, Data Sheet, to reflect the current PZ-1 values for Delta T set-point, program. CP-3.0.0 Calibration And./'r Maintenance Of Delta Flux Controllers PCN75-1688. CP-20.0 Calibration And/Or Maintenance Of Delta Flux Controllers ~m5- u . CP-30.0 Calibrat,ion And/Or Maint,enance Of Delta Flux Controllers Channel 3 PCH75-1690. CP-40.0 Calibration And/Or Maintenance Of Delta Flux Controllers 5- 6 The Committee reconnnended approval of these change 75-1081 PT-5.10 Process Xnstrumentation Reactor Protection Channel Tri 'l'est Channel 1) PCN75-1667. E. Beatty presented this procedure change. Xt was requested in .tep 6.89 (SF < FNS} bc changed to read. (SF < Fh'F) also in step 6.99 to add "if desired" for better operation. 75-1082 SC-1.7A Emer e>>cv Radiation Monitorint, Procedure PQN75-1655. E. Beatty prescntcd this procedure change. Xt rcqucstecl off-site tccun //1, step 6F, off-site team //2, step 6F, off-site tecun //3, tn change ccncrgcncy phone number to update the procedure. Thc Connnit,tcc i cconnnc>>dcd upprovul of tlccsc,clnnges. 'I Pr-(i.4 Nxi orc/Tncorc IIacal.tbrnl:ion PCN7>-I.CihB. II. ItonLLy pro.:onecd Lhc:co proacduro chandc". Tt, rcuuc::Lcd Lo udcl two ncw,"Acps Co rcud; Stcli 6.1.1 - I,'>>1.c.7 value in 1(lc021 of "-1" Chi: i>>hibitn cLxilc.ll Cil C progrcUn ~ Aclcl new step 6.11 - 1.'>>Ccr vuluc in K4021 of "0" thin restart" uxiul tilt program. Tcclmicul Specifications <<liow inhibiting <<x.i.ul tilt; progrccnc clue ing reculibrccCio>>. Thc ConnnlCLce recownc>>clccl approval of thi s chu>>gc. -176- Annual Rcport tf1.l. of nl.1 peuccdurc chanl;cs: (Cont'Jnuc<l) 1/1/75 to 12/31/75 Inc lus ivc PORC ITI H NlWI)BR: DHf)CI( JP'f TON ~7-3. 007 ~!. DT-22.i< L'i. mtonk This PCN was to 6'nly. Dokok Doiwonn Door Volnmo Lonkroko To.".I: facilitate steps marked N.A. The Committee reviewed this change. ~75-L00 0-26.4 Com uter Bod Position Alarm." PCN75-1602. E. Beatty presented this new procedure. This procedure is to,provide description of the computer rod position alarm program which is designed to alarm when a control rod is more than 7.5 inches from its bank position. The Committee recommended approval of this new proccQure. 5-10 0 A-57 Com uter Technical S ecifi.cation Belated Pro ram PCN75-1601. E. Beatty presented this procedure change. Thi" procedure is to define responsibilities and requirements for implementation of plant computer programs rclateQ to Technical Specifications require-ments. The Committee recommended approval of this new procedure. M-5".3 Removal Ins ccti.on And Bc laccment Of Control '-102 Bod Drive Mechanism Coil Stack PCN7 -16 6. E. Beatty presented this new procedure. This procedure provides the guidelines for maintenance or replacement of a Magnetic Control Bod Drive Mechanism Coil Stack. The Committee re-commendcQ approval of this procedure. ~75-10 7 S-4.1E Waste Condensate Release PCN75-1703. E. Beatty presented. this procedure change. It requested to change step 5.12 to read "Obtain a sample in a new bottle after allowing the sample line to purge for about 30 seconds". This is to specify sampling procedure. The Committee recommended approval of this change. J5-1099 S-4.1G "A" or "0" I.aundry AnQ llot Shower Tank Release To Dis-char.,e Canal PCN75-1701. E. Beatty pre"entcd this procedure change. Xt requested to change step 5.13 to read; "Start lau>>dry pump and recirc. tank for about 1/2 hour. Obtain a sample in a new bottle after purging the sample line for about 30 minutes. Xf the ta>>k i.s to be transferred to the B.O. Unit thc sample bottle doesn't have to bc ncw". This is to specify sampling proccdurc. Thc Commi.ttcc recommended <<pproval of this change. -177" ~ ~. il1IFv'~, Ann<<:r1 Rcport /Ill oC al.l procedure chanl,cs: (ContInucrl) 1/1/75 to 12/31/75 Inclusive PORC ITI,"M NUI IDiill: I I) I,"SCIL O'I'ION 75-1103. S-lr.h I i uid llaotc Process Gtartu PCN75-1635 75-170Ir. E. Beatty prcsentcd these procedure changes. PCN75-1635 - requested correct opclling (rr1ASTE) be made in step 5.1.2. PCN75-1704 requested to change step 5.1.8 to "after about 2 hours, open sample valve 1734 and purge the line for about 1 minute before otaining sample". This is to specify sampling porcedure. -The Committee recommended approval of these changes. -1102 P-1 Precautions Limitations and Set pints P-1 Reactor Control And Protection System PCN75-1644 PCN75-1645. E. Beatty pre-sented these procedure changes. PCN75-1644 - requested the following temporary changes for review only; 2.14.5.3.5 Level Controller (Level Compensation) 2.14.5.3.6 LC-463F 0 LC-473F Filter lag time constant 7.2 sec. Filter lag time constent 28 sec. Proportional band 4' Proportional bank 655 2.14.5.3.7 Flow compensation FC-466A 8 FC-476A Proportional band 150'~.- - Proportional band 150/u Reset. Time Constand. 30 min. - Reset Time Constant 30 min. The Corrunittee reviewed these changes. PCN75-"1645 requested several oectiong of the procedure be delct,cd. Reason for this is due to charrgc in plant characteristic.. that make it neceo..ary to adjust the proportional band arrd reset of a contro3.ler for optimum control. The Committee rcconvnendcd approval of thi change. 75-1103 M-37.3.0 Hc air Of Blcrrd S stern Va3vc FCV-11013. E. Beatty prcscntcd these procedure changes. PCN75-75-1713 - wao for review only. This PCN wn. to facilitate several'tcpo marked N.A. Tire Corrunittcc rcvicwcd tlrio rcqucot. The oecond. request wao in step 5.5.1 to include valve 360 to be clooed before opening 367. Tlrc Committee rcconuncnded approval of tlrio clrange. I 178- hh ~ h Annual, Report: //l.1 of a11 procedure changes: (Cont:Jnucd) 1/1/75 to 12/31/75 Inc 1us ivc VORC rrt:,H NIIHIII!II: nrSCRIVtTON ~5-1104 li'- h, E. Beatty present;cd thi proccdurc change for review only. This w is to faci3.itate steps marked N.A., as only stroke adjustment was performed at this time., 7'5-1105 PT-16 Auxiliar Fcedwater S stem Flow Check PCN75-1711, E. Beatty prc'ented this procedure change for review only. This was to facilitate step marked. N.A. a" MOV 4007 is being kept closed due to leakage into pump casing. The Committee reviewed this change'. ~5-1106 O-l.l Plant Heat U From Cold Shutdown To Hot Shutdown PCN75-1716. E. Beatty presented this procedure change. Xt requested to;
1) Add a ncw step 5.18 "Verify //1 seal leakoff < 0.3 GPM" as read on Fl-175 and Fl-176. r Fl-175 1A RCP < 0.3 GPM Fl-176 1B RCP < 0.3 GPM The Committee recommended approval of this change. This item XS COMPLETE.
75-1107 S-2.lA Pre-Startuv Line-Un Of Reactor Coolant Pum s PCN75-1715. E. Beatty presented this procedure change. It requested; (1) Change step 5.4.6 to read "< 0.3 GPM //1 seal leakoff f3.ow indication on RCP'S as read on Fl-175 and. Fl-176. Reason for this is the minimum flow is needed before RCP pumps are started to protect seal faces from running dry. The Committee recommended approval of'his change. 7 -13.12 GS-17.0 Accountabilit of Personnel Durin Emer,enc 'onditions ~T-outlines security force responsibilities to ensure accountability of all personnel within the protected area, during an emergency con-dition. The Committee recommended approval of'his procedure. -179" I a.uS Annual ltcI>ort: (/ll of all procedure chanpcs: (Conl'inucd) 1/1/75 I:o 12/31/75 Inclusive POIIC ITI',H NIIHB I'.It: DI'.SruI I rION L. Drodie presented the following SC procedures; I SC-1.1 Badiation Rmcr enc Procedures Gcncral Information PCN75-1 (36. SC-1.2 l,ocul. Radiation Suer rnc Procedure PCHV>-17ill. SC-1.3h ,".itc Bndiation Emcr enc (Shift Foreman h Control Boom) PCN75-1'( <2. SC-1.3C Site Badiation Emcr.enc (Non-0 eratin Personnel) PCN75-17 I 3. SC-1.3B Site Badiation Fmcr rnc (Rmcr,cnc Coordinator R Survey Center Assi necs PCN'(5-1752 SC-1.5 Evacuat,ion l'rocedure PCN75-1738. SC-l.. h Bnergenc Badiati.on Monitorin Procedure PCN75-1732. SC-1.79 Field Dct,ermination Of Io<line Or Particulat,e PCH75-1'(39; SC-1.8 Post; Accident Hnvi.ronmcntal Samnlin PCN 5-1744. SC-1.:lO Plnnnin Conduce h Pvaluation Of h Ra(latino Iencu enc Dril'3 PCN75-16 U. SC-l.ll Post Accident Be-Hntr hnd Berover Plan PCII75-1737. SC-1..12h Immediate C Lll Idiot PCN75-170 75-1733. SC-1..13 Fstimatinp Of f-Site Do" es PCN75-1748. SC-1.14A Accountabilit Of Per onnel PCN75-1734. SC-1.148 Search 8 Be cue 0 eration PCN75-1.64 E PCH75-1749. SC-1.15, In.. ect,ion Of Dner;ency E ui ment 'PCN75-1726. SC-1.16 Transfer Of Emcr,ency Surve Center To Station 13A PCN75-1.751. SC-l. Badiation Monitorin Off-Site Qurve 'll- ri D Emer,enc . Team SC-1..7R Emcrp<.ncy Badiation IIonitorin On-Site Team //9E (Blue) PcrI (5-1728. SC-1.7F Emcr cnc 'adi.ation Monitorin Off-Site P, Survey Team //9F Green PCN'(5-172< . -180" Annual Report I!11 of all procedure changes:(Continued) 1/1/75 to;12/31/75-Inclusive PORC ITEi~) NE'SI R DESCRIPTION 75-1113 SC-1.7G Emer ency Radiation Monitorin On-Site Surve Team Pi G Yellow PCN75-1730. SC-1.7)i Emer enc Radiation Monitorin Off-Site Team I/911 (Oran e) PCN75-1731. Several of these change re(tuests were to clarify the procedures and some were new procedures separating SC-1.7A into separate ones to he3.p clarify survey teams instructions. The Committee recommended approval of these changes and. new proceduresz-" 75- I M-37.3 Tem orar Re air Of Main Steam Safety Valve Flan e Leak Using Furmanite America, Inc. Process, PCN75-1760. J. Noon presented this new procedure. This procedure describes the steps necessary to facilitate a temporary repair of a Main Steam Safety Va"ve Flange Leak. The Committee recommended approval of this procedure. 75- 1512 M-37.3 Tem orar Re air Of Main Steam Safet Valve Flan e Leak Usin Furmanite America Inc. Process Valve No. PCN75-1768. L. Brodie presented. this temporary procedure change to be made permanent. Several changes were incorported, to allow for changes in method on injection sealer. The Committee recommended approval of these changes. 75-111)). M-37.39 Tem orary Renoir Of .'lain Stcam Safety 'Valve F3.an c Leak Urinr, Pnrmnnite Ncerica Xncorporatccl Prone>re 'Valve t<o. PCI)75-1772. B. Snow presented this tc)!)porary proccdurc change. This was to facilitate tcps H.h. 'd. Reason wa the repair-man wao back to continue to try and, stop additional leak. The Cot)>tt>ittee rcvicwcd this change. 75-ill.5 PT-5.20 Proc(.oo Instrumentation Rca<>tor Protection Ch(tnnc3 T! i i Tent C)>a)>ncl. 2) I'CH75-lCi71. )3. Snow pz cocttted this proccdu> c cl><<ngc. Xt rcqu(:otcd t)>c fo3.lowing ch<<ngco bc ma<le to improve cia) ity of thc proccdurc. Step 6.107 - Ch<<nncl 1 test (LE<<rttt o)>.,t>ld rend; C)>>:n>>c3. '? Loot . alar))> Stc)) 6, 100 ndd; X/C Tcc)>>>i ci ttt> Xt>i Li t>1 'I')>(e Colt>tl>ittcc r(!co)tlltl(!>)()c<l ()))))1'ovl>3. of Lltcoc c)>t>>> I'(.'o. T)>i IL('.t) 3 lI COW)'I Ill'I"". J >-1 I'I I> )If>!'>I'-3 .5, Vt>l v(! I t)l.(;) 1(>(:k V(!t I I'I <!!>I.)(>n - I"(.('<Iwt>l.(~> .'f!;olttl.f~<>>> ) <.r4(. I f>>., ))...>>.w I>t .,<.>>I.<.(I t.)>(. I<)l).ow)>>I,I I>>o<<..(I>>>c <.I>t)>>I.(::). LL't>!) rc(I>><!<<L'c<l I.o (!)>)>)>I.(! )>L(!I) C>..II Lo rctul; ")'3)tc<! I.)>(! fol.l <lwl >)I; IIt>>>(l/A>>I,o))>t>L I (: L)'tt)>:) I't!1':()t>t.)'03 l.()t't) L() LI>( It>t>>n>t)l ~ I>l>!> I I. I (t>> (MC I> j. t>>>(I > l )I>>( ~ 1 ~ >))t>>>>>t>1 t t>>>I.)'l>l setting to acro" Thio io to clarify what control io to be adjusted. The Committcc recommended approval of this change. r I t "='Annual Rc))ort: /ILL o)'11 ))roccdurc c)rr)r)I crr: (Continued) '/1/75 to 12/31/75 Inc lus ivc PORC ITI)M NI.IHIIIR'. )) I'.SCR1 O'I'10N 75-].1] 7 'P-2 . 1. 1h I:rrrcr cnc D).cs('.]. I (ncrr'ut()t'"r'()>>"tart hl.i B. Snow prc"cntcd t;)rc fo11.owing procedure char)go, liar(:rrl'CN'(5-l.'(6'(. It re(Iucstcd to c)rurrgc step 6.2.8 to rc:u(l; "Ensure the following "vit,c)res in lh )3nttery Boonr nre on (lh Muin D.C. Di't,ribut;ion Panel)" Reason for this is the switches fo) the h Die (1 Gen()abator are on tlrc lh Muirr D. C. dist,ribution panel. The Committee recommended approval of this change. 75-1118 PT-5.30 Process ] nstrumentation Reactor Protect;i.on Channel Tri Test (Channel 3) PCN75-1672 1673 I(, 16(4. I3. Snow presented the following procedure changes to improve clarity of the procedure. PT-5.30:4 - Step 6.19, Channel 2 should read. Channel 3 h Omit vord "TRIP" PT-5.30:5 Step 6.22, "goes out" should read. "CONES ON" PT-5.30:5 -,Step 6.30, T should, read hT PT-5.30.6 Step 6.35, T should read hT and add; (1.71 F; .912 MA = l)0.40 MA + .912 l~iA = 41.31 Mh). Record on data sheet. E PT-5.30:9, Step 6.54 add. "Switch T/401B, located in S.D. Hack .NOTE: Deviation alarms may occur when svitching occurs. PZ-5.30:9, Step 6.55 add "(svitch T/405F, located in B.I.L. rack)" NOTE: Deviation a1arms may occur when svitching occurs PT-5.30:13, Step 6.87 -add I/C Technician Initial PT-5.30.16, Gtdp 6.107 should read: Place feedwater by-pass valve corrtro].lcr l)CV-Ir81 to po. ition desired. I'-5.30:16, Step 6.11] acid I/O Technician Init;ial Thc Corrrrnittcc rcconrmcn(lcd rqip) oval of',l)csc change.".. 75-]1 ~0 (l.l"I'r i rill(.'I ) )'CN'(5-1.'('!5. I>. )flow ))rcacrrltccl t Ill" proccdur'c) ch(cr)gc. 1t; was rc(luc t,c: d t;o c)range 4)rc lu't::cntcncc of tcp 5.].0 t;o rend; "Alr)o note mrrtc) i(c].u und. t;heir associut;cd pu) c)ra,. e o) dcr ntvrrb(.) s ur)c(l in ) cbui].ding tlrc snubber" 'I')rin i" to mair)t;uin tznccnbility of parts fronr I))'o(:urcrncnt througlr iris)'nllution us ) ()(luircd by the Q,.C. pr'opznrn. 'Ihc () 'E f)I'()cc (Iro c l(E(lpcs: ()nt .nllc 1175 t<E 12 3175 Inc lus ivc Ol',SCI< 1.P 7 TON PT-5.40 Process Instrumentation Reactor Protection Channel Tri Test (Channel I() PCII75-1675. )3. Snow prc" ontcd the following procedure changes. It requested the following changes be made; Step 6.17 Homove word "THIP" Step 6.)E8 Add I/O Technician Initials Step 6.69 "Low-Low Logic" should be "Low Lovel Lpgic" Step 6.70 "Low-Level Logic" should read "Low-Low Logic" The Committee recommended approval of these changes. This is to clarify and update the procedure. S-12.2 0 erator Action In The Event Of Indication Of Si nificant Increase In Leakapo PCN75-165 75-1750. B. Snow presented these procedure changes; ~55-6 65 "Containment purge system status change in the last-7 days" PCN75-1750 Hequested to change step 1 to; "Chango 2)E hpurs tp )E8 )spurs" POHC recommondcQ Qisapproval of t)>cse changes. B. Snow was a signed to investig(xto t)Eis fut't)lcl . A-52.2 Con)'.rol Of Locked Valve 0 Eoration PCN75-)660. B. Snow presented tho: o )Erpc(E<iu>e chango". IL rcquosto(I;
1) AdQ locked valve //1701 to locked valve list (valve //1701 lockeQ closed) kcy number E509

2) Chango lock number E-626 on valve 1762 to E-)(73 on pago A-52.2:6 Heason for change //1 was that proccQure" call for 1701 to be locked closed. //2 is the lock t)Eat wa6s cut off due to faulty mochansim and rcplaccd by. I.'-I(73.
The Committee rocornmendcd approval of those c)uu>gcs. M-11.14 Ins ection An<1 Maintenance Of Inporsol Hand Pu(n )3. Snow presented this procedure changes; 'CN75-l/59. Change 3.2 and 3.)E as follows: 3.2 add; (Use procedure M-ll.2 for Containmcnt Spray Pump Isolation). 3.)E - If work is to be performeQ.on the Component Cooling Mater Pumps (Mod. No. 8 X l)E SD) or the Containmont Spray Pulnps (Mod. No. 4 X llA) notify Quality Control. The is to clari.fy and update the procedure. Thc Comnittco recommend('Q (mnrnvnl nf'hn~( hnilnr ~. '-183- An>>ual Rciior.'t f/11 of all proccdurc changes'(Cn>>t: J>>ucd) 1/1/75 to 12/31/75 Inclusive' PORC rrvtt NUMI3l R: DHscRzi rION 75-1130 M-11.15 In" ection E Maintenance Of Pacific Pum s PCN7>-1(56. {BHH Pump.",) B. Snow presented this procedure change. This procedure was rewritten as only "Pacific pumps are the BilR pumps". The Connnittee recommended approval of this rewrite. This item IS COMPLETE. 75-1131 M-ll.98 Isolation And Maintenance Of 18 BHB Pum PCN75-1757. B. Snow presented this procedure for deletion. Thi" procedure hao been incorporated in M-ll.15. The Committee recommended approval of this deletion. 75-1132 GS-10.0 Securit Guards Action" Durin A Radiation Emer icncy PCN75-1755. B. Snow presented these procedure changes. It requested; Add: 3.1.3 "If required, follow procedures outlined in sections 3.2.2.6; 3.2.2.7, and 3.2.2.8." 3.2.2.6 - Open emergency survey cent,er, by breaking glao in kcy box and obtaining key 3.2.0..7 >> Act.ivat,c tape recorder and test all communications equipment for operability 3.2.2.0 - Standby to operat;e comm>>>>ication cquipmcnt; ao instr>>ctcd until relieved by designated person>>cl {L'lncrgcncy Tag li'14) iBt.noon for this is to ch<<ngc guard i>>ot,r>>ctiono t,o <<I,rcc with fic-l . 75-1135 HSSP-1. 3 Valve Interlock Verificat;ion Chemical Volume And Control System PCN75-1753. B. Snow pre entcd these procedure changes. Several change were request,ed to improve step sequence, clarify locations and update format. The Committee recommended approval of these changes. 75-1136 S-26.1 Com uter Pro,ram Check PCN75-1746. B. Snow presented this procedure change. It requested in step 5.4 to change the last sentence to road; " Event Report SHALL also -" This change is to insure uniform operator compliance with procedure. The Committee reconnnended approval of this change. -184- Alllulr)1 Rcport (/11 ol: n11 lrroccdurc cire>>gcs: (Cont lrxrrcr)) 1/1/75 to 12/31/75 I ac lus ivc )'ORC 17 I H NUM)))'.R: l)l;SC)>l l'Y l()N 75-1137 S-26.2 Com uter Out-Of-Service PCN75-17)r5 rxnd PC)l75-17)r7. B. Snow presented thi" proccQure change. It was request,ed to add to Instruction "Transfer reactor coolant pump bearing temperature monitoring from computer to recorder RK-30A" also to change the worQ should to SI)ALL in step 5.2. The Committee rccorrnncnQcd approval of this change. 75-3 138 EIS-3 < hc VLir Of Din >1<ra a Valve 3C)3n ()l3 conor to Bt&V f.".elation Valve) )'(.'H'(5-1'(;! r. )). Snow prc"cnt,cd tlris proccrlure c)rrurgc. T)ris proccrlurc was put in A-30 format and mrxdc thc 2 1/2 year: review of t)rc proccdurc. T)rc Commit.tcc rccornrncndcQ approval ol'his c)uxnge. 75-1141 EM-150 Temaora Re air Of Auxiliar Feedwater S stem Manual Isolation Valve 4012 PCN-75-179 . J. Noon presented. this new procedure. This procedure describes the steps necessary to utilize the Furmanite process for sealing the water-stean leak at the body to bonnet )oint of Valve 4012. This procedure is for temporary repair of Auxiliary Feed-water System Manual Isolation Valve 4012. The Committee recommended approval of this procedure. 75-1142 PT-22 Containment Penetration Leak Testin PCN 75-17 6 D. Gent presented this procedure change. It requested steps 22.18 and 22.19 be deleted and steps 22.21 and 22.22 be added: 22.21 - Mehcanical Penetration-Manifold "L" Leakrate Test 22.22 - Fuel Transfer Flange Leakrate Test Reason for these changes are to correct error in numbering of procedure and. to expand Initial Conditions. The Committee recommended approval of these changes. 75 ll)r3 PT-22.21 Mechanical Manifold "L" Leakratc Test PCN 1764. D. Gent present,cd this new proccQure. T)ris procedure outline steps ncccs..ary to perform a lcakrate te of the t mec)ranical pcnetrations on Penetration Prc""urization System Manifold "L". This procedure i to proviQe st,eps for lcakratc test,. The Committee reconnnenQcQ approval of t)ris procedure. Pl'-22.22 Fuel Trrxnnfcr Finn;c I crxkrrxtc Tent PCN 7"-176". D. Gent prc cntcd this>>cw proc'cdurc. This procedure outline:; the steps necessary to perform a lcakratc test of thc )'ucl Transfer )'lunge pcnctration on Penetration Pressurization syotcrn manifold "L". This procerlurc is to provide steps for lcakrrxtc test. The Cormnitt,cc reconrmcndcd appr oval of i,g'eke.< Annun1 l(aport (/11 oC nl,l proc(.()ur(. chnngcs'. (ContJnuc()) 1/1/75 to 12/31/75 Inc lus ivc POI(C IYVM Nl)MIII'.R: Dl!SCRT.PTT.ON ~5-1146 8-26.1 Com uter Pro ram Chcc)c PCN 75-1775. L. Brodie presented .this procedure c)mnge. It requested to add Step 5.8.3: "Multiply value by 100/actual 5 power." Reason for this is to correct/for power reduction. The Committee recommended approval of this change. 75 ill)7 P- Precautions Limitations and Set pints P-9 Radiation Monitorin S stem PCN 75-1773. L. Brodie presented this temporary procedure change for review. It requested "tem-porary increase of setpoint on RIIS Channel 19, to 20K/background." Reason for this is to blowdown Steam Generator's during ST 75-6. The Committee reviewed. this temporary change. 75 ill>8 L. Brodie presented the following CP were requested, to update and improve existing procedures. '. Several minor changes CP-2.0 Calibration and/or Maintenance On Rod Position Indica-tion S stem PCN 75-1781. CP-2.3.0 Rod Position Indication S stem "Shutdown Bank " PCN 75-1782. CP-2.4.0 Rod, Position Indicator S stem "Part Len,th" PCN 75-1784. CP-2.5.0 Rod Position Indicntor System "Banlc A" PCN 75-1786. CP-2. 6. 0 Rod Pn..ition Indi cator S stem ")3an)c B" PCN '5-1788. CP-2.7.0 Rod Po..ition Indicator System "Hanlc C" PCN 75-1790. CP-2.8.0 Rod P< sition Indicator S stem "Bank D " PCN 7 -1( 2. The Committee rccommcndcd approval of these changes. I '('i- I I <i'( If-'>'>.>'l:>inl.<ii:iii<< l(<<<><iv(i(ii')I'(<:i<I.<ii'l<:ul ~ (!<><<I.i'<> I I <>il> I i <".:. ( i'<'f'<<r I () I'()I((! I II.((( /~'('>-.I()'I ('ll'()l("I .I lf<><>u I>i'<.::(:<<I;< ::I.-Il:(<iil.(((- ~ iiu(:<: r< v i( w. 'I'lii:: l>r(>c(:<li)rc w(u) I>( i'I'(irmi:() <>n I.O/ I.,I/'(p. ( ol>y <) I' >r, I i> ( " " r(',i>or L .)." ((( I '(('li<<' lo I I)ou('. m i nu I ( .' -186-. V/ w /7// Annual Rcport ftll oE all procedure cl)angcs: (Continued) 1/1/75 t>> 12/31/75 Inclusive POI<C ITI M NOHill!R: DIHOIST.PTTON ~1073 P.-6.1 l,a::s Of Cnm >oncnb Coolin puris~1'ower 0~ural,ion ~PCtl ('L"-G.~I .I'.. Bcn(ly prcncnt<:d thi" proccuurc cln>nnc. Il. request<<d step 4. 5 be cl)nngcd from 424 to 50u no I)-0 octpoi))t is 50/o. Thc Committee recommunQcd approval of t,hi'hange. / ~7-107h li-11.10 Mn or Ino ccl;ion Of 8crvica Vntar Pum PC((7$ -16(ip.. I". Heat/ty presented this temporary procedure change for review only. Thi: PCN wao to facilitate steps marked N.A. no thi" procedure wno used for minor inspection nnd lubrication. ,The Committee reviewed thio change. ~7-1075 M-40s2 JI Qrnulic Snubl)er Unit In" ection And He nir Procedure PCN75-167 f. E. Beatty present;ed thi procedure .change. It requested that in the NOTE under step 4.3 a spelling error be corrected from "it it" to "if it". The Committee recommended approval of this change. ~7-1076 E. Beatty presented the following M procedures for changes; M-ll.14 Ins ection 8 Maintenance Of In ersol Rand Pumos PCH75-1663 75-166 - requested to change step 3.4 to read; 3.4 Notify Quality Control for maintenance inspection on component cooling water pumps (SIT 0567-318, 319) and containment spray pumps (SN 0667 154, 155). ~75 66 - 3. seal leakage. Step 5.8 should read; "Lubricate pump bearing, per manufacturers instruction" Reason for this io not all pumps are equipped, with seals, not all bearings are oil 1>>bricnted. M-ll.17 Ins ection 8 Mnint,enance Of Weinmnn Pum s. PCN75-1664. This requested step 5.8 be chnngeQ to rend; "Lubricate pump bearing per manufacturer'o instruction Thi" io because pump bearings nre grease lubricated. M-ll.IA .Ino ection A Mnint;<<nance Of Buffalo Fo) ce Pur~).", PCN'(5-1665 zcqucotcd ..tcp 5.8 be changed to rond; Lul)ricntc pult)p bcnl lng pcr But'fnlo I"orcc Bulletin 33.l-l" Chang<< step 3.1.2 to rend; "gland lenlcngc". Thio io no bearings nrc prcnoc lubricated, glands nrc packed wit)) pnckinl,. M-1.1.19 I))o )<<etio>> k hti)into>>iu)cc of Crane -Dunt)), I'um). PCN'(5-'I fIf)f) r<<quc:)b.d otcI) 5.8 be chang<< to rend; I ubricnl'c l)ull)p l)cari))g. Pcr llu)nut net>>)rvr>> il)ot ructiollo i).~. ~ /)C ('(/.",.~.i )>>)v>>i<.i>>3) <~ 'i'b(s C'(>>ii>(ii 1,t.<w(>> (~r('>\mn<<>>dcd -175- Annual Rcport /IL1 oI." ()Ll procedure ch()nlacs: (Contin>>cd) L/1/75 to 12/3l/Z5 Inclusive')ORC ITI'.H NLIHIIIR: DI':H(iR 1:PT ION 75-1 I 50 1'"I'-15, C<>>>I.(>> nl. I'I)> ) .'l>>>>)>l v An I I'.>I><<>>()t 1 ~ n I):f>f>n< >* Cl<r.".- u) (( 'I'I>>I I'I:II Z'i-1 !iI> 'a. C. Ila)'4li(:1) p)'(.s<.nt;ed 4l)i.'. )>I; I I>>'<A-cedu>(:. TI>i:; p> oce(I>>)'(> in Lo p) ovi<Ic i>>'4ruct.ious 4n "ccu>(: ch(>r4 tr;>ceo fro>n wl>ici> closure 4)>>.c of t,l>c cnn4:)in).)c))t. pu)'g() supp]y an(<u::t. <I:u)p(r" )I::>y be obt:>in<<;1. 'LI>u Co>>>:>i,t.4ee rect.'>>1( 1>()( (L )pprovaI of t!)i" pro(.'cdu>'e. 75-13 59 l>:ese>>4(.d t!)c fol:Lowing CP I>r(7ecdure.< each onc is a proces>rc I'o)'hc calibralion of tl>e rod po.:itio)> indica-tion syst<.>> fo) diffe) <<>>I: beni:s <1u) i>>g an at power conditio: ). ',<)rl P<>>>it.io.) J))<1ic:>ta.$ on . v::te;:> ",'<ul;(!()w>>" Phan!( (>4 Pc>we) A.L >r'>>I I< )>t.. I'CH '/>-1783. CI5-2.1'.1,, I?(><1 I'o! iI,:aon 1>>al)(;at:)on qyv~'(');a Parti La<'n) ar>> )$ (>nl At I'ri'".:f'l.fr rn ".r.".II.'I: 75 ):II-I5. CP-2.5.1 Rod Pn:;;it:ion .In(iic(>tion,ivsten "A" i'an'r, At. Powe) hlirr,'rnarI .Ir.!Il 7!!-.I'18'I. CP-P.(>.1, II()<1 Pon) I.ion 1'n(1i(.:>I:io>) l>v::4<:>> "8" II(<>>I:;d. I'ow(!>'P-P.7.1 1'<7<1 I': it:ion Tn(li(:d,io>) .'lv::t.e>>'C" Ran!; At; P()w<>)':I.:i <n)>>>I()>~t. I'(!ia 7'i-:L7()1 . Cl'-...ll.'I. Ilr rl )'".i I i ni 'inlir:i'I.'irn ."~i'::triri "li" I'.:nif: 'Cl'-.".<), II(>l I'<::.i t.ion I>< ti<':>l.l<>>> "v:>I.< >I> A~ ('. t.<> I).(!. (".<>> > I 1:>l.i ('I>a < I:, I'('.ll 7'a-l7<>I>. (II ~ I < 1 1 ra fal I ~ I > I > I 1>> I >Ill <'>Ll 1 ~ > ~ iaf;: I a'Ill ~ >1 > >>I a'>><a>la'a ' '1 I > Ia >"'1 I I < 1<> (.'1>a a I:, I'<.'lI '('a- I 7al ~ . I lla'.alii>Ill> I I <'11'a'afllllffa'>>ala'ai ~ ~ <<!I!1>'aaV:> I aal Irlla'ua'1>'ala'a'<ll>>'a' ~ 75-1160 EM-151 htaintenance On Non-Re enerative Heat Exchan er Pressure Circuit For PCU-135 PCN75-1853. J. Noon pre-sented this new procedure. This procedure is for trouble-shooting the non-regenerative HX exchanger control circuit, P-135. Reason for this procedure is that PCV-135 was not operating properly in auto. -187- 1 l =' . Annual l(cpo;rt //ll of all procedure cllangca: (Cont flulcol) 1/1/75 to 12/31/75 Inc lus ivc rouC 11'I:H NIIHIII'.It: J)l',SCIt T I'I'ION 75-1165 EM-136 Maintenance of Non-Re encrative lleat Fxchan er Com onent Coolin 1A)ter Valve TCV-130 PCH 75-1851 PCN 75-1851 - L. Depcw presented these procedure changes. PCN 75-1851 - requested to add to step 5.13 "charging pump may be returned to automatic if desired" Reason for this is operator only needs to adjust IICV-123 P P to control charging pump speed. The Committee recommend-ed approval oi this change with modification. PCN 75-1852 - requested a sign-off line be added for shift foreman at the bottom of pago. The Committee reviewed this change as the line does appear on the original howcvcr did not show up after running copies 75-1168 PT-16 Auxili;ir Fccdwater S ..tcm Flow Clicck PCN 75-1841. L. Dcpcw presented th is temporary procedure change. It was rcqucs tcd Step 6. 1. 10. 1 read; "should leave MDV 4007 closed." The Committee reviewed this change. 75-1171 '-37.39 Tem orarv Rc air 0f Main Steam Valve Flan e Leak Usin Furmanite America Incor orated Process Valve No PCN 75-1836. L. Depew pr'esented this temporary procedure change. It requested stens 5.4, 5.5 and 5.6 he N.A.'d. Reason for this is furmanite per'sonnel are going to continue attempting to stop the leak. The steps maked N.A, had pre-viously been completed. The Committee reviewed this change. 75-1178 PR-4 Rela Calibration And Tri Test 4160/400 Volt Station Transformers Transformer // PCN75-1779. L. Depew presented this new procedure. This procedure is to provide instructions for calibration and maintenance of protectiveTrans-relays associated with the 4160/480 Volt Station Service formers. The Committee recommended approval of this procedure. 75-117 PR-5 Rela Calibration 4 Tri Test 4160 Volt Auxiliaries FCN75-1770. L. Depcw presented this new procedure. This procedure is to provide instructions for calibration and maintenance of protective relays associated with the 4KV Auxiliary circuits. The Committee recommended approval of this procedure. ) 1 'L' Annual I)cpurt /311 of n11 procedure clian),cs: (Conti>u<c<l) I/1/75 Lo 12/31/75 Tnc lusive PO)hC ITI I I NUMIII'.R: DI'.SCII 1)'I'10N 75-1165 EM-136 Maintenance of Non-Re enerative )I< <<t Exchanger Com onent Cool. in Mater Valve TCV-130 I'C:. 75-1851 PCN 75-1851 - L. Depew presented these procedure changes. PCN 75-1851 - requested to add to step 5.13 "charging pump may be returned to automatic if desired" I t Reason for this is operator only needs to adjust )ICV-123 to control charging pump speed. The Committee recommend-ed approval of this change with modification. PCN 75-1852 - reques'ted a sign-off line be added for shift foreman at the bottom of page. 4 The Committee reviewed this change. as the line does appear on the original however did not show up after running copies 75-1168 PT-16 Auxiliar Fcedwatcr S ..tcm Flow C)aleck PCN 75-1841.. L. Dcpcw presented this temporary proc<.dure change. It was requested Step 6.1.10.1 read; "should leave MOV 4007 closed " The Committee reviewed this change. 75-1171 M-37.39 Temnorarv Rc air Of Main Steam Valve Flan e Leak Usin Furmanite America Incor orated Process Valve No. PCN 75-1836. L. Depew presented this temporary procedure change. It requested stens 5.4, 5.5 and 5.6 he N.A.'d. Reason for this is furmanite per'sonnel are going to continue attempting to stop the leak. The steps maked N.A. had pre-viously been completed. The Committee, reviewed this change. 75-1178 PR-4 Rela Calibration And Trio Test 4160/480 Volt Station Transformers Transformer /I PCN75-1779. L. Depew presented this new procedure. This procedure is to provide instructions for calibration and maintenance of protective relays associated with the 4160/480 Volt Station Service Trans-formers. The Committee recommended approval of this procedure. 75-117 PR-5 Rela Calibration 8 Tri Test 4160 Volt Auxiliaries procedure PCN75-1778. L. Depew presented this new procedure. This is to provide instruct;ions for calibration and maintenance of protective relays associated with the 4KV Auxilia'ry circuits. The Committee recommended approval of this procedure. -189- L etA '/1/75 ~ Annr!al Report //11 of all procedure clrrr>>gco: (Conti>>ucd) Lo t12/31/75 I>>c 1urr ivc PORC ITEM NIIMIII',R: I) HSC R I I'I'.ON 75-1165 EM-136 Maintenance of Non-Re enerative i!eat Exchan er Com onent Coolin Water Valve TCV-130 PCN 75-185I PCN 75-1851 - L. Depew presented these procedure changes. PCN 75-1851 - requested to add to step 5.13 "charging pump may be returned to automatic if desired" Reason for this is operator only needs to adjust HCV-123 to control charging pump speed. The Committee recommend-ed approval of this change with modification. PCN 75-1852 - requested a sign-off line be added for shift foreman at the bottom of page. The Committee reviewed this change as the line does appear on the original howcvcr did not slrow up after running copies 75-1168 PT-16 Auvilirrr Fccdwatcr S .,tcm Flow Clrcck PCN 75-1841. L. Dcpcw presented tlris temporary procedure. change. It was requested Step 6.1.10.1 read; "slrould leave MOV 4007 closed." The Committee reviewed this change. 75-1171 M-37.39. Tern orarv Rcr!air Of lfain Steam Valve Flan e Leak Usin Furmani.te America Incor orated Process Valve No PCN 75-1836. L. Depew presented this temporary procedure change. It requested stens 5.4, 5,5 and 5.6 he N.A.'d. Reason for this is furmanite per'sonnel are going to continue attempting to stop the leak. The steps maked N.A. had pre-viously been completed. The Cormnittee reviewed this change. 75-1178 PR-Ir Rela Calibration And Tri Test I!160/Ir00 Volt Station Transformers Tran former // PCN75-177 . L. Depew presented this new procedure. This procedure is to provide instructions for calibration and maintenance of protective relays associated with the 4160/400 Volt Station this Service Trans-formers. The Committee recommenrlcd approval of procedure. PR-5 Rein Cclibrnt ion d Tri Test h160 Volt Auxilinries PCN75-1770. L. Dcpew presented this new procedure. '1'his procedure is to provide instructions for calibration and maintenance of protective relays as. ociat,ed with the 4KV Auxiliary circuits. The Connnittee recommended approval of this procedure. -].90- xnellt IUn lxnr<i L4 II ~ ~ d l Ql, dlLA Iirocr Inc lu!r f.ve POI:C ITI M N<nn',Kll: Dl',!IClkT I'I'ON 1 II-37.Ir0 Maintenance On IIotor Driven Auxiliary Feedwater Purn ., Dl!rclrar c Valve!'OV 4007 and I'IOY lr000 PCI'l75 1860 L<<Depew '" presented thi" new procedure. This procedure is to describe the steps necessary to perform maintenance of MOVIr007 or MOV4008. The Committ,ee recommended approval of this procedure wit.h modifica-tions. 1 75-110lr A-5lr. 3 Cutt,in And Wcldinp Permit PCN75-1059. L. Depcw .presented this procedure clrangc. Several changes vere requested to reflcct-the new Cutting and Welding permit. The Committ.ce recommended approval of these changes. Id-11.50 Bchurnin The 1B <donor Driven Auxili<<r Foedvnher Pum To Service After Maintenance PCN75-1862. L. Dcpew pr'esent,ed this procedure for the 2 1/2 year review. The only change requested was that Committee recommended approval of this change. it be put in A-30 format. The 75-1188 PT-5.40 Proces'nstrumentation Reactor Protection Channel Tri Test (Channel 4). PCN75-1,858. L. Depew presented this procedure change. It was requested on data sheet under transmitter number to change; Feedwater Flow/Stm FT-466 and. FT-464 to ead; "Feedwater Flow/Stm FT-.475 and FT-477 is to update the procedure. The Committee recommended 'his approva3. of this change. ~75-118< CP-2.0 Calibration And/Or Maintenance Of The Rod Position Indication System PCN75-1857. L. Depew presented this procedure change, It was requested steps 5.2 through 5.2.7 be deleted. This is because these steps for defeating the channel are covered under procedure CP-2.1. The Committee recommended approval of this change. 75-1190 PT-2.3 Safe uard Valve 0 eration PCN75-1657 75-1856. L. Depew present,ed these procedure changes; PCN75-1657 - requested that all NOTES ri ferred to in the procedure be typed out and to assign all NOTES a number sequence. PCN75-1.856 - several" changes were requested to separate ystems, number steps, add cautions and generally improve thc format of the procedure. Tire Committee recommended approval of these clranges. Annual IEcIIort I/ll of a1.1 IIroccdurc clIanl;co: (ContL<<IIcd) ~ O'L 1/1/75 to 12/31/75 lnclui'I vc ITI'.M 'OIEC NEWIII II: I>r:S( Ilrl>I >OW 5-11 1 M-60. 5 Protect i vc Bcl n. Cal i,brIition hnd TI i '1'cot .l.h incr, cnc Diesel I'CW'(5-1'(70. I. Dcpcw presented this proculurc clIangc. rcqucotcII several changes to improve instructions and I,o redesignate a" PII-2 oo that, Diesel l)claying iI included in a new "eric" of PI< procedures. The CoInInittcc rcconuncndcd approval of thcoc changes. M-60.6 Protective Rcla 'Calibration hnd Tri Tcot l.B 1",Incr cnc Diesel 1'CW7"-1771. 1 . Depcw presented this procedure change. Several changes werc rcqucoted to improve instruction" and to rc-designatc a" PB-3 so that Diesel Relaying io included in a new series of PR procedures. The Committee reconnnended approval of these change.. 75-1192 A-52.2 Control Of Locked Valve 0 eration PON75-1796. L. Dcpcw presented this procedure change. It requested valve 5763 be added to the locked. valve list. In addition it was requested that valves 5974, 5946 and 5940A under 3 Diesel, valves 5973, 5947 and 5947A under A Diesel be added. to the locked valve list. The Committee recommended approva1 of these changes with modifications. 75-1193 A-52.5 Control Of Limitin Conditions For S stem S ecifications. PCN75-1845. L. Depew presented this procedure change. It requested. to change step 3.6 to read -"IF time -" also "place plant in HOT shutdown mode",. This is to correct spelling errors. The Committee recommended approval of these changes. 75-1195 M-ll.13 Ins ection 8 Maintenance Of Goulds Pum s PCN75-1844. L. Depew presented this procedure change. It requested to change; Step 5.3 to read "uncouple or detach pump motor" Change step 5.9 to read "Lubricate pump and/or motor bearing per manufacturers instructions" Change step 5.11 to read. "recouple or assemble motor to pump This is because motors are attached differently on some models and bearings vary ao to type of lubricant. The Comnittee recommended approval. of this change. PCN75-1097 requested the same as PCN75-1044. The ComnIittce reviewed thi" PCN. -192- Alllllla1 Rcport II J. 1 of: rr 1 1 l)roc c(lure clrnrl)',l.'a 'Collt' l>>le() ) 1/1//5 L'o 12/3 1/ I5 Inc i>>a ive l'Ol)(l I'l'I'.H N)lHll)',I)r )))".H(lB T))') ON 75-3.1.96 EM-150 Tern orur Bc air Of A>>xi3.irLr )"cedwutcr S stern Manual Isolation Vrrlvc I 012 PCN75-11)35 75-3 037. L. Dcpcw presented t)rcae procedure c)rurrgea. PCN75-1037 - BequeateQ several clrrurgea to allow in,)ection of Furrnunite Compound into t)rc void between -.B3 << yoke und bonnet. wording "bonnet yoke" ulao to clrunge it to read, "deep and then continue with 3/16" diameter hole into". Tlria ia to upQute the procedure. The Committee recommended approval of these changes. 75-1200 L. Brodie presented the following SC procedures for changes; SC-1.17 Communications PCN75-1 17. It wa requested step 3.1.,4 be added to read,; "The plant P.A. system has been installed at the Emergency Survey Center to provide hard wire communications between Emergency Coordinator and Control Room" SC-1.15 Ins ection Of Emer enc E ui ment PCN75-1916. Tt requested to add a new step 2.4 to read; "Ion cleaner (defogger) for masks" SC-1.14A Accountability Of Personnel PCN75-1915. Several changes were requested to clarify responsibilities of personnel in the procedure. SC-1.12B Station Call List PCN75-1913. Several addresses and phone numbers were changed to update. the procedure. SC-1.12A Immediate Call List PCN75-1 12. Changes were made to update the call list by adding the names of additional trained personnel. SC-1.13 Estimutinr Off-Site Doses PCN75-1 14. Several changes were requested to correct typing errors und to clarify the procedure. SC-l.llA Immerlicute Be-entr PCN75-1.911. Changes were to udd u reference to the procedure to clarify some of the steps in the procedure. SC-1. In- lant Radiation Monitorin, PCN75-1.93.0. Several changes were requested to clarify t)re uac of respirator, aelf-contuined brcatlring apparatus und to uQQ u prccuution rclutive to the limiter3 uir supply of a, Scott Air Puck. SC<<1.7)) Rmer .,cncy Budiutiorr Monitorin r Off- boite ')'curn IIO)) Orrrrr c l'CN'-3 0< . Sevcrul clrurrgca werc requcatcd to c3rrrify u atep in the procedure, to eli)ninrrte r tcpa irr tire Tll'Af f fhll'f nr>'r ~ I Annu)1 Report //11 oC ol.l procedure cl>nn)res: (Con):inucd) 1/1/75 L'0 12/31/7.") Inclu"ive 1'I.'I H ORC N(IMIII'.R: D ISC R T. P'I') ON ZZ-1200 (Cuir.. ) SC-li 7() e l."mer Pcnc Bad) ation Monitorin 0>>-Site Survc Team //9('i Yc3.low )'roccdurc P(.'N75-1~ 00. Several changere werc request,cd to clarify some 'tops in the proccdurc and to correct. typing errors. SC-l..7F Emcr enc Radiation Monitorin; OCf'-Site PCN75-1 07. Several changes were requested to clarify some steps in thc procedure and to correct typing errors. SC-1. H Emer .cnc Radiation Monitorin On-Gite Survc Team // E ( Blue) Procedure PCN75-1 06. Several changes and aQditions were requested to clarify the procedure and to correct typing errors. SC-1.7D Emer enc Radiation Monitorin Off-Site Surve Team // D ReQ) PCN75-1905. Several changes were requested to clarii'y the procedure and to correct typing errors. SC-1.7B Determination Of Iodine Or Particulate PCN75-1904. This requested to add. a new step 3. . .1 to add. conversion calculations for thyroid dose. 20-1.7A Rmer encr Radiation Monitorin Procedure ~75->> SC-1.7A procedure series, SC-1.3C Site Radiation Emergenc (Non-Oneratin Personnel) PCN75-1902. This requested a new step be added to allow the Office Supervisor to obtain tag 14 out of order. SC-1.3 Site Radiation Emer enc (Emer enc Coordinator I); Surve Center Assi nees , This procedure was rewritten to clarify tag assignments and Emergency Coordinators res-ponsibilities. This request was approved with modifications. SC-1.3A Site Radiation Emer enc (Shift Foreman And Control Room) PCN75-1 00. Several changes were requested to make filling out of plant status easier and with less confusion. SC-'.2 Local Radiation Emer encv Procedure PCN75-1899. This request was to correct, a spelling error in step 3.2.4b. The Committee recommended approval of all these changes. 75-1201 M-38.1 Diesel Fire Pum Enpine Isolation For Maintenance AnQ In.. ection P(,N75-1922. D. )Iamclznk presented this new procedure. This procedure i" for isolation of diesel fire pump engine for maintenance and inspection. The Committee recommended approval of this procedure. 75-1202 3.1, M-63 1 r.ontninment Recirculation Fan Cooler Unit Maintenance, PCN7'-1(3 23. D. lla)nelxnk pre u)ted thz ncw procedure. Thx procedure is to provide thc steps necessary for maint, na the )e contain)ncnt gccirc-fan-cooler units. The Co)nmittce reconnnended " V"~ Annu<r1 Report r'll). oC n11 )rrocc<lrrrc circa),crr '(Continu<<.)) . 1/1/75 l:o 12/31./15 T.nc lu:: lvc I'U)M 'OI<C N()hf)t) R: D),"S(ll( I )')'() N 75-3.203 BSSP1.2 Valve Interlock Verification - Snfet In ection S tcm PCN75-1.075, L. Depew presented. this procedure chnngc. D; re-queateQ after step 2.4, Valve Traveling after step 2. 4, Valve 'i'ra.veling red light, to ada 7MOV 625n an6 2 exhibits a red light only). This is to make a proceQurnl correction. The Committee recommended approval of this change. I ~7-l 206 S-3.6 Auxiliary Buildin Heat Tracin S stem 0 cration PCN75-1095. L. Depew present,ed this procedure change. Several change were made to provide information for breaker numbers for respective heat tracing circuits and to incorporate information from OSO-7)r-4. The Committee recommenrlcd approval of these changes. 75-1207 Annunciator H-21 PCN75-1855. L. Depew presented this procedure change. It was requested to change the alarm points on H-21 Cond. Hotwell level to Hi ~32" and. Lo ~18". The Committee recommended. Qisapproval of this change as this could not be done because the alarm setpoints are not ad) ustable. 75-1200 T-36.1 Station Service Mater-Header Valve Ali nment For Two Loo 0 eration. PCN75-1898. L. Depew presented this procedure change. Several changes were requested. to add valves and improve and correct nomenclature. The Committee recommended approval of these changes. 75-1216 PT-16 Auxiliary Feedwater Pum Flow Check PCN75-1918. L- Depew presented this procedure change for review 'only. It was requested step 6.lelO.X be marked N.A. Reason for this is the valve is being maintained closed due to back leakage through the check valve. The Committee reviewed this change. 75-1217 SC-l. 7C Monitorin Site Radiation Level )) ITD PCN75-3921.. L. Depew presented this procedure change. It was requested to replace the old mnp with a new updated one which is clearer and has correct TLD station numbers. The Corrrmittee recommended approval of this chango. 75-1210 M-43.0, Steam Generator Mninterrancc Test; An(1 Rcnnir Pzocedur<a PCN75-1710. L. Dcpcw present.cd thi s procedure c)>ange. It requested to ndQ na Appendix I to t)rc procedure a table of specific surveillance dutie for t)rc )).P. Technician nnd Job Foreman. Thiia vill provide better mrr>>ngement .,urvcill.ance controls for thc steam generator inapectio>> procedure. The Conunittcc rcconuucnded approval of this change. 220 ).'-C>.1 Ion.. Of Com ion<.nt Coolin ~ Durirr Power 0 crntion ~5-! "!'ns step 1.4 be dclci,cd na alarm ia re<ducat,cd on) norrnn3.ly. Thc Cornmittcc recormucn<lcd npprovnl of this delctrion. I ~5-l 221 P- Precautions Limitations AnQ Set, ointa P<<9 Bnrlintion Monitorin ~ S .,tom "PCN75-1002. I.. Dcpew preacn c<l thi" procedure chnngc. Xt re<guested R-4 nlnrra setpoint be ch ngc to 15+Mr/hr to provide n morc practical setting.i t The Cor ittcc zecommcn<lcd approval of this change.' 'is&~ I Annual Rcport //ll ol nil procedure changes: (Cvntknucd) 1/1/75 t:o 12/31/75 Inclusive l)OI(C I'1.'IM NiiHIii'.R: I Di',HCR P'i'ION 75-1222 PT-15 Containmcnt Pur e Su 1 And Exhaust Dam cr Clo ure Time PCN75-1076 PCN75-1001. L. Depcw presented these procedure changes. PCN75-1876 requested;
1) Add step 6.1.1 Open Containment Depressurization valves and verify containment pressure on PI-944 at MCB is equal to 0 p"ig.

2) Add new step 6.7.7 ao follows:
6.7.7 - Close Containment Depresourization valves
3) Change existing step 6.7.7 to step 6.7.8 Reason for these changes are to ensure no flow out of containment through open purge supply and exhaust valves.
PCN75-1881 requested;
1) Add new steps 6.4.2.1, 6.5.2.1, 6.6.2.1 and 6.7.2.1 as follow-':
"Connect input leads of a third channel of trace recorder ncrosn dnmners rnd indicnt'ing light.
2) Chongc steps 6.4.5, 6.5.5, 6.6.5 and 6.7.5 from (green light on) to (RED LIGliT OUT)

3) Change step." 6.4.1, 6.5.1, 6.6.1 and 6.7.1 oo that word" (wire
//PIP....etc.) follow words ......control switch Reason for these changes are to add additional monitoring and correct method of connection. The Connnittcc rcconnnendcd approval of these changes. 75-1225 BQSP-2.7 Safet In ection Se uence Timers Train A Ec 8 PCN75-1926. L. Depcw presented these procedure changes. Several changes were requested to incorporate Test Control, clarify steps and add data sheet . The Corrnnittee recommended approvol of these changes. 75-1226 M-ll.ll In.". ection hnd Maintenance Of Crane Chem um .; Scric G ~5->>9 step 3.4 be changed to read; "Q.C. should be notified if it io a Boric Acid Pump" This io to clarify applicability to Q.A. components. The Committee reconnncndcd approval of this change. -196" si s\ I Ann((ol R()I)nrt //11 ol.'11 I)rocc()urc cli()nI;co (Co(lbinuc()) 1/1/75 Lo l.2/31/75 Inclu 'ivc ))OIIC 1'I.'I H NIIHIII'.lI: I)I7HCI).T I)'I' OI I 75-1222 PT-15 Containment Pur e Su 1 And Exhaust Dam cr Clo ure Time PCN75-1076 PCN75-1001. L. Depcw presented these procedure changes. PCN75-1876 requested;
1) Add step 6.1.1 - Open Containment Depressurization valves and. verify containment pressure on PX-944 at MCB is equal to 0 poig.

2) Add new step 6.7.7 ao follows:
6.7.7 Close Containment Depresourization valves
3) Change existing step 6.7.7 to step 6.7.8 Reason for these changes are to ensure no flow out of containment through open purge supply and exhaust valves.
PCN75-1881 - requested;
1) Add new steps 6.4.2.1, 6.5.2.1, 6.6.2.1 and 6.7.2.1 as follows:
I "Connect input, leads of a. third channel of trace recorder ncross dnmpers red indicnting light
2) Change steps 6.4.5, 6.5.5, 6.6.5'and 6.7.5 from (green light on) to (RED LIG)IT OUT)

3) Change steps 6.4.1, 6.5.1, 6.6.1 and 6.7.1 oo tha4 word" (wire
//PVP....etc.) follow words ......control owitch ...... Rcaoon for these chongcs are to add additional monitoring and correct method of connection. The Colmnitt,cc rcconnnendcd approval of these chang(.o. 75 1225 RSSP-2.7 Safet Tn ection Se uence Timers Train A 8 B PCN75-1926. L. Depcw present.cQ these procedure changes. Several changes were reque teQ to incorporate Test Control, clarify steps and add data sheets. The Connnittee recommended approval of these changes. 75-1226 M-ll.ll ection Maintenance Of Crane Scric" ~5->>9.Xno AnQ Chc>n umno G step 3.4 bc changed to read; "Q.C. should be notified if it is a Boric Acid Pump" This io to clarify applicability to Q.A. components. The Committee recnnnncndcd approval of this change. -196" Annual Report //11 of. ()11 proccdurc cl)<)<<f,cs: (C<)<<tlnuc(l) 1/1/75 to 12/31/75 I<<clusivc POIIC O'I M IIIIIIIIIIII: I)rSCRII rlON L. Dcpcv presented the following ncv CP proccdurco; ~CP-2C .I.Cnlibrntio.n of I".burlino Model PIIC-bB I C'II75 1-677. This i" <o describe the steps ncccoonry to calibrate thc portol monitor tfodcl PMC-40. CP-20 .2 Cnlibrat,ion of Trace)lnb Madel PPM-0 Po)tnl Monitor PCN75-1870. This io to describe the steps nccco nry to calibrate thc Trnccrlab Model PPM-8 portal monitor. CP-20 .3 Calibration Of. Ebcrlinc hfodcl llFM-3 Ilnnd And Foot Monitor 'PCN75-187 . This procedure io to dc cribc the steps necessary to calibrate the Eberline Model llFM-3 lland And Foot Monitor. CP-20 .4 Calibration of Nuclear Men uremcnts Cornoration Portable Air Monitor PCN75-1880. This procedure is to describe the steps necessary to calibrate NMC Portable Air Monitor. The Committee recommended approval of these procedures. 75-1230 S-2.1 Reactor Coolant Pum 0 erntion PCN75-1714. L. Depcv presented this procedure change. Zt requested to add nev step 9 on. "B" Initial Condition to read; "Reactor Coolant Pumps //1 seal leakoff flow 0.3 gpm as rend on Fl-175 and Fl-176" Procedure vas also rewritten to conform to A-30 format. The Committee recommended. approval of these changes. 75-1232 S- F Transfcrrin S ent Fuel Pit Transfer Canal To The CVCS Holdu Tnnk Isa te Holdu Tank Or Monitor Tanks PCN75-1932. L. Depev presented this procedure chnnge. valve number in atop 5.2.3 from 1794 to ~17 5G. Tbe Contnittee It requested to change recommended approval of this change. 1233'- 75 S-9E, Draining Storn e Tn))k S cnt Fuel PCN 7> 1933. Pit Transfer Canal Too Refuel' c uc in'tcr M t L. DQ p ev p r cse>>tcd thxs proccdurc change re(luco 'Qd in step 5. to change valve number 1794 to 179"0 ypxng error, Thi" canal" should rend I canal '. The )e Commxttcc C rccommendcd npprovnl of this change. 75- 1237 P-9 I'rccnutio<<s l,imitations an<1 Sct )oints 'n s I'-- 9 R()(l).at.z<)<<Moni.to). i<< ~ S stem PCN 7S-" l9?0. l 9?0. L. I)cpc'i4 ) prcsc<<tccl thi s temporary procc(lure cl) an gQ for rcvicv only. It requested: 2.2.2 ' ella)) fec 5)l)ll/lion1. to 2)ill(/I)oui 2.3.2e4 el)ange 3 X 10 3 cpm to 1 X 10 cpm -197" I Annual Rcport I/11 of nil procedure clrn>>gco: (Contlrrucd) 1/1/75 to,12/31/75 Inclusive PORC ITI'2i NIIHIII!II: DESCRY> >> r ION I 75-1238 HM-152 Re air of Main Steam Insolation or Check Valve Cover Gasket Leak IIsin "Furmonite Process" PCN 75-1969. D. Hamelink presented this new procedure along with the safety analysis on EI& 1430. This procedure describes the steps necessary for using "Furmanite" to seal steam leaks on the main steam line isolation valves cover gaskets and the main steam line check valve cover gaskets. The Committee performed the Safety Evaluation and found Lhat this does not involve an unreviewed safety question and that Technical Specifications are not affected. The Committee recommended approval of this procedure. 75-1241 B. Snow presented'the following procedures for reviev only; PT-16 Auxiliary Feedwnter S stem Flow Check PCN75-1971 requesteQ step 6.1.10.1 be N,A.'d because the valve is being maintained closed due to leakage through check valve 4009 back to pump casing. PT-)2.1 Dncr cnc Diesel Generator 1A PCN75-1 0 was to facilitate steps N.A.'d. M-3 .3 Tcm orar Re air Of Main Stcam Safet Valve Flan e Leak Uoin Yurmanite America Inc. Process Valve No. ~T,- 7 7.1 7.6 " .1. to allow Furmanite personnel to continue attempts to stop the leak. The Conunittee reviewed these changes. This item IH COMPLETE. 75-1242 E-33 Quadrant Power Tilt PCN75-1646. B. Snov presented this procedure for 30 month reviev. Several changes were requested to comply with Technical Specifications and A-30 format. The Conunittee recommended approval of these changes. 75-1244 B. Snov presented the following procedures. for deletion; M-60.5 Protective Relay Calibration 8 Tri Test (1A Diesel), PCN75-195Ir. This procedure hao been replaced vith PR-2. M-60.6 ~7'-. Protective Relay Calibration 6'. ' 5 '-7. Tri Test (lB Diesel) M-22 Securin, F Restorin To Service the N< Su 1 Sy.,tern For Maintenance PCN75-1956. This proceQure vao replaced with S-4.2.11. M-2II Waste Condensate Poliohin Demincralizcr 8 Be"..in Re laccmcnt PCN75-).957. This procedure wao replaccQ vith S-4.5.2. A-2.10.1 Partial Flux Ma s,Uoin Com nrtcr PCN75-1940. r A-2.10.2 Partial Flrrx Ma With Com utci Out Of Service I'CN 5-1941. TIrcoe vere s cquc: ted to be deleted ao partial flux nrapo are>>o lohgcr %1m Par) Annual Rc)7nrt (/11 o).'11 )7r(7cc(lure c)7nn)t('.s: (Coal.lnuc()) 1/1/75 t(7 12/31//5 I>>c lus 1vc ))I'.SCI) TPl'JON ~a-l,'?I>5 M-11.5)I Rcmovin Th(. 1A Motor Dri.vcn Auxi.liar Feed Pum From Service For Mu'i.ntcnancc PCN75-1953. B. Snow presented this temporary proccdurc c)iungc to be mu(le permanent. It, wns requested st,cp 5.4 be change'o rcud; "))old shut vulve 4357" The Commii,l()c recommcn()cd approval of this change with modifications. \ ~75-124 M-ll.13 In" ccti.on And Mnintcnunce Of Goulds Pum " PCN7.l-l 66. B. Snow presented these procedure changes. There were four changes reque ted, the first three change requests were done previously in a PCN, therefore, the Committee disapproved these. The fourth request was to add a step between 5.10 and 5.11 to read; add a "verify proper shift formemun motor sign rotatation, off line. if necessary" and to The Committee recommended. approval of these changes. 75-1248 B. Snow presented the following procedures which were requested to be redesignated; A-2.2 1/M Curves PCN75-1 43 to 0-1.2.1 A-2.4.2 Cold Shutdown Boron Concentration Calculation PCN75-1947 to 0-2.2.1. A-2.4 Critical Rod Position Calculation PCN75-1 45 to O-l".2.2. A-2.4.1 1)ot- Xenon Free Shutdown Mar in Calculation PCN(5-1 46 to 0-3.1. A-2. Reactivit Chan es PCN75-1 50 to 0-6.5. A-2. Correctin Measured Boron Concentration To Reference Full Power Ex ected Boron Concentration PCN75-1 48 to 0-6.6. The Committee recommended approval of these changes. ~75 121> B. Snow presented the following procedures for deletion; A-2.2 I/M Curves PCN75-1958 re laced with 0-1.2;l. A-2. I Calculation of Critical Rod Position PCN75-1960 rc laced bv 0-1.2.2. h-2. <.1 C<>lo>>1<>tion Of llot: Xenon I'reo NI>et<le><n lier in I>CN75-19I>I. rc laced bv 0-3.1. A-2. I.2 Calcu.'lat'ion of Cold S)>utdown Boron Concentration 1'CN75-1962 rc >lac(.(I bv 0-2.2.1. A-2.5 Co(pectin; M(.us>>rc(1 ))nron Conccntrati.on to Reference Fu13 Pouer~nx ><.<tuQ Iloron Co>>e<>>or<><.ion I'I.'N75-'.I963 >o >1<>eeu 1>r O-Ci.f>. A-2.( C)uu7 cn ln )Icactivity )'CN'(5-1( 75 rc 1ncc(l b 0-6.5. Thc Committee rccomm()ndcd upprovnl of'hese dclctions. -199- Annual R<'.port f/11 of n11 procedure chnngcs '(Cont Ln<<c!l) , 1/1/75 to 12/31/75 -Inclusive PORC ITI:M N VMlllR: Dl.hCRIP l JON ~5-1>> 51. A-54.3 Cuttin And Meldin Permit PCN75-1 68. B. Snow presented ~ ~ this proccdurc change. Vpon review of thc proccQurc quested to add to step 3.2.5; it was re- "The Control Room vill be notified. of the area whore burning and welding permits have been issued prior to the gob commencing." The Committee recommended approval of this addition. EM-153 Service >later Pum 1A Breaker Auto-Close Circuit Check PCN75-1994. D. Gent presented this new procedure which describes the steps necessary for checking the continuity and proper operation of the Service >later Pump 1A Breaker Auto-Close Circuit. The Committee recommended approval of the procedure. j~r'-1P." 6 B. Snow presented these two procedure" for the same changes. 0-1.2 Plant From llot Shutdown To Stead Road PCN 7 -1 52. 0-2.2 Plant Shutdown From llot Shutdown To Cold ShutQown PCN75-1 51. The chango requested that the Reference in each of the above procedure be changed from A-2.4 to 0-1.2,2. This is to update the procedure. The Commi:ttec recommended approval of this change. This item TS COMPI,I",ir. T 5-1'.">7 B. Snow presented thc following changes to be maQe in the following proceQures; PT-6.3.1 Power Han c Nuclear I!!strumcntation 5 .,tern Channel 41, ~T5- M. . PT-6.3.2 Power Han e Nuclear Instrumentation S stem Channel 42, ~7'- ll". ~IIC. PT-6.3.3 Power Han e Nuclear Znstrumcntation S st<<m Channel 43, PT-6.3.4 Power Han c Nuclear Xn. trumcntation S ..tcm Channel 44, Several changes werc made to the procedures to improve data collection and clarify .,tcps. The Committee recommended approval of these chango".'200- / I Jl I I I Annun1 Rcport I/11 of nil procedure clinnI;ca: I,'Continued) 1/1/75 to, 12/31/75 Inclusive POICC XYI II NUI IIII',II: Df hCIITI'I'TON +l-l ."8 SM75-7.21 IlYAC Backfits PCN75-l. 78. B. Snow presented thi" procedure for the following changes; Step 2,1.3 Delete this reference. Stops 2.1.11 Chango 54 shts. to shts. 1 5, 2. Steps 2.1.12, 2.2.7, 0 2.3.7 change shts. 0-4 to 0-6, add new reference 2.5 Specification 214 "IIVAC Backfits". The reasons for these changes are due to drawing changes and previous omittals. The Committee recommended approval of these changes. '~5-l2 "ig S-3.1E lA Boric Acid Stora e Tank I olation/Restoration PCN75-1 7 This was redesignation of M-12A into S series. S-3.1P 1B Boric Acid Sto' e Tank Xsolat-'on, PC~N75-1 Sl. This was redesignation of M-12B into S series. S-4.5.3 Boric Acid Eva orator Condensate Demineralizer. Re.-in Re lacement PNC75-1 83. This was redesignation of M-2F into S series. B. Snow presented the above procedure changes. The Committee recommended approval of these changes. 75-1260 B. Snow presented the following procedures for deletion; M-12h Isolation/Rostorin 1A Boric Acid Stora o Tank PCN75-1 80, replaced by S-3.1E. M-12B Isolation/Restorin, lB Boric Acid Stora.e Tank PCN75-l. 82, rcplaccd by 8-3.11'. M-2F Resin He incr.mont Proccdu> c Boric Acid Eva iorator Condrnsnte Deminexalizor PCN75-1984, replaced by S-4.5.3. The Committee rcconnncndcd approval. of these delot.iona. M32.1 DB-2 DB- 0 ld DB-7 Circuit Breaker IIaintonancc 0 Ovcrcurrcnt Tri Device Test hnd/Or Be l.acemont Procedure PCN75-1 2. H. Snow presented'this procedure change. It requested to chango stop 5.19 number from 63.23 to 60.23. This is to correct a typing error. s The Committee recommended approval of this change. M-11.4.2 I.,olation of lB Chan in Pum for Maint. and Rontorin to Service After Maintenance PCN 5-2022. L. Depow presented this procedure change. It re<guested to delete step 5.1.10 and add steps 5.1.10 thru 5.1e14 to the procedure. Reason for this change is to allow weld repair on drain line. The Connnittoe x.ecommonded approval of this change. -201- Annual Report all.1 of a).1 procedure clisu),es: (Cont)nues) 1/1/75 to 12/31/75 Inc lus ive PORC ITIH N) IM13 I'.R: D I HCR I O'I') ON 7 ~126 RHSP 2.2 Diesel Generator Load ~7-requested And Safepuard Se uence to make changes to "Diesel Generator Load, and Safe-Test guard Sequence Test" procedure to make general improvements for clarity and typing corrections. The Committee recommended approval of these changes with modifications. l 7 ~1272 S-)I.lL Reverse Osmosis Unit Startu and Shutdown PCN75-2027. L. Depcw presented thc following procedure changes; Xnscrt a new step: 5.15.5; Before proceeding to restore valve alignment to isolate the Laundry tank flow path to the H.O. unit feeQ tank, place tl>e selector switch to Manual to prevent inadvertant start of thc Laundry pump against a dead head. The reason for this is to save the pump. Mith I).0. feed tank being less than 60$ anQ Laundry tanlc greaser than 10$ , thc pump it will start on auto, and would be unwise to have sy tern isolated. The Committee recommended approval of the chango". ~7-1273 SM - .21 Core Drillin For MCC For Standb Auxiliar Feedwater Pum PCH75-2003. L. Depew presented the following procedure chamges; Change Hefcrences 1 Drawing //DMD D-281-013 Detail B. Under Instructions l., Change the drawing number to D281-013. The drawing change is by GAX and the procedure change is by NUCAM. The Committee recommended approval of these changes. EM-152 Be air of Main Steam Isolation or Check Valve Cover Gasket Leak U"inp "Furmanitc" nrocess. L. Depew presented the following changes; PCN75-2001 requested to; Change: Step 5.8 to Step 5.11 Add: Stop 5. 8: "Drill 5/16" 1)oles CentcrcQ Between The Studs > As Necessary" AQQ,: Step 5.9; "Tap 5/16" ))o1es and In ta13. Adaptor Shutof fs" AQQ: Step 5.10; "In)cct Furmanite Compound Into Nozzlcs Around the Joint" Thc reason for t)>cse changes is to allow more sealant to be in)ected into )oint. -202- Annun1 Rcltnrt Itl1 of n11 procedure changes: (Cont Jnuc~l) 1/1/7j'(:o 12/31/75 Inclusive PORC TTl M NljMlsl'.l Dl SCl(TltYTON 75-1274 Step 4.6 - change 3/16" to 1/8" Step 5.2 - change 3/16" to 1/8" NOTE: Size change has been verbally approved. by J. llutton who performed original Safety analysi reason for these 'changes is to reduce steam leaking thru drilled. holes. The Committee recommended approval of these '~1~27'heS-lh changes. Hi h Reactor Coolunt nctivit PCN75-2000. L. Depew presented thi" procedure chango. '1'his procedu re 'is to change units in 1.1 from 20 Mc. pcr gram to 2.0 pci pcr gram because thc units shown indicate Millicuric., in place of Microcurie.",. The Committee recommended approval of this change. Ql-12~ PT-2.3 Sai'e card Valve 0 erat,ion PCN 5-1 5. L. Depew presented this procedure change to add sign ofi'ine to stop 6.17.7. This is to provide step for sign-off. The Committee recommended approval of this change. HSGP-3 Verification of Emer cnc . Start Lo ic For Auxilia Feedwater Pum s PCH75-2018. L. Depew presented these procedure changes. It requested to make changes to procedure "Verification of Emergency Start Logic Auxiliary Feedwater " for correction of typing errors and general clean up of Pump procedure to add valve numbers and equipment locations. The Committee recommended approval of these changes with modifica-tions. 75-1279 P-8 Precautions Limitations and Set pints P-8 Haste Dis osal ~Secern. L. Depew presented the following changes; ~T 6 P-8 Step 2.20.23 PICA-1025 Vent header Pressure 0.5-15 psig Hi ALM 1025A 2.0 psig Low ALM 1025A .5 psig Hi control 10258 1.8 psig Low control 10258 1.2 psig The reason for this is to update P-8 to system design. PCN75-2008 requested; To incorporute Operation Standing Order E-73.44 to this* procedure. The Committee recommended approval of these changes. -203- Annual Rcport: //11 ol'11 procedure changes: (Continued) 1/1/75 to, 12/31/75 Inclusive PORC ITL'M N NMI)I'.R: nrSCRT>>'rrON I 0-6.8 Lo iin MYAH Electrical nnd Tie Line Hcndinvo PCN75-2006. L. Depcw presented this ncw procedure. This io to provide a procedure on Station 13 MVAH Headings,Qaily electrical log, nnQ tie line readings. The Committee recommended approval of this change. ~7>-'12 p 0-6.7 Weekl Alarm Status Check PCN75-2021. L. Depcw present,cd this ncw procedure to provide a mean" of mnintaining a status of nlarmo, nnd to provide a menno of determining if proper ond timely actions are being .tnken to correct t,he alarm conQitiono. The Committee recommended approval of procedure. ~-1VB~i SC-2 Site Contin enc Plan Sc-2 Adverse Weather Emer enc Plan PCN7"-2010. L. Depcw pre ented thi" procedure change, adding what to Qo with wind below 40 mph. but greater thun 25 mph. The Committee recommended. approval of this change with modificationo. 75-1286. E-4 Station Blackout 0 eration PCN7 -2011., L. Depew presented this procedure change. Xt wns requested to incorporate Operation Standing Order G-73-28 to this procedure. The Committee recommendeQ approval of this change. 75-lv87 L. Depew presented the following' procedures for the same chnngeo; Emer enc Diesel Generator 1B PCN75-2032. Emer enc Diesel Generator 1A PCN75-2033. Both PCN's requested additions to the procedure data sheet incorporating approximate values. The Committee recoriunended approval of these changes. 75-1288 L. Depew presented the following 2 procedures for the same changes; N.X.S. Xntermcdinte Ran c Channels PCN75-2030. Source Han e Nuclear Instrumentation S stem PCN75-2031. Both PCN requests are to ndd thc Channel numbers ~on both the t,itle sheet and data sheet. The Coimnittee recommended approval of the e chnngeo. 75 1290 T4- 0 eratin. Xnotructiono 'l'-4 Main 1 crdwnter P>on 0 oration, '"7'tanding Order G. 73-52 to this procedure. The Cononitt;ec recommended npproval of these changes. M-11.3 Waste Evn oriiLor 1'red Tank Pum > Hc placement PCN75-2036. L. Depew presented duhio proccdu're to dcocribc thc ioolnt;ion nnd replacement of'he Peed Tanlc Pump. Thc Committee recoimncndcd approval of'hese change" wit;h modifications. -204- Annual Report: /ill of all procedure changes: (Cont:inucd) 1/I/75 to l2/3l/75 Inc lus ive PORC ITEN NUMB t':R: DJ SCRIPTION 7-124 SC-1 Site Contin cncv Plan SC-1 Radiation Emer enc Plan FCN75-1936 PCN75-2038. L. Depew presented the following procedure changes: ~7 >>6 Item 8.0, 2nd Paragraph delete words "... the severity of the occurrence was..." and replace with the following: "off-site consequences of the occurrence were" The reason for this change is to eliminate the need. for USNHC concurrence in cases where only fire department or ambulance first aid were called to provide support. ~6-experience 66 of recent drill.) The Committee recommended. approval of these changes.='~6-'12 M-ll.ll Crane Chem um s Series G Ins ection and Maintenance, 1 PCN75-2035. L. Depew presented this procedure change to provide for isolation of pump. The Committee recommended. approval of this change. =-, I 75-1295. M-li .~M Ins ection of. Safe uard Motor for lA Service Mater Fumi FCN75-2068. L. Depcw pr csented this procedure change for review only. This PCN was to facilitate . the steps marked NA because they werc not required. to uncouple the pump. The procedure was used to check the pump and, motor for-free roll and to check the thrust bearing rotor assembly. '"the Committee reviewed this 'P>-)!01 change.,'S-10.0 Securit Guard Actions Duri'n A Radia ' PCN75-2064. L. Depew presented the following procedure changes; 3.1.4 delete word "film" to read "retain th ear ' 3.2.2.1 - same ad ges add: 3. 3.8-- Be-entry to the site following a site evacuation shall be in accordance with existing entry procce d ure. 3.8.1-- Personnel who have retained their badges, as instr'ucted, must show their badge to security personnel upon re-entry. r The reason for these changes is to satisfy ~ 75-7: f >>71:TS finding 3. The Committee recommended AFCAR au d 3. t changes. This item IS COMPLETE. approval of these 7)y-'[ )or~ GS-21.0 Access Control (Securit ) And Personnel I.D. PCN75-206 5 L. Depew presented. thzs procedure change. requested that step 3.1.3.6 be changed, to read., It Visitors shall be escorted,, except for the top fl ervxce uilding and the office area in the warehouse f th normal working hours. During off-hours an during for all areas. escort is recD>ired The rea on for this procedure change security pcr request of operating per isonncl. to improve off-hour The Committee recommended approval of thi. change. ~ ) hrrn<rrrl R<rport //11 <!f rr11 procedure clrrrnI,'es: (C<>nl:irr<red) 1/1/75 L<> 12/31/75 l>>c lu" ive POII C I'I'I'.M Ntlkfill'.ll:r DI'.SCIL TO'I'()H ry- noh 0$ -31.0 Door Alarm Ii "t<:m PCH7"-20I!3. L. Dcp<;w prese>>tcd this procedure change by addir!g a ncw "tcp 3.4.1.2 to read; Corn.!unication is e.,tablislred between alarm ccntcrs by act,ivating alarm point //30 <<nd //31. Point //30 is activated by pushing the "Acknowledge" button on the printer panel of the master unit. This butto!r should be Qeprc 'cd until point //30 activates ((2 ec.) The Security force activateo Point //31 from the guerQ house in the same manner. The reason for this change is to meet requiremcrrts of Regulatory guide 1.17. The Committee recommcndcQ approval of this change. 'l5- f305 0-6.3 Maximum Unit Power PCN75-1944. As a result of a Q.A. audit, L. Depcw presented. this procedu're change for Redesigna-tion of A-2.3 Maximum Unit Power to 0-6.3. The Committee recommended approval of this procedure change. 75-1306 0-6.4 Core Quadrant Power Tilt Calculation PCN75-1 Ii<). As a result of a Q.A. audit, L. Depew presented this procedure change for redesignation of A-2.7, Core Quadrant Tilt Calculation, to 0-6.4. The Convnittee recommended approval of this procedure change. 'l5-I 30T L. Depcw presented the following procedures for deletion: A-2.3 Maximum Unit Power PCN75-1 59. It has been rede ignated 0-6.3. A-2.7 "Calculating Core Quadrant Power Til.t". PCN75-1961r. It has been redesignated 0-6.4. The Convnittee recommended approval of tlrcse Qelctions. 75-iaido S-12.4 RCS Leaka e Srrrveillance Record Instructions PCH75-2016. L. Depew present,ed tlris new procedure to provide instruction for the usc of the reactor coolar!t system leakage survcillar!ce record form 1!9-61 anQ to ensure proper leak rate docurnenI;ation. The Convnittee recommended approval of this new procedure. 7~a= Iso -6. ho 1)epew prcscrlt<<.' I hin ncw I>r'oceQ!rr'e lo descril>e tire oper<<t;Jnl; limit;" for'irrr!a Str<tion Tr rrnnrni>>.r:i or! Cir cuil'" <elor'IK)l'<LLc Opernliorr St;nn<ling Order 1).73-55 into tire new procedure. Tire Convnil,1.c<<r<<cor!vnc>>ded appr ovr<1 of t.lre rlcw pl'occdrl!'e. -206- AnllU(jl Rcport: /ill ok o).1 prove()(<rv el<an);vs: (Co>>(:I.>>((c()) 1/1/75 I.'o 12I31I 75 ):>>c 1(<s 1vc PORC TTI,"hl Nl IHIII'.R: I) I'.ll(lR T O'I' ON \ SC ].]O pl)n)))I)) Ccn<jll< I; en> I']<)<~<'.<>>< Y Drill l](l-1 . 10 1'(! N7 >-'!()ill'. I . ))(:pcw prv>>vnl.v(l t'.I( l s I>> (]<:(.'(1>>rv chun(;v.* It is rvqucnl,(Q lo <ulQ 4)>c followi.>>(, wor<l" to ni,ep 3 2e ~ Pele ")lc shall also in'truct ul3. observers to ensure thc guurQ hou e. door i'losed tight after opening thc door" The reason for thi" chu>>gc i'o locked for security requirement". Thc Committcc reconvncndcd ensure that thc door ils kept approval of thi" procedure change. ~i-J3I I L. Dcpew prescnteQ thc following procedure changes; SC-1.7E E<<er enc ]In<]inticn Mcnitcrjn On-Site Survc Tear<) //9 (Blue) Procedure PCN75-20I(l. It requested to udd thc following to step 3.7.9.1.; "Ensure guard. house Qoor is closed and locked after using it" The reason for thi" is to maintain security. SC-1-7G Emer rene Radiation hlonitorin On-Site Surve Team I'I< G (Yellow) Procedure PCN75-2040. Xt requested to add step 3 ( 7 "Ensure guard house door is closed and locked after using it" The reason for this is to maintain'ecurity. The Committee recommended approval of these changes. Q('- I 3 l 2 SC-1.11 Post,-Accident He-Entry And Recovery Plan PCN75-1935. PCN75-1935 requested to change item 3.2 to read a follows: The E<nergency Coordinator shall have thc responsibility to determine that the facility und/or surroundings are safe. Xf off-site conQitions are such that off- ite support assistance were required, the HGRE Nuclear Audit anQ Hcvicw Board, the Plant, Operating Review Co!rnnittce, and thc USNHC mu t mutually ugrce that the site i safe und the plant can then be returncQ to normal opcrution. The reason for thi is to be consistent with SC-1. Thc Burcuu of Radiation )Iculth should only bc concerned with mutt,cr . bcyo>>Q the site boundary. The, Connnittce rcconnncndcd approval of thi chango. '($ -.).3 i 3 '-< 6 L. Dcpcw )]r v: e>>l;c() t)>(.s(. )>> ovvdu< c chan(fvs. lt rcqucstcd; D('.J.vtv ol(l stop II.l Au AQQ>>cw stvp II.l Thc uuzili<(ry f(.(.(lwut.(>>'ystc<n it rcu(l'.; <jt pr(>> <nrl; in <(1 ig>><<. l for nr(f(.(:u<(r(l;'o)](>> ul',.i.o>>. T)>('. rc((>>n>> I'or t,hin is th<(l wv nhoul.() bc r>>>>>>.in(f u ()01nplvtc ch(.clc ofl'ach l,in<(, )ui(]r lo p(>> I'or<ni>>p I"1'-.)(> on I;hvsc p>>n<l]n. -207-I<c'.<]Ill]It I. I,<)fe ])I>f <i]<]l)I<~I ~ ~ t)ts) ~ <) tr)) <' '<)< ~ ~ ~ r. <<1) <) )Itr)r ~ c', Annual Rcl~ort jill of all Proccdurc c)ian),co: (Continued) 1/1/75 to 12/31,/75 1 Inc lus ivc PORC ITI'.M NIIHIII!II: Dl',IiCIIT I'I'TON Precautions I imitutxono nn<1 ~e':.into P- Rndintion ~r-1315 P J . Dcpcw pre cntcd. these Monitorin S stem PCN75-20 <7.ote)1.", werc uddcd to Chio procedure procedure chungco. )"our ncw OrQer to incorporate information10B. from an Opcrntion Standing concerning )3uses 10A and. The Conunittee recommended. approval of these changes. 1 M-32.1 DB-25 DB-50 and DB-75 Circuit Breaker Maintenance nnd 75-1318 Overcurrent Tri Device Test anQ/or Re lacement Procedure, PCN75-2060. L. Depew presented the following procedure changes; Step 2.1 - change 63-23 to 60-23 Step 5.1.4 change 63-25 to 60-23 Step 5.1.9 change 63-23 to 60-23 The reason for those changes is to correct a typing error. The Committee recommended approval of the e changes. ~7-1321 L. Depew brought the following item to the Committee's attention. PCN75-1434 was presented to the PORC at Meeting //103-75, but wns inadvertently omitted from the minutes. P- RaQintion Monitorin, System Sct pinto PCN75-1434(Temporary). E. Beatty presented. the procedure change. ."R-12 setpoint is now 10K, present activity io 9K. Suggest rnising setpoint,to 30K, J"Q DeMcrit4 concurs with this." The Connnittcc agreed with the change, and it i.o to be made permanent. The reason for thio change io to prevent; the CV ventilation i olation signal nt the alarm point (of 10K). 75-132 d 0-6 0 cr<<4:ion and Pro<:cso Monitorinr PCH75-2045. L. Depcw prcscntcd t,hio procedure chungc. Sev<<rul ch<ulgeo werc re<)ucotcd to incorpornt;c Op< r<<tion St.<ul<)inl; Orders. Thc Committ;ce rccotnn<cndcd approval of theo<. chnnl.'<.o. 75-1327 S-14 Area nnd Process Ra<lintion Monitorinp System PCN75-7056. L. Depcw presented this procedure change. It re<lueoted to; Change note ofter ot<<p 5.1.13 to rcaQ: "Step 5.1.13 may bc considered. N.A. if system wno in operation and PT-17.1 hns been completed, within one month." to rend; "Step 5.6 mny bc con. i<lercd N.A. if systemuf4cr Change note Step 5.6 wno in operation nnd )"1'-17.2 hn" been co)nplc4cd within onc Dion tll ~ T)<c reason for these changes io to correct the wrong o4cp number in cn<.)>>io4c. Thc Conmii);tee rccolmncll<)cd <ll)luovul of thin change. -208- hnnun1 Rcl>ort'l11 of a11 I>roccdurc changes: (ConLinucil) 1/1/75 to 12/31/7b Inclusive 1)ORC ITfiM NHMlil'.R: Df'..;CR Ti TION "-1331 S-26. 2 Com >uter Out;-of-Service PCN75-2044. L". Dcpew present;cd this procedure change. It requested the following changes; Step 2.2 should road "GS-22.0, Com >uter Guard Check". Add << 5.1.1 - Record time the computer fails and time it is returned to service in the control room Official Record,. 5.3 Add - "File for these with thc computer log sheets to the time period. There wa. no print out." fill in 'l'hc Couunittcc rcconuneniled approval of these changes. SM-7'5-18.2 Pre-Startuo Checkout of Tem orar Blowdown System, PCN75-2082. S, Spector pre ented this new procedure, which was Pre-PORC'd, to outline the steps that must be performed prior to startup of the temporary blowdown system. 75-1337 SM-7 -18.3 Ini.tial Startuo of Steam Generator Blowdown Heat Recove S stem PCN75-2075. S. Spcctor presented this new procedure, which was Pre-PORC'd, to describe the steps necessary to perform fin~1 check-out of the steam generator blowdown heat recovery system. This item is NOT COMPLETE pending post-maintcnance-review. 75-1338 L. Depew presented the following procedures for review; EM-112 Inspection and Repair of 1A Gas Deca Tank Inlet Valves, PCN75-2120. EM-1.16 Re lacement of the Clio-on Strainer.", for thc Service Hater Pum s PCN75-20 8. EM-120 Re lacin Valve 2233 on the Non-Re,cnerative lieat Exchan er Drain IIine PCN75-2107. FM-12 Re air of 1A Stcam Generator Blowdown Sam lc Isol.ation Valve CV-76 5735) PCN75-2113. I M 1 38 '.-Ile'v I.'ue'I. Rlciccnt Tnflcx llo'le Reicn1n ~ PCII7~n192. KM-341. Exec .. I ctilown I,inc Rclocict.ion 1'CN75-;>10A. 1'.M-342 I cvcl T> <<nnmi t.t;cr I'V-llf1'? Tn::tra13c<l .in 1'lace of'T-4C>3, t,o Cont;ro3 1M- i631" iuul 10-48() I'(:N715-l>3.0 'I'hc Couuuitt(.c ) ccouuncn(lcd t.hat; t,hc ab<>vc I>roccdurcs bc ilclct.cil nn t,licy arc no longer needed. -209<< a 4aa .rL I Annual Rcport t/11 of n11 procc<)urc c)inn);cs: (Continue<)) 1/1/75 to,12/31/75 Inclusive OJ<C I'J.'J:.H NUHJJ J'B DJ;SCR I)J'ION 75-l 54)) S-i.l)J )'rc-0 <.r: i,ionnl. I inc IJ of )Jo) I<'c i<) li stem ~ )'CN'j5-. 001. I. Dcpcw prc'cntcd thi tcrnpor<<ry procc<lure chango to bc made permanent. Xt rc<)uc %cd the following change.",; Add u reference 2.2 Flow diagram CVCS Ghcct //1 Add 5.2.1 I)utch Tank outlet valve 375c closed 5.4.2 Add - (If cover on filter an<1 no leaks evident, ass>>Inc va,lve closed.) 5.4.4 Change to: 34GA 5.4.5al - Change to PT-108 5.8 Change to M. O. 'mmediate borat,ion valve MOV-350 closed Add 5.8.1 - Isol<<tion valve. for MOV-350, 348B open Add - 5.8.2 MOV 350/BICC flush valve 353 loclaed closed. Add 5.9.1 )~iOV 350/BPil flush vent 348c closed. E capped Add 5.16.1 Check filter bottom for possible leakage (see step 5.4.2,'dd. 5.19 MOV-350 fuses in Breaker closed. The reason for this change is to provide better guidance for Pre-Operational line up. The Committ'ee reviewed the e tempo> ary changes and recommended that they be made permanent. ~7"-1 'Eh9 I'-p..'3 "pa<I'c u<<r<) V<<lve 0 <ernaor pCtr(q-p139. 't . Dope<< pra.".cot<:d N<ia procedure cha<<dc. 'Ia re<p<e:;I;cd ao dcyaC<'. "aepa 6.10.6, 6a10.6.1, und 6.10.6.2. The rca.",on f'r this is t)><at both C.C.>l. )lcdt Exchungcrs are to remain in serv,t.cc. Thc . Conunittcc rcconuncndcd:<pproval of thi" change. 'j 5-l 350 M-12a I )Jori c Aci<l 1"low Transmitter-I"I'-110 Removal anQ Installa-tion )'CJJ'j5-2063. I.. Depcw presented this new procedure to provide u procedure for the removal of )7-110 for muintcnancc and/or replacement. Thc Connnittcc recommended. approval of this new procedure. 75-1351 K-32 Ann>>nciutor Cur<i Fi,l.e PCJ)75-2079. L. Depcw prcsenteQ Xt, re<Eucsted to ad<i to Annunciator K-32, the temporary blow-thi'CN. down heat. recovery Hi temperature alarm. This will convert this alarm window to a dual function', the C.V. air dryer, which is only useQ during refueling, and the above ))eat Exchanger which is used. when plant is on the line. The rea on for this i there are no spare annunciator windows for t,he temporary blowdown lieut Exchungrei . 7 5-l. 358. PT-6.2A N-35 N.I.S. Intermediate Ranpe Channel.. Al.i,nmcnt and/or Bistable AQ u.,tinent Procedure PCW75-2169. L. Dcpcw prescntcQ this temporary procedure for revi<.w only. Xt re<Euestcd that St,eps 5.6 through 5.21.10 and stops 5.23 through 5.23.13 are to be marked N/A. The reason for this is that only the steps to adieu t high level rod stop, and high level trip setpoints were necessary. The Committee reviewed this change. -210- Annual RcporL I/11 of n11 Px'nccdurc changes: (ConL'inocd) 1/1/75 Lo 12/31/75 T>>clus ivc 1'ORC .ITL'H NUMINE P:R: Dt;.SORY'i'1 ON 75-1 35 PT-6.2h If-36 N.I.S Intcrmcdiatc Rant'c Channel Al.i ~.nmcnt and/or Bi. table Rd ustment Proccd>>rc PCNe(5-21'(0. L. Dcpcw prcscntcd this temporary procedure for review only. It requested that Steps 5.6 through 5,21.10 and Step" 5.23 through 5.23.13 arc to bc marked N/A. The reason for thi" i that only thc step to adjust high level roQ stop anQ high level trip selpoints were ncccs.,ary. Thc Committee revicwcQ this change. ation Monitorin and Rclatcd. ") .,tcms ..tc . Dail Plot 75 135 S-14. 1 Radi r, Rc uircmcnts PCN7 -20~ . L. Dcpcw prc'nted thx new pr o " 'b c. tl c daily plotting rcquircmcnts and, howw thec p Order lotting to Q cscri ll sah bee Qonc.on Thi" is to incorporate Operations 73-12 into an S procedure. The Committee ns recommen Standing ended, a pp roval of this new procedure. ~5-1365 '-8 Com onent Coolin plater S stem PCN75-2181. L. Brodie presented this procedure change. It requested to add Step 3.6 as follows; 3.6 Maintain both C.C.U. heat exchangcrs in service with service water throttled to keep C.C.M. Heat Exchanger outlet temper'a-ture ) 5O~F. The reason for this is to'nsure proper operating policy. for C.C.M. system. The Committee recommended approval of this change. 0-5.1 Load Reduction PCN75-210~i. -L. Brodic pro" cntcd this procedure chungc. It requested to change Step 5.2 to rcaQ; "Add Boric Acid to the Reactor Coolant Sy tcm (Bcfcr to S-3.1, Step 5.4, Boron Concentration Controls." The reason for this is that Procedure S-3.1 was updated and thc step number was changed. The Committee recommended approval of thi" change. This item IS COMPLETE. ~75-136 0-6.7.1 Plant Alarm Panels Test PCN75-2195. L. Brodie presented this ncw procedure to describe use of panel test log form in the testing of p'lant alarm panels. The reason is to provide a procedure for panel tc t log forms. The Committee recommended approval of this change. This item IS COMPLETE. ~7-1373 GC-1.1 Radiation Pmerr encv Proccdi.rea General Information PCN75-2201. L. Brodic presented this procedure change. It requested to add to step 3.2.2.8 the number of the H. P. procedures. The reason is the number is missing. The Committee 'uggested the procedure specify that the Health Physics Section may be responsible rather than use the words of the PCN request. The Committee recommended approval of this change. -21"- ee. ~ eq ~ Annual Rcport I/ll oE all I>roccdurc clr<rr>gcs: (Contin<re()) 1/1/75 tu 12/31/75 Irrclvsivc PORC ITI'.H N)IHIII',It: Dl'.I>CI) 7 I'7 ION 75-1375 M-ll.4.2 Isolation of 18 Char, in Pumn for Maintenance an<1 Reotorin to Scrvicc After Maintenance PCN75-2193. L. Brodic prcocnted thio temporary proccdurc for review only to repair leak on "B" charging Pump Drain Linc. The Committee rcvicwcd this c)range. 75-1381 M-11.24 Wain Feed Pump Insuection and Maintenance FC<'175-1172. L. Brodie presented. this new procedure to be used for the inspection and rcaintenance of Worthington Type 14 VNCD-133. pumps. Certain steps may not apply to all maintenance; and those steps may be marked H/A. The Conqnittcc recommended approval of this nev procedure. 75-1382 M-ll.4.6 Char in Puma Stuffing Box Replacement PCN75-2022, L. Brodie presented this new procedure to outline the otepo for replacement of the stuffing boxes on a charging pump. The Committee recommended approval of this new procedure. ~1363 M-ll.4.7 Char.in< Pumr>s Stuffin Box Assembly llotshon Insr>ection and Maintenance PCH75-2142. L. Brodie presented this new procedure to be used for the inspection and maintenance (Rebuilding) of charging pump stuffing box assemblies in the Hot Shop. The Committee recommended approval of this nev procedure. 75-1384 ~M-5 .1, poccr Rnn e Ni." Detection Ne >lnccment pCN75-P16l.. L. Dco0ie presented thi- ncv proc<.dure to describe the tcp., rc<)uircd for replacement of a NIG Pover Range dctcctor. Tlrc Committc<. rccomrncn<lcd approval of t)rio ncv procddurc. 75-1385 S-l)<.2 RMS Clr(ck Source Data PCN75-"04A. L. 13rodic prcocntcd this procedure. Xt wao disap)>roved. Tlrio procc(lure io not rc(luirc<l by Tcchnical Spccificationo or operations. ~75-13 0 CP-35.0 Inter rnc<li(Ltc Ran,c C)ra>>nc1 N-35 Calibr at,ion r(n<l/or Mnintcnancc PCN75-2)( 2. L. Bro()ic pr c.crrtcd this ncv procc(lure to dcocribc a cries of proccdureo arrd a data olrc(.t ncc(>>:n<L>y for calibration or maintenance work on Intcrmc(liatc Harrgc c)r<ir>>r<.l N-35. The reason for t)rio io to c)r<Lng<. P'I'-C>.2A to a cal.ll>rat,iorr l>rocc(lur c. Tlrc Cormnit.tcc rcco>>>>>>en<)c6 approval of t'.hio ncw pr occ<)urc. 5 l CP-35. 1 Int('mr('<l i <L).(')<Lrr '.< N-35 Cion('.t'<Ll. D(', I'c<Lt PCN75-r~e~31 ~ le ~ BrO(li C pr'L!<r(!ill.e<l I'lr )>> l>L'W l>1'OC(.'(llr <'C I 01 (I<>I (.'<Lli >>I; i<> I,er <n(:(li <Lte Br(trgc N-35 to p<'r'I'orm caiibr'r(tiorr r(rnl/or rn<(irrt.<.rr<r>>c<>. T)rc r'c<c.'.(>rr for thi>> i" to clrrrr>I;< I"I'-I>. h t,o rr Calibrat,iorr I'rocc<lur'c. 'I')rc ~ rccomrn(:n<lcd
l>r ov<(1 of l.lr I.>> rrcw 'ornrnil,tcc I>>'<><"<I'>>"'212<< ~~ "~l."tf 6~ 6','<) Annu(r1 Bc)3ort fill of n11 )rr(3ccdurc c)>>ropes: (Contin(re()) 1/1/75 ta,12/31/75 Inclusive'ORC rrEH N illill lill: DESC)) IPTTON CP-3".3 Trrtcrm(.() ir(tr. Bnn '(. N-35 C(Ll.i)>rat ion )'CN7'p-l'l'i'3. Brodic prcscntcd tlri>tlirrc a pr(3(:c()rrr(: f'r c:()6))rr((tion and/or maintcnancc on Intcrmcdiatc approval of',l>ia rr<<w pr occdurc. This item IS COMl'Ji)",3'I",. ~75-13 3 CP-3".4 Tntcrmr(liatc Ran e N-36 Bistablc Bcla Drivers Cal,i.bration, PCN75-2234. L. Brodic prcscnt<<d thi" new proccdurc l'or calibration and/or maintenance on Intermediate HanCe Bistablc Belay Drive~". The rea on for this i" to chanj~c PT-6.2A to a Calibration Procedure. The Committee recommended approval of this new proccdurc. IS COMPLETE. 75 13<iii CP-36.0 Intermediate Ranee Channel N-36 Calibration r(n(3/or Maintenance. ~77- 'series of procedures and a data sheet necessary for calibration or maintenance work on Intermediate Range channel N-36. The rea"on for this is to change PT-6.2A to a Calibration Procedure. The Committee recommended 6 approval of this new procedure. ~75-13 5 CP-36.1 Intermediate Range N-36 General Defeat PCN75-2235. L. Brodie presented this new procedure for defeating Intermediate Range Il-36 to perform calibration and/or maintenance. The'eason for this is to change PT-6.2A to a Calibrati'on Procedu."e. The Committee recommended approval of this new pr'ocedure. ~V-1396 ~6. CP-36.2 Intermediate is to change Intermediate Rankle N-36 General Reir.state Procedure Range N-36 from the defeat mode. PT-6.2A to a Calibration Procedure. The reason for this The Committee recommended approval of this new procedure. 75-1397 CP-36.3 Intermediate Ran e N-36 Calibration PCN75-2237. L. Brodie presented this new procedure for Calibration and/or maintenance on Intermediate Range N-36. The reason for this is to change PT-6.2A to a Calibration .Procedure. The Conrmittee recommended approval of this new procedure. ~75-13 0 CF-36.4, Intcrmcdiatc Ranpe N-36 Bistable Relay Driver" Calibration, PCN75-2234. L. Brodie presented this new proccdurc to outline a procedure for calibration and/or maintcnancc on Intcrmediatc Range Bistable Belay Drivers. The Reason for this i" to change PT-6.2A to a Calibration Proccduic. The Cormnittec rccommcndcd approval of this ncw proce(lure. ~ ~ ~75-13 PT-6,2A N.I.A. - Tnt(.rnnr()intr. Ban .c C)>>>>>nrln Al i .rrm(nt <<n(l/or Bis tabl r A(l 1>r.; tmrn 4 I't'n(.('.()rr( ('. PCN75-9'1(l0. IBrod i. c pr'caen t(:() this proccdurc l'or ()clctiorr bcca>>sc it i" bcirra rc)rlr(cc(3 by Cl'-35 and CP-36. T)rc Co(run).tt '.c rcconrmcndcd approval of')ri" dclction. r 5-1i<01 l i . n'!<7<n <nnr nl. (lrrnl in l'<<n< 1(i ~<<'nl. inn <<n<l N >npcctiorr and maintrrrarrcr. of cornponcrrt coolirr); )3(un)3::. Tire Connnittcc rcconnncrrdcd (L)>pr(3val of tlrin new procc()>>r r:. I Annual Rcport $/11- of al.1 Iiroccdurc cl>nnI;es: (Conti.nucd) 1/1/75 to 12/31/75 Inc luffivc PORC lTI'.H NUNIII:R: DI SCR7P'I'TON 75-1404 PT-12.2 Zmerpcnc Diesel Generator 18 PCII75-2240. L. Hrodie presented this tcmpor"ry procedure for eview only. It requested to mark steps 6.22 to 6.3, and 6.13 to 6.24 H/A. The reason for this is that the Diesel Generator was started just to check the air pressure during start. The Committee recommended approvnl of this temporary change. 75-1405 P- Precautions Limitations and Setnoints P- Radiation IIonitorinr: 8 stem PCII75-2242. L. Brodie presented this temporary procedure change for review only. It requested; I .3.. 6 Pg. P-9:5, R-1G - change 6000 cpm to 30 000 corn. MPC for Iodine 9 100 GPI4(approximately normal full blowdown) is equivalent to approximately 4$ ,000 cpm. The reason for this is to allow re-.opening of the S/G blowdown 'alves following isolation. The Committee recommended approval of this temporary change. 1 JANUARY 1 1975'TO DECEMBER 31 1975 INCLUSIVE Annual Report of System Modification and Special Tests SYSTEM MODIFICATION NUMBER: TITLE SM 74 2 Rod Position Indicator Pulse To Analo Converter Chan e
Description:

Remove the two existing pulse to analog converters, and install the new solid state pulse to analog converter'afety Evaluation: This modification does not involve any unreviewed safety questions or Technical Specification changes'M 74-3 Re air Of T e W2 Breaker Control Switches

Description:

Replace the pull lever in the W-2 switches with a new double pin lever. Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specification changes. SM 74-18 Steam Generator Platforms

Description:

Fabricate and install permanent (removable) platforms below steam generators lA & 1B for inspection, testing, and cleaning of Steam Generators'afety Evaluation: This modification does not involve any unreviewed safety question and does not require a

~

change in Technical Specifications. SM 74 23 Installation of the Modification for Control of the Boric Acid Su 1 to Safet In ection S stem

Description:

Change the logic and timer controls for the refueling water storage tank to safety in)ection system valves 825A and 825'afety Evaluation: This modification does not involve any unreviewed safety question and does not have an effect to the Technical Specifications.

-215-

Annual Report 011 of all System Modifications and Special 1/1/75 to 12/31/75 Tests completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 74-24 Containment Monitor Pum Tri Modification

Description:

Install trip ci.rcuit so pump will stop on closure of inlet and outlet valves when monitor is in containment sample mode. l Safety Evaluation: This modification does not involve any unreviewed safety questions and does not require change of Technical Specifications ~ SM 74"30 Steam Generator Blowdown Jum er

Description:

Modify the Steam Generator Blowdown isola-tion valves (CV-70 and CV-71) control circui.try to. per<< mit opening of the valves when main feedwater pumps are out of service. Safety Evaluation: This modiHcation does not. involve any unreviewed safety questions or Technical SpeciHca-

=

tion changes'M 74-41 Reactor Tri Breaker Train A and. B. Undervolta e 20ET and 20AST Monitor Circuit Installation

Description:

Install monitor lights to verify proper operation and circuit makeup of the trip breakers and undervoltage trip scheme. Safety Evaluation: This modification does not involve any unreviewed safety questions or Technical SpeciHca-tion changes'M 74-45 All Volatile Treatment Panel

Description:

Installation of All Volati.le Treatment Instrument panel. Safety Evaluation: This modiHcation does not effect Technical Specifications and does not involve any un-reviewed safety questions'M 75-1 Instrumentati.on Relocation in Intermediate Buildin

Description:

Reactor protection channel flow and pressure transmitters that sense maIn steam li.ne pressure and main feedwater flow were moved to areas that are less vulnerable to pipe whip as a result of a major main steam or feedwater pipe rupture. Jet shi,elding was installed to protect the associ.ated instrument tubi.ng. 'abling of some containment instruments that could be affected by such a rupture were rerouted through the Auxiliary Building.

-216-

Annaul Report 8'll of all System Modifications and Special 1 1/1/75 to 12/31/75 Tests completed in 1975 Xnclusive SYSTEM MODIFICATION NUMBER: SM '75-1 (Con't) Safety Evaluation: This modification does not involve any unreviewed safety question and does not require Technical Specifications change, SM 75-2 T.V. S stem in Containment

Description:

Mount T.V. monitoring system, install a new electrical penetration, and run conduit and cables to allow control room observation of reactor coolant pumps, reactor vessel and charcoal filters. Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specifica" Cion changes SM 75>>3 Reheater Steam Relief Vent Pi e Su ort and Concrete

Description:

Modification of xeheater valve inlet. pipe and xeheater syeam relief header discharge piping for relieve escaping steam dynamic load, and addition of new structural steel for increased support. Safety Evaluation: This modification does not involve any unreviewed safety questions or any Technical Speci-ficat$ on changes. SM 75-4 Reroute of Steam Generator Blowdown Line

Description:

Reroute portion of the Steam Generator Blowdown piping and install get shields and line restraints, Safety Evaluation: This modification does not involve any

~

unxeviewed safety question or Technical Specification changes'M 75"6 Service Water Redundant Return

Description:

This modification consists of the addition of a redundant 'return line for the Service Water. This return line will service two component cooling water heat exchangers, the spent fuel pit heat exchangpxs, and the auxiliary building motor coolers. Safety Evaluation: This modification does not involve any unreviewed safety question and does not require Technical Specifications change.

-217-

Annual Report 811 of all System Modifications and Special 1/1/75 to 12/31/75 Tests completed in 1975 1 Xnclusive SYSTEM MODIFICATION NUMBER: SM 75 7.1 Heatin Uentilation and Air Conditionin Backfits for Control Room and Rela Room

Description:

Installed duct work above control room

-ceiling and conduit and cable in the control room and the relay room areas, Safety Evaluation: This modification does not involve any unreviewed safety question and does not require a change of Technical Specifications.

SM 75-8 Service Water protection - Intermediate Buildin

Description:

Xnstall steel plate in the Intermediate. building directly under the main steam header. Safety Evaluation: The modification does'ot, involve. any unreviewed safety question or Technical Specifica>>-

.tion changes.

,SM 75-10.1 Installation of Groundin Cable for Auxilia Buildin Addition

Description:

Xnstallation and revision of grounding cable for grounding the new Auxiliary Building. Safety. Evaluation: This modificati'on does not involve any unreviewed safety question and does not require a change of Technical Specifications ~ SM 75"10.2. Installation of Auxiliar Buildin Addition Caissons

Description:

Installation of caissons for the Aux>>. iliary Building addition. Safety Evaluation:'This modification does not involve any unreviewed safety question and does not require a change of Technical Specification. SM 75"10.21 Auxiliar Buildin Addition Excavation Fill and Com"

~ac Cion

Description:

Excavation, Auxiliary Building Addition. fill and compaction for the Safety Evaluation: This modification does not involve an unreveiwed safety question and does not require a change of Technical Specification.

'-218-

~

I g I Annaul Report 811 of all System Modifications and Special 1/1/75 to 12/31/75 Tests completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 75-10.22 Auxiliar Buildin Addition Below Ground Installations

Description:

Make below ground penetration and other necessary installation, prior to floor pad installa-tion for the Auxiliary Building addition. Safety Evaluation: This modification does not involve and unreviewed safety question and does not require a change of Technical Specification. SM 75-11 Switch Control Board Recorders and Controllers to Instrument Bus 1C

Description:

Switch of control board recorders and controllers power feed over to instrument bus lC. Safety Evaluation: This modification does not involve and unreviewed safety question and does not requ~ a change in the Technical Specifications. SM 75-16 Feedwater Thermowells Installations

Description:

Install new thermowells between flow . orifice and check valves in "A" and "B" feedwater lines. Safety Evaluation: The installation was in a Non+A pipe and is before the check valve. Due to this there ia no safety problems and does not require a Technical Specification change. SH'75-17 'Condensate Re ect Line Se ration

Description:

Separate Auxiliary Feedwater pump suction from condensate reject line. Safety Evaluation: This modification does not involve an unreviewed safety question and does not require a change in Technical Specifications. 'SM 75<<19 Pressurizer Jib Crane Extension

Description:

Add a removable extension onto the pressur-izer )ib crane to allow work on the pressurizer safety valves. Safety Evaluation: This modification did not involve any unreviewed safety questions or Technical Specification changes.
7 I Annual Report 8'll of all System Modifications and Special 1/1/75 to 12/31/75 Tests Completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 75-20 Control Rod Drive Sha ft Modification

Description:

Machining of chamfers on control rod drive rod assemblies to correct an interference con-dition which is possible. Safety Evaluation: This modification does not involve any unreviewed safety question and does require change of Technical Specifications. CM-75 23 accumulator Revel Indicator Modification

Description:

Remove and reinstall loop accumulator level transmitters to allow raising of their positions approximately 16. 778". Safety Evaluation: This modification does not involve any unreviewed safety questions and does not'equire change of Technical Specifications. SK 75=24.1 ~earn'Generator Orifice Rin 'Modification

Description:

Remove the existing orifice ring and install new'rifice ring to steam generator swirl vane'. Safety Evaluation This modification does not involve and unreviewed safety question and does not require a change in Technical Specifications. SM 75-24.2 Feedwater Rin Modifications on Steam Generators

,Description: Enlarge hot leg holes and plug certain cold leg holes.

Safety Evaluation: This modification does not involve any unreviewed safety question and does not require a change in Technical Specifications. SM 75"24.3 Downcomer Resistance Plate Removal for Steam Generators

Description:

Remove feedwater resistance plate and support rods. Safety Evaluation: This modification does not involve any unreviewed safety question and does not require a change in Technical Specifications.
r Annual 811 of all System Modifications and Special 1/1/75 to 12/31/75 Tests Completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER

'M 75-24.4 Tube l.ane Blockin Device

Description:

Install tube lane blocking device Safety Evaluation: This modification does not involve any unreviewed safety question and does not'equire a change in Technical Specifications. SM 75"27 Provide Ke Switched on MCB for MOV's 896A 6 896B

Description:

Install key switch on DC 'power for MOV 896A & B to reduce passive failure probability. Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specification. SM 75"28 Additional Tele hone Cables

Description:

Install two conduits from outside through 1B Battery Room wall to allow installation of two new 50 pair telephone cables.

"Safety'Evaluation: This modification does not involve any unreviewed safety question or Technical Specification change.

SM 75"30 Installation of Solid State Underfre uenc Rela For 4KV Bus Description Remove and replace protective relays 811/11A, B and 812/11A, B, with a new model KF relay, to reduce probability of a relay malfunction. Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specification change. SM 75"32 Installation of Penetration Seals With BISCO Silicone Foam

Description:

Install BISCO silicone foam in floor and wall penetrations for prevention, limitation and control of fire, its hazards and damaging effects, where the protection of safety related systems, structures and equipment is required.

-221-

Annual 811 of all System Modifications and Special 1/1/75 to 12/31/75 Test Completed 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 75-32 {Con't) Safety Evaluation: This modification does not involve any unreviewed safety questions and does not require a change in Technical Specifications. SM 75-33 Provide Ke Switches on MCB for 852A & B

Description:

Provide key switch on DC power for MOV 852A and B to de<<energize valves. Safety Evaluation: This modification does not involue any unreviewed safety question or Technical Specifica<< tion change. SM 75"35 Main Steam Isolation Valves Modification

Description:

Remove upper seal on piston in actuator, machine approximately 1-3/8'" off disc stop in valve body, and drill 1/8" bleed hole on upper chamber of actuator. Safety Evaluation: This modification does not involve any unreviewed safety questions and does not require a change in Technical Specifications. SM 75"36 Tem orar Feedwater Control Valve Modification

Description:

Install hydraulic dampening system on feedwater control valves. SPECIAL Safety Evaluation: This modification does not involve TEST any unreviewed safety question or Technical Specifica-NUMBER: tion change. ST 73-4 Circuit Breaker Overcurrent Tri Device Test

Description:

This test was conducted on the Safeguards Equipment to insure that the overcurrent devices would operate correctly. Several devices have been replaced and the testing is continuing. Safety Evaluation: This test does not involve any unre-solved safety question and does not require a change in the Technical Specifications, ST 74<<6.1 Installation of a Ne ative Se uence Recorder on the Gen-erator Out ut

Description:

Install a VF-840 watt transducer in the generator metering potential and current transformers for subsequent recorder hookup and tests.'
Annual'Il of all System Modifications and Special 1/1/75 to 12/31/75 Tests Completed in 1975 Inclusive

\

SPECIAL TEST .NUMBER: ST 74 6.1 Safety Evaluation: The test did not involve any (Con t) unresolved safety questions, and does not require a change in the Technical Specifications. ST 74 6.2 Removal of Westin house Su lied Ne ative Se uence Recorder and Installation of RG&E Ne ative Se uence

.Monitor on the Generator Out ut

Description:

To effect the steps necessary to remove

'a VP-840 watt transducer in the generator metering .potential and current transformers for recoxder hookup 'end tests, and installation of similar-equipment.

safety Evaluation: The test did not involve any unresolved safety questions, and does not r~e ire w change in tHe Technical.,Specie ST 75-1 Ra id Fuel Assembl Power 'Zs'caaation'"Test-"

Description:

By positioning a control rod (G-9) in a

region of relatively high linear power density,. the flux will be depressed, decreasing the power density.

During the conditioning, significant clad creepdown wi.ll take place. When the control rod is withdrawn, the linear powex density will increase, causing rapid fuel pellet expansion. The expansion should-cause.'. increased clad- stresses and'he test"-should verify Rat vendor calculations are conservative. (See

below) ~

Safety Evaluation: Higher than noxmal stresses placed on fuel assembly E-24 cladding, but less than design values. The margin of safety was not xeduced and there were no unreviewed safety questions. No Zechnical Specifications changes were necessaxy, ST 75-3 Westin house Develo ent Test MSR Reheater Scaven e Steam Vent Condenser

Description:

Establish the necessary condi,tion and steps which must be followed to enable the effective testing and evaluation of an SSVC which is installed in MSR-lA. Safety Evaluation: This test does not involve any un-reviewed safety question and does not require change of

.Technical Specifications, *: Test was aborted prior to actual rapid-power-escalation when NRC Compliance determined an unreviewed safety question was involved. "223-

Annual 011 of all System Modifications and Special 1/1/75 to 12/31/75 Tests Completed in 1975 Inclusive SPECIAL TEST NUMBER

'T 75-4 Initial Turbine Plant Start>>U Pro ram Followin Plant Tri of 0956 Hours on 6 17 75

Description:

To outline requirements for plant startup following plant trip of 0956 hours on 6/17/75. Safety Evaluation: This test does not involve any unreviewed safety question and does not re-quire a change of Technical Specifications. ST'5"5 Monitor Six.Sn'sam %suer'aror Leve1s Simulr~aneous1 From All Four .Reactor Protection Channels

'v

Description:

Record all'six steam generator levels

~

using most aensitiv'e range:on recorder without in-ducing:external noise., Safety Evaluations: This'est does not. involve

~

any unrevt,awed:safety;.question and does not re-quire a change.uC Zechnical Specifications. a ST 75>>6 Steam Generator -Moi.sture Carr Over Measurement

Description:

Determine the amount of moisture carry<< over from the.s'team generators to feedwater usi.ng 24-Na tracers. I Safety Evaluation: This'est does not involve any unreviewed safety. questiqn and does not requi.re a change .of Technical Specifications.
ANNUAL REPORT 811 JANUARY 1 1975 TO DECEMBER 31 1975 INCLUSIVE Annual Report of System Modification and Special Tests SYSTEM MODIFICATION NUMBER: TITLE SM 74-2 Rod Position Indicator Pulse To Analo Converter Chan e

Description:

Remove the two existing pulse to analog converters, and install the new solid state pulse to analog converter. Safety Evaluation: This modiHcation does not involve any unreviewed safety questions or Technical SpeciHcation changes. SM'74 3 Re air Of T e W2 Breaker Control Switches

Description:

Replace the pull lever in the W-2 switches with a new double pin levex. Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specification changes'M 74>>18 Steam Generator Platforms

Description:

Fabricate and install permanent (removable) platforms below steam generators 1A 6 1B for inspection, testing, and cleaning of Steam Generators'M Safety Evaluation: This modification does not involve any unreviewed safety question and does not require a change in Technical Specif.cations. 74-23 Installation of the ModiHcation for Control of the Boric Acid Su 1 to Safet In ection S stem

Description:

Change the logic and timer controls for the refueling water storage tank to safety injection system valves 825A and 825B. Safety Evaluation: This modification does not involve any unreviewed safety question and does not have an effect to the Technical Specifications.

-225>>

Annual Repoxt $ 11 of all System Modifications and Special 1/1/75 to 12/31/75 Tests completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 74-24 Containment Monitor Pum Tri Modification

Description:

Install trip circuit so pump will stop on closure of inlet and outlet valves when monitor is in containment sample mode. Safety Evaluation: This modification does not involve any unreviewed safety questions and does not require change of. Technical Specifications'M 74-30 Steam Generator Blowdown Jum er

Description:

Modify the Steam Generator Blowdown isola-tion valves (CV>>70 and CV-71) control circuitry to per-mit opening of the valves when main feedwater pumps are out of service. Safety Evaluation: This modification does not involve any unreviewed safety questions or Technical Specifica-tion changes. SM 74-41 Reactor Tri Breaker Train A and B Undervolta e 20ET and 20AST Monitor Circuit Installation

Description:

Install monitor lights to verify proper operation and circuit makeup of the trip breakers and undervoltage trip scheme Safety Evaluation: This modification does not involve any unreviewed safety questions or Technical Specifica-tion changes'M 74-45 All Volatile Treatment Panel

Description:

Installation of All Volatile Treatment Instrument panel. Safety Evaluation: This modification does not effect Technical Specifications and does not involve any un-reviewed safety questions. SM75 1 Instrumentation Relocation in Intermediate Buildin

Description:

Reactor protection channel flow and pressure transmitters that sense main steam line pressure and main feedwater flow were moved to ax'eas that axe less vulnerable to pipe whip as a result of a major main steam or feedwater pipe rupture. Jet shielding was installed to protect the associated instrument"tubing.- Cabling of some containment instruments that-could be affected by such a rupture were rerouted through the Auxiliary Building.

-226-

Annual Report 811 of all System Modifications and Special 1/1/75 to 12/31/75 Tests completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 75-1 (Con't) Safety Evaluation: This modifioation does not invo1ve any unreviewed safety question and does not require Technical Specifications change. SM 75-2 T.V. S stem in Containment

Description:

Mount T.V. monitoring system, install a new electrical penetration, and run conduit and cables to allow control room observation of reactor coolant pumps, reactor vessel and charcoal filters'afety Evaluation: This modification does not involve any unreviewed safety question or Technical Specifica-tion changes SM 75-3 Reheater Steam Relief Vent Pi e Su ort and Concrete

Description:

Modification of reheater valve inlet pipe and reheater syeam relief header discharge piping for relieve escaping steam dynamic load, and addition of new structural steel for increased support. Safety Evaluation: Tapis modification does n'ot involve any unreviewed safety questions or any Technical Speci-fication changes'M 75-4 Reroute of Steam Generator Blowdown Line

Description:

Reroute portion of the Steam Generator Blowdown piping and install jet shields and line restraints. Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specification changes'M 75-6 Service Water Redundant Return

Description:

This modification consists of the addition of a redundant return line for the Service Water. This return line will service two component cooling water heat exchangers, the spent fuel pit heat exchangers, and the auxiliary building motor coolers. Safety Evaluation: This modification does not involve any unreviewed safety question and does not require Technical Specifications change.
Annual Report 811 of all System Modifications and Special 1/1/75 to 12/31/75 Tests completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 75>>7.1 Heatin Ventilation and Air Conditionin Backfits for Control Room and Rela Room

Description:

Installed duct work above control room ceiling and conduit and cable in the control room and the relay room areas. Safety Evaluation: This modification does not involve any unreviewed safety questi.on and does not requi.re a change of Technical Specifications. SM 75 8 Service Water Protection - Intermediate Buildin

Description:

Install steel plate in the Intermediate building directly under the main steam header. Safety Evaluation: The modification does not involve any unreviewed safety question or Technical Specifica<< tion changes. SM 75-10.1 Installation of Groundin Cable for Auxilia Bui.ldin Addition

Description:

Installati.on and revision of grounding cable for grounding the new Auxi.liary Building. Safety Evaluation: This modification does not involve'ny unreviewed safety question and does not requi.re a change of Technical Specifications. SM 75"10.2 Installation of Auxiliar Buildin Addition Caissons

Description:

Installation of caissons for the Aux-i.liary Building addition. Safety Evaluation'. This modification does not involve any unreviewed safety question and does not require a change of Technical Specification. SM 75-10.21 Auxiliar Buildin Addition Excavation Fi.ll and Com-

~action

Description:

Excavation, Auxiliary Building Addition. filland compaction for the Safety Evaluation: This modification does not involve an unreveiwed safety question and does not require a change of Technical Speci.fication.

-228-

Annual Report 7111 of all System Modifications and Special 1/1/75 to 12/31/75 Tests completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 75"10.22 Auxiliar Buildin Addition Below Ground Installations

Description:

Make below ground penetration and other necessary installation, prior to floor pad installa-tion for the Auxiliary Building addition. Safety Evaluation: This modification does not involve and unreviewed safety question and does not require a change of Technical Specification. SM 75-11 Switch Control Board Recorders and Controllers to Instrument Bus 1C

Description:

Switch of control board recorders and controllers power feed over to instrument bus 1C. Safety Evaluation: This modification does not involve and unreviewed safety question and does not require a change in the Technical Specifications. SM 75-16 Feedwater Thermowells Installations

Description:

Ins'tall new thermowells between flow orifice and check valves in "A" and "B" feedwater lines. Safety Evaluation: The installation'was in a Non-QA pipe and is before the check valve. Due to this there ia no safety problems and .-does" not require a Technical Specification change. SM 75-17 Condensate Re ect Line Se aration

Description:

Separate Auxiliary Feedwater pump condensate reject. line. suction'rom Safety Evaluation: This modification does not involve an unreviewed safety question and does not require a change in Technical Specifications. SM 75-19 Pressurizer Jib Crane Extension

Description:

Add a removable extension onto the pressur-izer jib crane to allow work on the pressurizer safety valves. Safety Evaluation: This modification did not involve any unreviewed safety questions or Technical Specification changes.
Annual Report $ 11 of all System Modifications and Special 1/1/75 to 12/31/75 Tests Completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 75-20 Control Rod Drive Shaft Modification

Description:

Machining of chamfers on control rod drive rod assemblies to correct an interference con-dition which is possible. Safety Evaluation: This modification does not involve any unreviewed safety question and does require change of Technical Specifications. SM 75"23 Accumulator Level Indicator Modification

Description:

Remove and reinstall loop accumulator level transmitters to allow raising of their positions approximately 16.778". Safety Evaluation: This modification does not involve any unreviewed safety questions and does not require change of Technical Specifications. SM 75 "24.1 Steam Generator OriHce Rin Modification

Description:

Remove the existing orifice ring and install new orifice ring to steam generator swirl vanes. Safety Evaluation: This modification does not involve and unreviewed safety question and does not require a change in Technical Specifications. SM 75-24.2 Feedwater Rin Modifications on Steam Generators

Description:

Enlarge hot leg holes and plug certain cold leg holes. Safety Evaluation: This modification .does not involve any unreviewed safety question, and does not require a change in Technical Specifications. SM 75-24.3 Downcomer Resistance Plate Removal for Steam Generators

Description:

Remove feedwater resistance plate and support rods. Safety Evaluation: This modification does not involve any unreviewed safety question and does not require a change in Technical Specifications.
Annual Report Nll of All System Modifications and Special 1/1/75 to 12/31/75 Tests Completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 75-24.4 Tube Lane Blockin Device

Description:

Install tube lane blocking device Safety Evaluation: This modification does not involve any unreviewed safety question and does not require a change in Technical Specifications. SM 75-27 Provide Ke Switched on MCB for MOV's 896A & 896B

Description:

Install key switch on DC power for MOV 896A & B to reduce passive failure probability. Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specificati'on. 8M75-28 Additional Tele hone Cables

Description:

Install two conduits from outside through

'1B Battery Room wall to allow installation of two new 50 pair telephone cables.

Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specification change. SM 75-30 Installation of Solid State Underfre uenc Rela For 4KV Bus

Description:

Remove and replace protective relays 811/11A,B and 812, llA,B, with a new model KF relay, to reduce probability of a relay malfunction. Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specification change. .SM75-32 Installation of Penetration Seals With BISCO Silicone Description; Install BISCO silicone foam in floor and wall penetrations for prevention, limitation and control of fire, its hazards and damaging effects, where the protection of safety related systems, structures and equipment is required.
Annual Report N'll of all System Modifications and Special 1/1/75 to ,'2/31/75 Tests Completed in 1975 Inclusive SYSTEM MODIFICATION NUMBER: SM 75-32 (Con't) Safety Evaluation: This modification does not involve any unreviewed safety questions and does not require a change in Technical Specifications. SM 75-33 Provide Ke Swi.tches on MCB for 852A & B

Description:

Provide key swi.tch on DC power for MOV 852A and B to De-energize valves. Safety Evaluation: This modification does not involve any unreviewed safety question or Technical Specifica-tion change. SM 75-35 Main Steam Isolati.on Valves Modification

Description:

Remove upper seal on piston in actuator, machine approximately 1-3/8" off disc stop in valve body, and drill 1/8" bleed hole on upper chamber of actuator. Safety Evaluation: This modification does not involve any unreviewed safety questions and does not require a change in Technical Specifications. SM 75-36 Tem orar Feedwater Control Valve Modification

Description:

Install hydraulic dampening system on feedwater control valves. SPECIAL Safety Evaluation: Thi.s modification does not involve TEST any unreviewed safety question or Technical Specification NUMBER: change. 'ST-73-4 Circuit Breaker Overcurrent Tri Device Test

Description:

This test was conducted on the Safeguards Equipment to insure that the overcurrent devices would operate correctly. Several devices have been replaced and the testing is continuing. Safety Evaluation: This test does not involve any unre-solved safety question and does not require a change in the Technical Specifications. ST 74-6.1 Installation of a Ne ative Se uence Recorded on the Generator Out ut

Description:

Install a VP-840 watt transducer in the generator metering potential and current transformers for subsequent recorded hookup and tests.
Annual Report $/11 of all System Modifications and Special 1/1/75 to 12/31/75 Tests Completed in.1975 Inclusive SPECIAL TEST NUMBERS: ST 74-6.1 Safety Evaluation: The test did not involve any (Con't) unresolved safety questions, and does not require a change in the Technical Specifications. ST 74-6 2 Removal of Westin house Su plied Ne ative Se uence Recorded and Installation of RGB Ne ative Se uence Monitor on the Generator Out ut

Description:

To effect the steps necessary to remove a VP-840 watt transducer in the generator metering potential and current transformers for recorded hookup and tests, and installation of similar .-equipment. Safety Evaluation: The test did not involve any unresolved safety questions, and does not require a change in the Technical Specifications. ST 75-1 Ra id Fuel Assembl Power Escalation Test

Description:

By positioning a control rod (G-9) in a region of relatively high linear power density, the flux will be depressed, decreasing. the power density. During the conditioning, significant clad creepdown will take place. When the control rod is withdrawn, the linear power density will increase, causing rapid fuel pellet expansion The expansion cause increased clad stresses and the test should verify that vendor calculations are conservative. (See

below) .

Safety Evaluation: Higher than normal stresses were placed on fuel assembly E-24 cladding, but less than . design values. The margin of safety was not reduced and there were no unreviewed safety questions. No Technical Speci,fications changes were necessary. ST 75-3 Westin house Develo ment Test MSR Reheater Scaven e Steam Vent Condenser

Description:

Establish the necessary condition and steps which must be followed to enable the effective testing and evaluation of an SSVC which is installed in MSR-lA. Safety Evaluation: This test does not involve any un-reviewed safety question and does not require change of Technical Specifications. Test was aborted prior to actual rapid-power-escalation when NRC Compliance determined an unreviewed safety question was involved.

-233-

Annual Report 8'll of all System Modifications and Special 1/1/75 to 12/31/75 Tests Completed in 1975 Inclusive SPECIAL TEST NUMBER'T 75-4 Initial Turbine Plant Start-U Pro ram Followin Plant Tri of 0956 Hours on 6/17/75

Description:

To outline requirements for plant start-up'ollowing plant trip of 0956 hours on 6/17/75 Safety Evaluation: This test does not involve any unreviewed safety question and does not require a change of Technical Specifications. ST 75"5 Monitor Six Steam Generator Levels Simultaneousl From All Four Reactor Protection Channels

Description:

Record all six steam generator levels using. most sensitive range. on recorder without in-ducing external noise. Safety Evaluations: This test does not involve any unreviewed safety question and does not re-quire a change of Technical Specifications. ~ ST-75-6 Steam Generator Moisture Car Over Measurement

Description:

Determine the amount of moisture carry-over from the steam generators to feedwater using 24 Na tracers. Safety Evaluation: This test does not involve any unreviewed safety question and does not require a change of Technical Spedifications.

-234-

') fi

'I I

I

~

AiWJAL OPERATING REPORT 813 OF R. E. GXi'tNA i~tUCLEAR STATION ROCHESTER GAS Il: ELECTR1C CORPORATION 1977 DOCKET NO. 50-244 LlCENSE NO. DPH-18
h J J 1
TABLE OF CON ""I'S PAG. Z'ITRODUCTZOH HZGiiLZGaTS SUii2V~RY OF OP%V.TZi'IG .XPWi~~IC ~ P~<Vi OP, PROCZ3brH CE<2IGZS, "STS, 'C? RATS, AÃD SAr TY-BRA '3 K< ~'PZfr~ICE Amendments to Facility License or Technical Specizications 5 - 23 Facility or Procedure Changes Requiring iiRC Approval 24 Tes s and. Lcperiments Reauir'ng HRC Approval 25 Other Changes, Tests, and. Ecpe iments 26-3l Corrective Maintenance of Safety Related .auipment 32 Mechanical and Electr'cal Maintenance 33 43 Znst~entation and Control Equipment Maintenance 44 - 49 LZCm~IS~ ~~ri x ~ORTS 50 - 72 O~r" EVmlTS OF Z'iiiEST 73 Fuel Performance Fuel Data 75 Core Loadirg Pattern 76 Steam Generator Znspection(s) 77 78 Summa~/ of Containment Znteg=ated Leak Rate Tests 7Q DATA ~MUMTZONS 80 Net Electrics'ower Generation 8l Uni Shu downs and Forced Poser Reduct'ons 82 83 iIumoe of Pe son"el a d. Man/Rem "-cposure oy ~(Iork and Zoo "urction 84 86 Plant Organisation and Pe sonnel 87 Opera ing Eistogram 88 UiiIZQUE BZ?ORTZ'IG REQU~~~KiITS 89 Condenser Tuoe Main ena"ce oo Primary, S/G Blovdo~ Ch~~'stry Leak T s s on Sou"ces 92 Rad'oactive "flu . ts 93 o4 Solid, Haste 95 - 96

>>nvironmental Mon'toring 97 - l00 GLOSSARY lol

INTRODUCTION R. ~ . Ginna Nuclear Station is a pressurized water reactor of 470 bÃe net maximum capacity, owned by Rochester Gas and Z1ectric Corporation and is located. in Ontario, New York, The nuclear steam supply system is a Westinghouse PWR. The Architect/r~gineer was Gilbert Associates, and the construc-tor was Bechtel. The condenser cooling method is once-through, and Lake Ontario is the condenser cooling water source. The Plant is subject to license DPR-18, issued September 19, 1969 pursuant to Docket Numoer 50-244. The date of initial reactor criticality was November 9, 1969, and commercial generation of power began July 1, 1970. This report was prepared by Frank W. Aman, 716/546-2700, Exten-sion 291-237,
E HTGHLTGHTS The Robert Emmett Ginna Station operated at 100% power until January 11 of this report period when, due to a tube leak in the 1B2 condenser, power was reduced to 46% while repairs were made, A turbine main steam stop valves test was also performed and the unit was returned to 100% power on January 12. On January 25, power was reduced to 50% to effect repairs on a tube leak in the 1B1 condenser. The unit was returned to full power on January 26. Power was reduced to 48% on February 13 to conduct the turbine steam stop valves test and returned to full power on February 19. On Harch 21, power was reduced to 45% to effect repairs on a tube leak in the 1B1 condenser and to perform a turbine main steam stop valves test. The unit was returned to full power on Mi rch 26. On April 15 the unit was placed in cold shutdown for annual overhaul and refueling. On May 22 the unit was taken critical but returned to hot shutdown on May 23 due to control rods K-7 and L-8 being in-operable. The unit commenced return to power on Hay 24 and reached full power on Hay 28. The unit remained at full power until July 5 when it was taken to cold shutdown to effect repairs on, a tube leak in the "B" steam generator. The unit was taken critical on July 13 and reached full power on July 14. The unit was again taken to cold shutdown on August 4 to effect repairs on two inoperable snubbers on the "A" steam generator. The unit was returned to full power on August 8. The unit was taken to hot shutdown on November 4 to effect repairs on an inoperable snubber on the "B" steam generator. The unit was returned to full power on November 6. The unit was taken to hot shutdown to correct inoperable control rods on November 17 and returned to full power on November 19. The unit was taken to hot shutdown on December 3 due to a leaking pipe tap on the residual heat removal system. The unit was returned to full power on December 4 and remained at full power through the balance of this report period.

SUMMARY

OF OPERATENG EXPEREENCE The following is a chronological description of Plant Operations in-cluding other pertinent items of interes for the twelve month period ending December 31, 1977. 1/11 1-B-2 Condenser, Tu'oe Leak - Also performed Turoine Main Steam Stop Valves Test. 1/25 1-B-1 Condenser, Tube Leak 2/13 Turbine Main Steam Stop Valves Test 3/21 1-B-1 Condenser, Tube Leak Also performed. Tubine Main Steem 'Stop Va1ves Test. 4/i5-5/22 Annual refueling and. maintenance. 5/24 Enoperabie Control Rods K-7 and L-8 7/5-7/i3 "B" Steam Generator - Tube Leak. 8/4-8/7 "A" Steam Generator Two inoperable"'snubbers. 11/4-5 "B" Steam Generator One inoperable snubber. il/ 7 EnoperaGXe:*Control Rods. 12/3 Leaking ppe tap residue'eat removal system.
PLANT OB PBOCEDUBE CHMVGES TESTS KG'EBiK>ITS AND SAFETY-BELA~~ Y>iNTENANCE
DENTS TO FACXLlTY LiC='HSE OR TECFZIZCAL SPECZFZCATZONS On April 7, 1977, The Nuclear Regulatory Commission issued Amendment i/12 to R. E. Ginna Nuclear Power Plant Provisional Operating License 3o. DPR-18, reviqing Appendi~ .A,-.paragraphs '3.1.2 and its basis Table 3.1.1, 3.1.2, 3.5.1, paragraph 4.3.1, Figures 6.2.1, 6.2.2, to read as follows: 3.1.2 Heatun and. Cooldown Limit Curves for Hormal Opera ion 3.1.2.1 The reactor coolant temperature and, pressure and system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance wi h F'gures 3.1-1 and 3.1-2 for the first 10.6 effective full po~er years. Basis: F acture Tou hness Pronerties Heatup and cooldown limit curves are ca1culated using the most limiting value of RT~T at the end of 10.6 effective ~l power years (EFPY). The 10.6 EFPY period is chosen such that the limiting RT~ at the 1/4T location in the core region is hiker han the RT~ . "iVVT of the limiting unirradiated material. This service period assures that all components in the Reactor Cool-ant System will be operated, conservatively in accordance with Code recommendations. The highest RT of the core region material is determined, by a%cling the radiation induced D RT for the applicable time period to the original RT shown in Reference (5). The fast neutron DDT (Epy gev) fluence at 1/4 thickness a'nd 3/4 thick-ness vessel locations is given as a function of fu11 power service life in Reference (5). Using the applicaole fluence at the end of the 10.6 EFPY period for 1/4 thickness and the copper content of the material in question, the D RT~T is obtainec. from Reference (5). The b, RT is mTore conserva-tive than the value obtained, From the second cap-sule of radiation surveillance program. Heatun and Cooldown Limit Curves Thus, the governing equation for the heatup-cool-down analysis is: where: K is the stress intensity factor caused by membrane (pressure) stress. K - is the stress intensity factor caused by the thermal gradients. ZR 'f is provided. 'oy the Cod.e as a function temperatu relative to the RT~T of the material.
('r J, Y (
Ref "ence

'hTCAP-8421, "Analysis of Capsule R from the Roches er Gas and. =-lectric Corporation)

R. Z. Ginna Un't No. 1 Reactor Vessel Radi-ation Surveillance ~ 0~em" 3.1-12 Amendment Ho. 12 Zf the specifieL shutdown m "e n is mai taineL) there is no gossi'oility of an accidental c iticality as a result of an increase in moderator temperature or a decrease of coolant pressure. 2800 12 amendment I'fo. 12

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Fi(!It re 3. I -! Reactor Coolant Syttc)II Heott)p I.i)It(tot(one Apolica'."Ic for 10.o Efiec!jve sP,.II Power Yenrt. I~o IO Fs P~ ~ = EO PSI

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4.3.0 REACTOR VESSEL PATEHIAL SURVEILLMlCE PROGRAM Snecif ication: The reactor vessel material surveillance testing program is designed to meet the requirements of Appendix H to 10 CFH Part 50. This program consists o the metallurgical specimens receiving the following test; tensile, charpy impact and the WOL test. These tests of the Radiation Capsule Specimens shall be performed as follows: CAPSULE TINE TESTED V End of 1st core cycle R End of 3rd core cycle T 10 years, at neares efueling P 20 years, at neares refueling S 30 years, at nearest refueling Standby
a T,CIHNA avcLLAP PIWI:t ILA:lr IVVNC IIVIT OPCA::IIA1 ION CIVAPT CNAIPHAH Ol'lat'PLLNO ofaaa TIHCIIOAAL AIIATIHONIPI PAISIOPNT I r I Cv I Iv C VICC I'at 5IOfvf V t, NAaltfTINC v,p, SLSC'faIC V t, ClfCTalC TAAHStOATATItal VICf. Pacflncaf vlcc talalljcal tvacNASIHC, lvlLIC STSI III tLANNINC flcINlfalac 5 f fill'TAII' SICAH NSAPN IHPOPAATIOH AHD OPCAATIOH 0151AIAOTIOH I Cva'51 avcf I OH ttvla'CT IIN OI5falCIS VTILIIATION OIV, Sut 1, PVACNASIHC OIV, 5VI'T ~ ~ Calf f IIC Iaf Lll fllCIalc ~ accaf SLSCT. THAN' SII AH 0> CIST., I ufll.. VaaNNN PION lO I SQ A5515TANT CNICP 4 4, ~ clfcfAIC 5utf, SLICINIC 5 NCIHI Ca aSSr. CNIIP Sut 5 ~ I Nfl Hal NT SISIIrl CINSAATIOA HLTCA I Laa CHCINICAINC I I I'NCINS a CIHNA 5IAIION ANO IVCL ~ LAHHINC CONSTAVCPION CP I 4'IACI.HS II tfalall vufaof 'vvIACI a 4 5 5 I 5 'I All1 ru Ol 5ICI ~ SIC alt CCHIP*L NAINIIHAacc la ALllf I\ ~ I I'l I IINIIHT 4554 aa:4 I 0 t v ac HI5 I HC fufL HallAca HINT ILICTAIC NSTCA Slaff Of SICH I CIN>af. CNCII If'AS acooaoS. oo vacNT COIITAOL, OAAPTIHC CIHIAAL 5'lafl'vALITP HAlNIIHANPC Cla:I ACL IPIALII'I ASLCIAICL Il'lI I.I,t tlAH'I IAINATION>'I CINLA STATIINI OICAI I AT II I Vl tl 0 Iul LNW al TIV II I' CUS>>ol&loa A I f I LTA>>l SUtl I IVTLIANNT ufl'ICC LAC I I I I ~ I5 I sul I5 v I OOt SU ~ CAVI50A Clllrllalat A>>0 Orlaal lsu<$ LOCI>>lt~ a1511 a A ru '115'lS NAI"lurAVCI tutlul lt

>>LCLIAa EIUALI lf C&/TAOL t>>CI>>tta AIALTN INI5IL'5 CJLII I I ~ tuel>>Isa >>INC'll NSALTN otaaavlcus 541 I&IISINAI<a I cululsf tNISICISf Sutkaullul ICN ICII "5 ~ C $ 1'ttaVISOA JCINI I a 5 ut L I v I aoa 1 Cuir'I5111 AAUIATION taOIICT IOL 5LI I: faalluu I/5NI IT rat>>CL:w,fl I IIS'I ~ ~ ClaN I 1 I AN IS I 1tCNAICIAIIS '1 SC INI IC I A I4 fOSL".NI, Cuafau futuIAL NfAD Cturf>>UL Ol. I IT ltl Itu.'ICIAI>> I OIISATOA I/SNITT IICI* ICL I LI C ~ I C I L' tII AIL'I I ASSI.II'TUCVAI ll'Ia LUI. SIN lua OtL>>A'lua LICw'll OL Cc>>IAUL utlAA1ca CI. OtfaAllra LICL .SL I/SNIT 1 AVAILIA>>lOl laalua I/1ul f1 Figure 6.2-2

A5KNDbMTS TO FACILITY LICENSE OR TECHNICAL SPECZF1CATZONS On May 17, 1977, the Nuclea Regulatory Commission issued Amendment 813 to The R. E. Ginna Nuclear Power Plant Provisional Operating License No. DPR-18 i revising Appendix A, paragrph 4.2 to read as follows:. lnserv'ice lnsnection Aaalicabilit Applies to the inservice inspection of Quali y Groups A, B and C Components, High Energy Piping Outside of Containment and, Steam Generator Tubes. Ob ectives To provide assurance of the continuing s ructural and operational integrity of the structures, com-ponents and systems in accordance with the recuire-ments of 10 CFR 50.55a(g). Saecification 4.2.1 The inservice inspection program for Quality Groups A, B and C Components, High Energy Piping Outside of Containment and Steam Generator tubes shall be in accordance with Appendix B of the Ginna Station Quality Assurance Y~ua3.. This in-service inspection program shell define the speci-fic requirements of the edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI, which are applicable for the forty month period of the ten year inspection interval. The program ten year inspect'on intervals sha11 be 'based on the following commencing dates. The inspection interval for Quali y Group A compon-ents shell be ten year intervals of se vice commenc-ing on January 1, 1970. 4.2.1.2 The inspection intervals for Quality Group B and C Components shall be ten year intervals of service commencing with May 1, 1973. The inspection intervals for the High Energy Piping Outside of Containment shall be ten year intervals of service commencing with May 1, 1973. The inspec-tion prog am aurirg each third of the first inspec-tion interval provides for examination of all welds at design basis break locations and one-third of all welds at locations where a weld failure would result in unacceptable consequences. During each succeeding inspection interval, the program shall provide for an examination of each of the design basis break location welds, and. each of the welds at locations where a weld fa'lure,would. result in unacceptable consequences.
4.2.1.4 The inspection intervals for Steam Generator Tubes shall be specified in the "Inservice Inspect'on Program" for the applicable forty month period. com-mencing with thy 1, 1973. 4.2.1.5 Inservice Inspection of ASME Code Class 1, Class 2 end. Class 3 components (Quality Groups A, B and C) shall be pe formed in accordance with Section XI of the ASi~Z Boiler and Pressure Vessel Code end applic-able Addenda as required by 10 CFH 50, Section 50.55a (g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50 55a(g) (6) (i) ~ Basis: The inservice inspection program provides assurance for the continued structural integ ity of the struc-tures, components and systems of Ginna Station. The prog em complies with the ASIA Boiler end Pressure Vessel Code Section XI "Rules for Inservice Inspec-tion of Nuclear Power Plant Components" as practicable, with due consideration to the design and physical access of the structures, components end. systems as manufactured, end constructed.. This compliance will constitute an acceptable basis for satisfying the reauirements of Genere1 Design Criterion 32, Appendix A of 10 CFR Part 50 and, the requirements of Section 50.55a, paragraph g of'0 CFR Part 50. On June 1, 1977, the iNuclear Regulatory Commission issued Amendment 814 to the R. E. Ginna Nuclear Power Plant Provisional Ope aCing License iNo. DPR-18, revising Appendix A, Table 3.5-1, page 3, paragraph 3.13, Table 3.13-1 (new), . Table 4.1.2 Paragraph 4.6.1, Paragraph 4.13, Paragraph 4.14 (new), Table 4.14-1 (new) to read as follows: 3.13 Shock Sunnressors (Snubbers) Annlicabilit Applies to the operability of all safety-related. shock suppressors (snubbers) listed in Taole 3.13-1. Ob ective: To specify the recuirements or operability of shock suppressors (snubbers). Snecificetion: 3.13.1 The reactor shall not be made critical unless (1) ell shock suppressors (snubbers) listed in Table 3.13-1 are operable. Continued hot shutdown or power operat'on is per-mitted. for a period up to 72 hours wi hout the conditions of 3.13.1 being met. Zf the conditions of 3.13.1 are not met 'n the 72 nour per'od, then the reactor shall be in a cold sh tdown condition within the next 36 hours. Basis: Shock. suppressors (snubbers) ar'e required to oe operable to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and follpwing a seismic or other event initiating dynamic loads.
I TA 3.5-1 iiC. o," 'll PL:: iQS .-"."~-.. r J .~ % ~Of>

!C, of Chli~Z~m 'KGnK OF ~~ ~ ~

l ~ AI t) l4LI

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FUNCTIONAL UNIT Ci"!liELS TC TRIP R>IU'lD CY "0 N DITIC: S i'4 ala l L

17. Circulating Hater P'lood Protection

a. Screenhouse Power operation ma be continued for a period of up to 7 days with 1 channe inoperable or for a period of 24 hrs with two channels inoperable.

b. Condenser Power operation ma be continued for a period of up to 7 days with 1 channe inoperable or for a period of 24 hrs with two channels inoperable.

NOTE 1: Hhen block condition exists, maintain normal operation. l' F o t'ull Power Not Applicable If both rod misalignment monitors (a and b) are inoperable for 2 hours or more, the nuclear overpower trip shall be reset to 93% of rated power in addition to the increased surveillance noted, If a functional unit is operating with the minimum operable channels, the number of channels to trip the reactor will be column 3 less column 4. A channel is considered operable with 1 out of 2 logic or 2 out of 3 logic.
0 ble 3 13-1 Safotv Related Shock Su ressors Snuhhers Accessible or Especially Inaccessible }/igl~ Radiation** Difficult to Snubber [hark Ho. Piping S stem (A or I) Zone Remove SGA-l "A" Steam Generator Yes Yes SGA-2 "A" Steam Generator Yes Yes SGA-3 "A" Steam Generator Yes Yes SGA-4 "A" -Steam Generator Yes LA SGA-5 "A" .Steam Generator Yes I fO SGA-6 A".Steam Generator Yes SGA-7 "A" Steam Generator SGA-8 "'A" Steam Generator Yes

~ 5J 0 SGD-l "D" Steam Generator Yes Yes SGD-2 "D" Steam Generator Yes Yes

r 7. Table 3, 13-1 (Continued) Safet Related Sho k Su r ssors Snubb~ers Accessible or Especially Xnaccessible lfigh Radiation"

Difficult to Snubber i~lark No. (A or I) Zone Remove SGB-3 "8" Steam Generator Yes Yes SGB-4 IIB I ~

Steam Generator Yes Yes SGB-5 "8" Steam Generator Yes Yes SGB-6 "8" Steam Generator Yes Yes SGB-7 "8" Steam Generator Yes SGB-9 "8" Steam Generator Yes FH-3 "A", Feedwater No No FH-5 "A". Feedwater No FH-25 "A" Peedwater No No
Table a,l3-1 (Continued) o Sa fet Related Shock Su ressors S~oubbors Accessible or Especiall Xnaccessible IIi.gh Radiation** Difficult t Snubber .'lark iVo. (A or I) Zone Remove AFH-25 "A" Aux. Feedwater No APK-2 6 11 A 11 Aux. Feedwat r No No AFW-27 "A" Aux. Feedwater No AFH-28 ."A" Aux. Feedwater tlo No AFW-29 "A" Aux. Feedwater No No AFH-49 "A" Aux. Feedwater No PH-9 "8" Feedwater X No FW-30 Feedwater t4o Ho FH-80 Feedwater A No No FW-Ol Feedwater No No IID sl FeeCwater Ho No

/f/

0 Table 3,l3-1 (Continued) Safety Refuted Sbock S~u res sors Soubbers Ac~essI.ble OE Especially Xnaccessible 33igh Radiation*~ Difficult to ."-.nubb Hark No. Piping Sys Lax> (A or l) Zone Remove FW-83 "B" Feedwater .'lo No AFW-10 "B" Aux. Feedwater A No AFW-13 "B" Aux. Feedwater 13o No MS-2 "A" Main Steam No Yes II Yes MS-3 AII Main Steam No I 3'1S-2 2 "A" .1ain Steam No No MS-7 "B" Hain Steam 31o Yes Its MS-8 "B" Main Steam 13o Yes ct'4 No 0 MS-146 '(Top) II B II h1ain Steam MS-,146 (Bottom) :"B" 3lain Steam
Table 3;la-1 (Continued) Safet Belated. Shock Su ressors Snubbers Accessible or Especially Xnaccessible )Cigh Radiation** Difficult t:o Snuiiber Hark No. (A or Xj Zone Remove HS-147 "8" Hain Steam No Ho MS-140 "B" Hain Steam Ho Ho MS-159 "B" Hain Steam Ho Ilo I HS-160 "B" Main Steam Ho No PRZR Relief Yes No jC-2 PRZR Relief X Yes Ho I CC-3 PRZR Relief No 11-4 PRZR Relief r CC-5 PRZR Relief Yes No H-6 Relief 'RRR Ho CC-7 PRZR Relief X Yes Ho PRZR Relief Yes No

Snubbers may be added to safety related systems without prior License Amendment to Table 3.13-1 provided that a proposed revision to Table 3.l3-1 is included with the next License Amendment request.

*" Chdificatlons to this table due to changes in high radiation areas (during shutdown) shall be submitted to the HRC as part of the next License Anendment r'equest.

TABLE 4.1-2 iMN~~H&1 FREQUZNCIES FOR EQUIPVZWZ AK) SAKLING TESTS FSAR SECTION TEST FREQUENCv R~RENCE

19. Circulating Mater Calibrate Each Refueling Shutdown Flood Protection Zquipment Diesel Generators

b. Automatic start of each diesel generator and.

automatic restoration of particular vital equipment, initiated by an actual loss of AC station serv'e powe supplies to-al'ormal gether with a simulated safety in)ection signal, This test shall be conducted du"ing each refuel-ing shutdown to assure that the diesel-gene ator will start and, following maximum breaker closure times after the initial starting signal for trains A and B will not be exceedede A B Diesel plus Safety In]ection 20 sec. 22 sec. Pump plus RHR Pump All breakers closed.'0 sec. 42 sec. Shock Sunnressors (Snub'hers) Applies to the operability of all shock suppressors (snuboers) listed in Table 3.13-1.

~ot ective:

To specify the requirements for 'nspection and func-tional testing or shock suppressors (snubbe s). Snecifications: Visual Insnections: Each hydraulic shock suppressor (snub'oer) w'th seal material fabricated from ethylene propylene or other materials demonstrated. compatiole w'th the operating envi onment, shall be determined operable by visual inspection in accordarce wi h the inspection schedule in Table 4.14-1. Initiatior. of the T ble 4.14-1 in-spection schedule shall be made assuming the unit was previously at the 12 month irspection irterval. The initi 1 inspect'on shall be performed wi hin 12 months of the effective da e o this spec'ficateon.
Each hydraulic shock suppressor (snubber) with seal material not fabricated from ethylene propylene or other material demonstrated compatiole with the operating environmen shall be determired ope able

.at least once every 31 days by a visual inspection 'of the snubber.

The inspection of the hydrau1'c shock suppresso s (snubbers) 'n 4.14.1 and 4.14.2 shall be a visual inspection and shall include inspection of the hydraulic fluid reservoir, fluid connections, and linkage connections to the piping or steam genera-tors and. anchors. Shock suppressors (snubbers) in 4.14.1 may be cate-gorized into two groups, "accessible" and "inacces-sible". This categorization shall oe based. upon accessibility for inspection du ing reactor opera-tion. These two groups may be inspected indepen-dently, but in acco dance with the applicable schedule. inspections performed. before that interval has elapsed may be used as a new reference point to determine the next inspection. Howeve, the re-sults of such early inspections performed before the original required time interval has elapsed (nominal time less 255) may not. be used to lengthen the required inspection interval. Any inspection whose results reauire a shorter in-spection interval will override the previous schedule. A hydraulic shock suppressor (snubber) is considered to be operable if the fluid reservoir level and the installation are in accordance with the manufactur-er's instructions. Functional Tes in During each refuel'ng outage, out at least once during each '8 month 'nterval a representative , sample of at least 10 hydraulic shock suppressors (snubbers) or 10$ whichever is less, of all shock suppressors (snubbers) listed in Table 3.13-1, shall be selected and. functionally tested. These hyd aulic shock suppressors (snubbers) shall be tested in accordance with the original manufactur-er's test requi ements. Hyd aulic shock suppres-sors (snubbers) greater than 50,000 lbs. capacity may be excluded. from functional testing require-ments. Hydraulic shock suppressors (snubbers) selected. for functiona1 testing shall oe selected
on a rotating basis. Hydrau3.ic shock suppressors (snubbers) identified as either being "especially difficu1t to remove" or in "high radiation zones" may be exempted, from functional testing prov'ded they we e demonstrated operable 'during previous functional tests. Hydraulic shock suppressors {snuboers) found inoperable cur'ng functional testing shall be restored. to operable status prior to being returned. to se~ce. ror each hydraulic shock suppressor (snuboer) found inop-erable during these functional tests, an edd'tional. minimum of 10>> of ell hydrau3.ic shock suppressors (snubbers) or 3.0, whichever is less, sha32. also be functionaM~y tested. unti3. no more failures are found. or e11 hydreulic shock suppressors (snubbers) have been functionally tested. The hydraulic shock suppressors (snubbers) are requized to be opera'ole to ensure that the structural integrity of the Reactor Coolant System and, all other safety systems is maintained. during and following e seism'c or o her event initiating dynamic loads. The only hydraulic shock suppressors {snubbers) excluded. from this inspection program are those installed on non-safety related systems encl then only if their failure or failure of the system on whicn they are insta13.ed. would have no adverse effect on any safety related system. The inspection frequency applicable to hydraulic shock suppressors (snubbers) containing seals fabricated, from materials which have been demonstrated com-patible with their operating environment is based upon maintaining a constant level of protection. Therefore, the reauired inspection Interval varies in-versely with the observed failures. The number of inope.able hydraulic shock suppressors (snubbers) found during an inspection determ'nes the time in erval for the next required inspection. To provide further assurance of hydraulic shock suppressor (snubber) reliability, a representative sample of the instal-led. hydraulic shock suppressors (snubbers) will be functionally tested during each refueling shutdown, but at least every 18 months. Observed failures of these samples will requ're functional testing of addi ional uni s. To mini-mize personnel exposures, hydraulic shock suppressors {snubbers) instal'd. In high radiation zones or in especially difficult to remove loca Ions mey be exempted rom functional esting requirements provided 0he opereoility of hydraulic shock suppressors (snubbers) was demonstrated, during functional testing et eithe the completion of their fabrication or at a subseauent date. Shock Suuaressor (Snubber) lnsaection Schedule Number of. shock suparessors (snub'oers) found, inoperable during Next required insaection or durinz insuec ion interval insmection interval Q 18 months + 25'~ 12 months + 255 6 months + 255 3or4 124 days + 25/~ 5, 6, or 7 62 days + 25$ 31 days 250/ NOTE: The above reguired inspection interval shall not be lengthened more than one ster at a time,
FACiLlTY OH PROCEDURE CEAilGES REQUlRDiIG NRC APPROVAL There were no procedural changes during this reporting period that reauired prior approval by The Nuclear Regulatory Commis-sion.
TESTS AK) r~ERMEHTS REQUlRZHG NBC APPROUAL There were no tests or experiments during the reporting period which reauired prior eppro~e~ by the nuclear Regulatory Commis-sion. OT~r, CHAi'AGES TESTS A%) EX&EH iPZV~"S S stem Modification SM 75-22 System Modification SM 75-22, inflatable Seal Hing. Presently a flat stainless s eel plate is used to seal off area between the reactor vessel and the reactor cavity during refueling. Due to leakage from this seal, preparations were made so an inflatable ring could be used. to provide a better seal. A Saxety Evaluation was performed and it was determined. that the possi-bility ox an accident is not increased. A change in the Plant operating Technical Specifications is not necessa.y. S stem Modification SM 75-39 System Modixication,SN 75-39, Modification of Main Steam Isolation Valves. This modification changed. the disc and disc s op ox the-valves to allow the disc to be ~~ly horizontal when in the open position. This modification also included installation of a larger actuator system. This should help prevent spurious valve closures. A Safety Evaluation was performed and it was determined that the possi-bility of an accident is not increased. A change in the Plant operating Technical Specifications is not necessaxy. S stem Modification SM 75-41 System Modixication SM 75-41, Full .low Condensate Demineralizers, This modification included the installation of demineralizers, condensate booster pumps, and associated equipment to allow 100/i condensate processing to im-prove secondary side water purity. A Safety Evaluation was performed and it was determined that the possi-bility of an accident is not increased. A change in the Plant operating Technical Specifications is no necessary. S stem Modif'ation SM 75-45 System Modification SM 75-45, Waste Evaporator Feed. Pump Control System Modification. This modif'cation included installing a low level shutoff of the waste evaporator feedtank for the'ecirculation pump. This pxovi-ded assurance that the pump would stop during dxumming of the waste when the tank was nearly empty. Presently there is a no level indication in the area the operator is stationed du"ing drumming, A Safety Evaluation was performed and it was determined that the possi-bility of an accident is not increased. A change in the Plant operating Techn'cal Specifications is not necessary.
S st m Modi ication SM 76-13 System Modification SM 76-13, Sprinkler Head Relocation. This modifica-tion involved relocation of the sprinkler head in the stockroom and various shop offices to provide better fire protection for these a eas. A Sa ety Evaluation was performed and it was determined the the possi-bility of an accident is not increased. A change in the Plant operating Technical Specifications is not necessa y. S stem Modification SiM 76-24 System Modification SM 76-24, Air Ejector Modification. This modification involves replacing the in-line monitor, that has been subject to failure due to moisture, wi h one that is ext:ernal to the piping. All eouipment for this radiation monitor including 'the readout module were replaced. A Safety Evaluation was performed and it was determined that the possi-bility of an accident is not increased. A change in the Plant operating Technical Specifications is not necessary. S stem Modification SM 76-2 System Modification SM 76-29, Main Feedwater Pump Becirculation. This modification involved installation of piping and valves to increase the recirculation capacity of these pumps from 8'o 254. This is to be used during startup and shutdown of the pumps. A Safety Evaluation was performed and it was determined that the possi-bility of an accident is not increased.. A chenge in the Plant operating Technical Specifications is not necessary, S stem Modification SM 76-30 System Modification SM 76-30, Grinnell Protomatic Valves. This mod'ication involved replacement of the sleeve valves with piston type valves in the fire system. he piston valve is a vendor recommendation to improve relia-bility of the system. A Safety Evaluation was performed and it was determined that the possioil-ity of an accident, is not increased. A change in the Plant operating Technical Specifications is not necessary. S stem Modification SM 77-01 System Modification SM 77-01, Auxilia~ Boiler Conversion. This modification involves temporary installation of a fuel supply tank and necessary piping to allow the house heating boile to burn oil due to a shortage of natural gas. A Safety Evaluation was performed and it was determined that the possi'oility of an accident is not inc eased. A change in the Plant operating Technical Specifications is not necessary.
S stem Modification SM 75-57 System Modification SM 75-57, Spent Fuel Pool Rack. This modification involved removing the existing racks and. installation of a nigher dens-ity rack to increase spen fuel storage capacity to 595 assemblies. A change in the Plant Operating Technical Specifications was necessary . and was approved by Amendment 811 to License DPR-18. S stem Modification SN 75-58 System Modification SM 75-58. Spent Fuel Pool Cooling. This modification involved relocation of the spent fuel'pool. heat exchanger suction and dis-charge piping to insure better cooling of the spent fuel assemblies in the new high censity racks. A Safety Evaluation was performed end it ~as determined that the possibil-ity of an accident is not increased. A change in the Plant operating Technical Specifications is not necessary. S stem Modification SM 76-05 System Modification SM 76-05, Nestinghouse Monitor Rack. This modification involved installation of a seismically restrained steel rack to. housa. vibra-tion monitoring equipment in the Control Room. A Safety Evaluatioh was performed and it was determined that the possibil-ity of an accident is not increased.. A change in the Plant operating Technical Specifications ' not necessary. S stem Modification SM 76-08 System Modification SM 76-08, Sump Tank Pump Discharge Piping. This modi-fication involved installation of piping and valves to provide an alternete discharge rrom the existing sump tank pumps. This new discharge piping is designed to provide a means for pumping the contents of the sump tank to temporary waste water processing eauipment. A Safety Evaluation was performed and it was determined that the possi'bil-ity of an accident is not increased. A change in the Plant operating Technical Specifications is not necessary. S stem Modification SM 76-11 System Modi ication SM 76-11, Spare 812 Transformer. This modificet'on 'n-cluded the installation of a transformer. Zn the event of a failure to,~12 transformer, the electrical connections can be made to allow use o the spe~e. A Safety Evaluation was performed and it was determined that the possibil-ity of an accident is not increased.. A change 'n the Plant operating Techn'cal Specif'cations is not necessary. S s em Mod'ication SM 77-03 System Modification SM 77-03, Boric Acid Piping Modification. Due to a leak found in this system, it was decided to replace certain areas of Scnedule 10 piping with Schedule 40 and reduce areas of high stress. Also, a portion of the system was rerouted to a more accessible area to allow closer surveillance of the piping.. A Safety Evaluation was per ormed and it was determ'ned that the possibil-ity of an acc'dent is not increased. A change in the Plant operating Technical Specifications is not necessary. S stem Modification SN 77-04 System Modification SM 77-04, Manipulator Crane interlock on Hoist-Up Circuit. This modification involved installation of an interlock on the hoist-up circuit so this contact cannot be made uMess the grippe" is in the engaged position or the weight indicator reads less than the weight of a fuel assembly. A Safety Evaluation,was performed and it was determined that the possibil-ity of an accident is not increased. A change in the Plant operating Technical Specifications is not necessary. System Modification SM 77-05 System Modification SM 77-05, Personnel Hatch Packing input Keepers. This . modification involves addition of restraine s on the teflon packing shaft seal nuts which are on the handwheel shafts of the containment personnel airlocks. This will prevent the packing gland nut from rotating with the handwheel shaft, thus preventing the nuts from loosening and allowing leakage. A Safety Evalaution was performed and it was determined that the possioil-ity of an accident is not increased. A change in the Plant operating Technical Specifications is not necessary. S stem Modific tion SM 77-07 System Modif'cation SM 77-07, Hydrogen Storage Boom Modification. This modif'cation involves ins allation of explosion bolt releases on the wes wall of the H2 and Co2 bot le house. This will provide means for instant pressure relief from an explosion in the room. A Safety Evaluation was performed and it was determined that the possibil-ity of an accident is not increased. A change in the Plant operating Technical Specifications is not necessary. S stem Modification SM 77-08 System Modification SM 77-08, Full Length Control Rod Sampling Resistor Modification. This modification concerns the 19 unused stationary coil current regulation sampling resistors in Powe Cabinets lAC, 2AC, 1BD, and 2BD of the Full Length Rod Control System. Fault current in any one of these unused sampling resistors could cause tne inadvertent drop of two to three rods. Vestinghouse Nuclear Service Division has the efore suggested that the feedback wire on the lower end of each unused resistor be removed. The wires are to be connected to ,he neutral bus, which 's the neutral of the 4'ire, 260 VAC supply from the rod d ive M. G. sets, and is common to he upper end of all sampling resistors. A Safety Evaluation was performed and it was determined that the possibil-ity of an accident is not increased. A change in the Plant operating Technical Specifications is not necessary. S stem Modification SM 77-0 System Modification SM 77-09, Relief Valve Diaphragm Modification. This modification involves changing the diaphragm material n the operators of valves PCV-430, 431A, 431B, and 431C to a more suitable mater'l for the environment. A Safety Evaluation was performed and it was determined that the possibil-ity of an accident is not increased: A change in the Plant operating Technical Specifications is not necessary. S stem Modification SM 77-11 System Modification SM 77-11, Divert Line Relocation. This modificat'on involves relocating a section of the letdown divert line to allow easier maintenance and repair on the piping. A Safety Evaluation was performed and it was determined that the possibil-ity of an accident is not increased. A change in the Plant operating Technical Specifications is not necessary. S stem Modification SM 77-12 System Modification SM 77-12, Encore Thermocouple. This modification in-volved relocating three thermocouples from the discharge of the fuel assembly area to the top of the reactor head. This was performed to pro-increased data on the reactor vessel upper head fluid temperature. 'ide A Safety Evaluation was performed and it was determined that the possibil-ity of an accident is not increased. A change in the Plan operating Technical Specifications is not necessarv. S stem i~Iodification SN 77-l62l System i~fodification SM 77-1621, Computer to Control Room Recorder. This modification involved installation of cable and recorder so the Control Room could have a recording of any parameter addressable on the computer. A Safety Evalaution vas performed and it vas determined that the possibil-ity of an accident is not increased. A change in the Plant operating Technical Specificat'ons is not necessary."
CORRZCTZVE Y>iiVVtAHCE OF SAFETY RELATED EQUlPMKNT Ml.'CIIANICAL AND ELECTRICAL MAINTENANCE NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULTS CORRECTIVE ACTION lA Main Steam Isolation Corrective N/A Gasket Leak Steam Leak at Covex Sealed using turmanite Process ! Valve Joint EM-152 lA Charging Pump Corrective N/A Leakage increase at Repacked east gland, M-ll.4.1 east gland leak off and M-11.4.6 1C Safety InJection Pump oxrective LER-77-01 Weak spring in Pump failed to Replaced //2 secondary contact. Bus 14 Breaker secondary contact start on first M-32.1. attempt during monthly surveil-lance .test lA Main Steam Isolation orrective . N/A Gasket leakage Rein)ected gasket area with Valve 3517 "Furmanite". Used EM-152-lA Waste Gas Compressor 'orrective N/A Unit stalled out at Checked out seal water piping 80 psig for blockage. ) Fire System Valve 5171 .orrective N/A Cast yoke cracked Valve bonnet yoke was replaced. Procedure M-64.1 was used. NIS Channel N-41 power :orrective N/A N-41 drawer out Redundant measure- Recalibrated NIS Channel 41. range 77-301 of calibration ment N-41 reads high.
MFCllANICAL AND ELECTRICAL MAINTFNANCE NATURE OF LER OR OUTAGE l lALF UNCT ION EQUIPMEifC MINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION BC4S-H-17-Component Cooling Corrective N/A Alarm setpoint Heading high with Ad)usted alarm level set to llater Monitor MR 77-393 drift no alarm proper value. 1D Gas Decay Tank Rupture Corrective Slow leak from tank Replaced rupture disc. Disc. back to vent header Isolated per Procedure S l(.2.13. 1A Charging Pump Corrective N/A Packing wear Leakage at packing Replaced charging pump stuff-TC-77-616 gland ing box assembly using M-ll.4.1 and M-ll.4.6. n Acoustic Leak Detection Corrective Calibration Drift "Caution" would not Performed PT 19 (calibration System clear on Point //5 of system). l Valve NCV-133 (Residual orrective N/A Transducer drift Valve leaking thru Calibrated and adJusted cur-lleat Removal NX to Demin- m 7V-622 rent to air transducer. eralizer) Pressurizer Power Operated orrective N/A Seat was cut Leaking through Inspected and installed new Belief Valve 430 internals and cleaned up gasket seating areas. 34
MECllANICAL AHD ELECTRICAL MAINTENANCE NATURE OF LER OR OUTAGE MALFUNCTION EQUIPMEHT MAINTENANCE NUMBER CAUSE RESULTS CORRECTIVE ACTIOH "A" Charging Pump Corrective Stuffing box Leakage Hepacked Stuffing Box. needed repacking "B" Boric Acid Tank Corrective Boron Buildup Plugged Valve Cleaned valve and replaced Sample Valve 3308 diaphragm.

"A" Boric Acid Tank Corrective N/A N/A Leaky bonnet Heplaced diaphragm and com-Sample Valve 330A pressor.

Steam Generator Tubes Preventive LEH 77-03 See steam genera- See steam generator Approximately 2200 tubes were Eddy Current tor'eport report checked in each steam genera-Inspection tor. Sludge lancing 'performed in both generators. Sludge profile determined in each generator. l3 tubes in "A generator and 1 tube in "8" were plugged.-

"A" Diesel Generator orrec'tive Leaking through Hebuilt valve.

Solenoid Valve 5907 "8" Steam Generator Blow- 'orrective N/A Seat Cut Excessive leakage Inspected and lapped valve. down Isolation Valve 5737 past valve MECIIANICAL AND ELECTRICAL MAINTENANCE 1 NATURE OF LER OR OUTAGE MALFUNCTION r E UIPMENT MAINTENANCE NUISER CAUSE Rl?SUI.TS CORRECTIVE ACTION Main Steam Power Operated Corrective Seat Cut Leaking through Inspected and lapped valve. Relief Valve 3410 "B" Loop Sample Valve 955 Corrective N/A Bad Gasket Valve leaking Replaced gasket. I.etdown orifice valves Corrective Bad. Gasket Valves leaking Replaced gasket. 200B and 202 Chemical Volume Control .orrective N/A N/A Damaged Valve Replaced Valve. System Letdown Vent Valve during XSX Ilydro. 2234.

"C" Charging Pump 'orrective N/A Belt Near Belt Failure Replaced belts.

r {Varidrive) Control Hod Drive Cables eventive LEH 77 04 Deterioriation of Inoperable control 28 cables replaced. During (K-7, L-8 inoperable) ables under rods physics testing, two vere adverse condi- found svitched. Made proper tions connections.

"A" 5 "B" Containment Preventive N/A N/A Motor inspected .- nev bearings, Spray Pumps Varnished "A" motor.

MECllANICAL AHD ELECTRICAL lfAINTENANCE NATURE OP LER OR OUTAGE lfALPUNCTION E UIPMEHT MAINTENANCE NUMBER CAUS E RES Ul.'I' CORRECTIVE ACTION "A" Steam Generator Blow- Corrective N/A Bad Seat Excessive Leakage New seat installed. down Xsolation Valve 3730 Hydraulic Snubbers AFW Functional N/A Snubbers not Bleed rates and Properly set lockup velocities 10, 27, 28, 49 Testing properly set at lockup velocities and bleed rates on units. factory unacceptable Containment Purge Supply Corrective N/A Xmproper ad)ust- Excessive Leakage Ad)usted seats. and Exhaust Valve ment on rubber seats Broken operator Would not operate Replaced spring. spring Diesel Generator Solenoid Corrective Welding'lag in Mould not operate Cleaned and rebuilt. Valve 5907 valve properly "A" Diesel Fuel Oil lligh Corrective N/A Float Broken .. Mould not operate Repaired level float stem and Level Switch properly linkages.

"C" Safety Infection Pump Corrective LER 77-07 Poor'ontacts Failure to start Multi-amp test and- replaced Breaker off of l3us 14 secondary contacts.

I Main Steam Power Operated Corrective N/A Seat Cut Leaking through Lapped valve. 'elief Valve 3411 Main steam to Turbine Corrective N/A Faulty Clutch Xnoperable Replace with spare limitorque. Auxiliary Feedwater Pump Assembly limitorgue MOV 3504 HECllANICAL AND ELECTRICAL MAINTENANCE NATURE OF LER OR OUTAGE MALFUNCTION EQUIP11ENT llAINTENANCE NUH13ER CAUSE RESUI.TS CORRECTIVE ACTION Boric Acid Filter PI-100 Corrective N/A Failed diaphragm Leaking Replaced diaphragm. Cutoff Valve 349B "A" Charging Corrective of dia-Pump N/A Pieces Pump Replaced valve disc and "0" phragm from valve delivering'pproximately 1/2 rings in pump suction flow. Charging Pump Discharge Corrective LER 77-09 Inadequate weld Pinhole leak Meld cutout and reweld. to Relief Valve 204 buildup on socket weld Auxiliary Spray to Pres- Corrective N/A N/A Packing leak Repacked valve. surizer Valve AOV 296 Charging to "A" cold leg valve 3928 Corrective N/A'/A Packing leak Repacked valve. Gas decay tank reuse valve Corrective Piece.'-'of steel Leaking through . Removed piece of steel 1632 caught in valve lodged in valve. Safety In)ection Pwnp Corrective LER 77-12 Crud buildup Stuck open Cleaned and inspected. Dischar'ge Check Valve 809A Steam Generator blowdown orrective Cut Plug Excessive leaking Replaced plug and stem. Isolation Valve 5730
HECIIANICAI. ANU ELECTRICAL HAIN'fENANCE NATURE OF LER OR OUTAGE MALFUNCTION EQUXPHENT 11AINTENANCE NUMBER CAUSE RESULTS CORRECTIVF. ACTION Pressurizer Liquid Space Corrective N/A Cut gasket Bonnet leak Replaced bonnet, gasket. Sample Valve 953 "B" Containment Spray Corrective N/A Torque setting Valve failed to Increased torque pressure Discharge Valve 060D too low close setting, Charging to "B" cold leg Corrective N/A N/A Packing leak Repacked valve. valve 294 "B" Steam'Generator Corrective LER 77-08 report'eaking See steam tor genera- tube Approximately 400 tubes Eddy Current tested. 5 tubes plugged. Rod Control System orrective N/A Blown fuse in "Urgent Failure" Replaced blown fuse. 2AC cabinet Alarm Boric Acid Filter Bypass orrective LER 77-16 Diaphragm failure Excessive leaking Bonnet and diaphragm assembly 'alves 390A and 390B. from bonnets replacement. l "B" Loop Smnple Isolation :orrective N/A Leaking through Cleaned and inspected. ! Valve AOV 966C "A" Charging Punp :orrective N/A Excessive leakage Stuffing box assembly replace-ment.

-'39-

HECIIANICAL AND ELECTRICAL HAIN'l'.ENANCE NATURE OF LER OR OUTAGE HAIFUNCTION E( UIPHENT HAINTENANCE NUHIIER CAUS E RES UI.TS CORRECTIVE ACTION Blender supply to Refuel- Corrective N/A Failed Diaphragm Bonnet leak Diaphragm replacement

, ing Mater Storage Tank Valve 365A "A" Steam Generator hydrau Corrective ,'ic snubber"; LER 77-13 Seal failure Excessive leakage, Replaced seals and tested 2 on nort;h- loss of fluid in seals. 'ast corner reservoir I

Rod Position Indication orrective N/A Drawer D-10 failed Turbine runback Replaced HPX drawer and relay System causing CR 9 re- coil. lay coil to burn out Reactor Protection System 'orrective N/A Relays HT -2 and Relays dropped out Replaced relays. RT 4 had open oil circuits

,'B" Charging pump discharge Corrective LER 77-18 Defect during Leak Ground out defect area and ', line to relief valve 284 eld installation repai.red. Performed pene-l trant test to verify repair.

I B C ha rg in g Pun > p Corrective Stuffing box leak- Installed spare stuffing box. I I I ing ~ I I I "B" Diesel Generator Tie Corrective I LEH 77-19 ent secondary Failure of "B" Tested, cleaned and replaced Bus 16 ontrol contact diesel breaker to ( secondary contacts. close onto Bus 16

-4O-

MECllANICAL AND ELECTRICAL MAINTENANCE ) I I I NATURE OF. LER OR OUTAGE MALFUNCTION E UIPMEHT MAINTENANCE NUMBER CAUSE RES UI.TS CORRECTIVE ACTION ','C" Charging Pump Discharge Corrective LER 77 Porosity or start/ Leak in weld Installed, new section of Drain Line to Valve 292E stop on initial piping. weld root pass NIS-42 Power Range Corrective N/A Blown fuse while NC-306 Iligh Range Replaced bistable. checking overpower Bistable failure . setpoint "B" Motor Driven Auxiliary Corrective N/A Cut seat Leaking through Installed new spring. Cleaned Feedwater Pump Relief and lapped valve. Valve 4022 "C" Charging Purnp- Corrective N/A Varidrive belts Replaced belts. Varidrive broke "A" Diesel Generator Corrective LEB 77-21 Governor set Failure of diesel Reset governor. improperly to achieve rated power Radiation Monitoring Corrective N/A Burned out Drawer inoperable Replace transformer. System B-6 transformer I I I 1 Fire System Corrective N/A Fire booster tank Valve Cycling Rebuilt positioner. I fill valve posi-tioner defective I
MECIIANICAL AND EI.ECTRICAI. IIAINTENAHCE NATURE OP I.ER OR OUTAGE MALFUNCTION EQUIPMENT HAINTEHANCE NUMBER CAUSE RESULTS CORRECTIVE ACTION I

"8" Steam Generator Snub- Corrective LEB 77-22 Seal wear Excessive leakage Heplaced seals and pressure

, ber 8-4 snubber declared tested unit. Procedure I inoperable M 40.7. Meld leak down stream of Corrective LEB 77-25 Poor'initial weld Pinhole leak Hepaired weld per EM-191. non-regenerative heat exchanger, ad)acent to Valve 2048 Steam line Atmospheric Preventive & N/A Leaking Solenoid Air Leak Performed PT-20.1 (Control Air Power Belief Valves Corrective galve on "8" System Integrity Test) on valve. CV-56 and CV-57. Heplaced solenoid valve for Valve CV-57 ("8" Valve). Hadiation Monitoring Corrective Defective Drawer Spurious alarms Heplaced with spare drawer. I System H-2 Containment MB 77-2659 & without meter mov-ing upscale Bod Control System Corrective Outage Number "Urgent Alarm" in Could not withdraw Beplaced defective printed 127 28D Power Cabinet Hank "D" circuit 'cards. I

'orrective i Bod I

Control System "Urgent Alarm" in Could not withdraw Heseated printed 18D Power Cabinet circuit cards. Heactor Protection Corrective . N/A 8istable PC-469A "Steam Generator Heplaced bistable. System failed Lo-Lo Pressure single channel alert" alarm MECllhNICAL AND ELECTRICAL HAINTENANCE NATURE OF 1.ER OR OUTAGE MALFUNCTION E UIPHENT l lAINTENANCE NUMBER'AUSE RES UI.TS CORRECTIVE ACTION RllR Piping near Valve 718A Corrective LER 77-26 Improper seal veld Pinhole leak Weld repaired per RM-192. on threaded. nipple during construc-tion "8" Charging Pump Corrective . N/A Normal Wear Varidrive failure Rebuilt varidrive per M-ll.4.4. Valve 252 RC filter outlet Corrective N/A llydro on HHR Leaking diaphragm Replaced diaphragm yer to HIIR heat exchanger System M-37.16A. "8" Charging Corrective Varidrive belt of charging Pump N/A Loss Replaced belts. failure flow "3" Charging Pump orrective N/A Varidrive belt Loss of charging Replaced belts. failure flow "C" Charging Pump orrective N/A'ormal wear'ncreased packing charging Hepacked pump. pump leak off rate NaOll Spray Additive Valves orrective Valves not seat- NaOll leaking into Cleaned and lapped seats, 836A and 8368 ing tightly RWST ad)usted valve stroke per M-37.55. Valve CV 58 (4561) Cooling orrective Defective Solenoi Valve could not be Replaced solenoid coil. Service Water to Contain- reset rnent 43
Instrumentation and Control E ui ment hlaintenance NATURE OF LER OR OUTAGE HALFUNCTION Equ IIhIENT hIAINTENANCE NUhIIIER. CAUSE RESUI.TS CORRI;CTIVE ACTION Boric Acid Tank Levels Corrective N/A Partial Plug LT-102 8 LT-172 Performed PT-21. Beamed out all Drifted High sensing lines. Boric Acid Tank Levels Corrective N/A Partial Plug IT-171 Drifted High Performed PT-21. Heamed out all sensing lines. I Boric Acid Tank Levels Corrective N/A Partial Plug LT-102 Drifted High Performed PT-21. Heamed out all sensing lines. 'oric Acid Tank Levels Corrective N/A Partial Plug LT-172 Drifted High Performed PT-21. Heamed out all sensing lines. . NXS Channel N-41 power Corrective N/A N-Irl Drawer out Hedundant measure- Hecalibrated NXS Channel 41 range of Calibration ment N-41 reads high HILS-H-17-component Corrective N/A Alarm setpoint Heading high with Ad)usted alarm level set to cooling water monitor drift no alarm proper value HMS-H-19-steam genera- Corrective Check source box Heading was high Freed up check source box lever. tor blowdown monitor lever stuck Boric Acid Tank Levels Corrective N/A Partial Plug LT-106 Drifted 1{igh Performed PT-21. Beamed out all sensing lines.
Instrumentation and Control E ui ment Maintenance NATURE OF I.ER OR OU1'ACL'UMBER 1IALPUNCT ION rqUIP ME~rr l IAIN1'ENANC E CAUSE RESUI.TS CORRECTIVE ACTION Acoustic Leak Detection Corrective N/A Calibration Drift ~ "CAUTION" would not Performed PT-19 (calibration of System clear on Point II5 system) Fire System Corrective N/A Pire water tank Fire service booster Hepaired fire water tank level level control pump would not controller. malfunctions start automatically Boric Acid Tank Levels Corrective N/A Partial Plug LT-106, LT-171, 8 Performed PT-21. Heamed out all LT-172 Drifted High sensing lines. Valve HCV-133 (Residual Corrective N/A Current to air Valve leaking thru Calibrated and adJusted current Heat Removal IIX to transducer drift to air transducer. dernineralizer) I Boric Acid Tank Levels Corrective N/A Partial Plug LT-171 was high Performed PT-21. Reamed out all sensing lines. RMS-H-15-air eJector Corrective Moisture in detec- Failing Low Dried out connector and detector. monitor tor connector Fire System Modification N/A SM 76-30,1 Modified Grinnell deluge valves to insure operation. RMS-H-15-air eJector Corrective N/A Pre-amp connector Spikes High Dried out pre-amp connector. monitor damp 45
Instrumentation and Control E ui ment Maintenance NATURE OF LER OR OUTAGE MALFUNCTION EQU IPMEI'ff MAINTENANCE NUMBER CAUSE RESULTS CORRI.'CTIVE ACTION ! RMS-H-15-Air eJector Corrective N/A Defective Detector Beading High Heplaced detector and recali-monitor brated. Boric Acid Tank Levels Corrective N/A Bad tubing fitting LT-102 would not Performed PT-21. Beamed. out all come off zero sensing lines. RMS-R-15-Air eJector Corrective N/A Defective Detector Heading High Replaced detector and recali-monitor brated. Hod Control System Corrective Blown fuse in Urgent Failure Replaced blown fuse. 2AC cabinet Alarm Rh!S-H-13 and H-14. Corrective N/A Low-Flow Low Flow Alarm Replaced pump. Auxiliary Building gas and particular monitors Fire Mater Storage Tank Corrective N/A Air leak in level Fill valve cycles Repaired air leak. controller open and shut HMS-H-15-Air ejector Corrective N/A Faulty Detector Reading High Replaced detector and recali-monitor brated. HMS-H-15-Air ejector Corrective N/A Faulty Detector High Alarm Replaced detector and recali-monitor brated. HMS-B-15-Air ejector Corrective N/A Moisture in con- Failed Low Dried out detector and connector. monitor nector Instrumentation and Control E ui ment Maintenance NATURE OF I.ER OR OUTAGE HALF UNCT ION EQUIPMI?NT MAINTENANCE NUHIIER CAUSE RESUI.TS CORRECTIVE ACTION Bod Position Indication Corrective N/A Drawer D-10 Turbine runback Replaced HPl Drawer and relay System failed causing coil. CR-9 Relay coil to burn out Reactor Protection Corrective N/A Relays RT-2 & BT-4 Relays dropped out Replaced relays. System had open coil circuits Boric Acid Tank Levels Corrective Partial Plug LT-171 was high Performed PT-21. Beamed out all sensing lines. Doric Acid Tank Levels Corrective N/A Partial Plug LT-106 was high Performed PT-21. Beamed out all sensing lines. HIIS-B-15-Air eJector Corrective N/A Bad Detector Reading IIigh Replaced detector. monitor Doric Acid Tank Levels Corrective N/A Partial Plug LT-171 was high Performed PT-21. Reamed out all sensing lines. BMS-H-15-Air eJector Modi fication Performed SM-76-24.3. Replaced monitor H-15 with a new unit. Boric Acid Tank Levels Corrective N/A Partial Plug LT-172 was high Performed PT-21. Reamed out all sensing lines. 47
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.E,JC>> VSg- -(Gb~ R~OR S Durir the reooz i-g oe"iod of Janua"y 1 1977 through Dece be"

total of 26 events, classified as Reportable Cccu-rences, 3'977, took 'Glace reouiring sucm'l of Ericensee Avant Renor s o she (LRC ~

<h foD~ owing is a compil<ation of narrative descriptions oz 'hose events:

77-01 "C" SZ Puma ca ed. to Start 1-03-77 During monthly testing, the "C" ST. numb =e,'led to staN manually zrom the Bus'4 breaker on the f'st attemnt. The contro'witch was reset and the pump started on nex th ee attempts. it also started successully from bus 16. This incident is similar to 7 events involving bus 3.6. Complete inspect'on of circu't or Z~ ". and all circui ry '.. "close" circu~ -as made. The only pro'olem found -as a wea'r. spri..g in a secondary contact assembly which would have caused inte~ttent fau3.ty operation. Circuit brea'<er is Westinghouse i>odel DB-50, 600V A. C. Contact assembly was replaced,. Pump will be started, weekly ~4th bus 14 breaker until the next scheduled mon hly surveillance test. iVo danger to the health and. welfare of the general puol'c was identified. 77-02 Reactivit Znsertion Curve Used for Safet Anal ses 2-17-77 As a result of review of a"alyses methods, West'nghouse notif'ed. RGB thet reactivity insertion c "ve, PSAR Pig. 14-1, used. for safety analyses is not su ficient3.y conservative. All ransients were re-eva3.uated using revised. curve. Westinghouse determined that there was no impact on any transients except loss of flow trans-ient Eor which 1.30 minimum DNBR criterion is still met. iso danger to the health and welfare of the general pub-lic was identified.

='~... 77-03 Abnormal Degradation oE Steam Generator Tubes 5-02-77 Dur'ng the pla.~ed ".ddy Cu ." nt inspection of the S e Generator (SG) tubes, 13 tubes 'n the "A" Steam Generator and 1 tube in the "B" Steam Generator showed. defects above the wastage criteria of 40$ . These tubes have been plugged,. Eocaliz d. corros'on of tubes caused by conc n-trations of residual phosphates. A complete Pddy Current prog am d sc ption and repor". is at ached. Vo da.ger o the health and. welfare oz the general public was 'denti ied.

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77-03 (Attachmni3.0 pages) ( fpnl c; St!I%! 10IIO I 'I .I:iI.'C '.'1 Final ~?c"..crt Ha J l 1, 1977 Ol ~ +$ Q QQ$ 1P(~ ! eCI '! ~ <<<<O<<<<+<<Q <<h+ lns. ec t'c o" >>!irma S a 'on

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stoa%.. '..e o s

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9 77

~ ~ "3, 1977 in accc='ance '>>'-'"-.". the instr; 'o .-.s.- ec ion P<<c>> 5- as ul>> c= thc This inspect'". cons'stcc.'= e.'", c ="ont ..~~inatio;.s 1hl "C.'PP<<<>n410>>cl ~ I oe>>>> 8>>4>>cv<<44o ~

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'. C'gP<<<<<W<>0<<

o<<>><<<<q, ' ! <>rw VI A-Znlet 25:-:E!<< S<<dgc <>

1731 405 ~ ~ Qe<<Oct <> 1 if'00 IQ ec>> 'L 14S 6 ~ 125 400: i:" Qc 100 400 ~ ~ ! 6th 207 C uI POI << 60 100 R'ft Defect hend A-Outlet 195 25:- ilt S';,e 1st 268 400 i:H" DQ Qct 6th 100 400 KH Vent 6th 207 3.5 RHt >u. po. ts
~~A f lj~~
Tubes Precueecv Ccecc...-. u It e c B" Znlet 195 25 KHz Sludge 1st 1252 400 KH2 Defect 1st 148 400 YHz Defect 125 400 E:E!z Oe e-t U"bend 70 400 KE!z Dent 5th 100 3e5 i!:z Support 6th 60 100 KE! z Defect U-bend EE Os 195 25 i:Hz S'dce 'st

'I 208 400 F.E! Defect 6th 100 406:-:E! 4 Des 6th 100 3. 5 KYz Support 6th ,~

Resu)ts o hese exa;..inaticns re ven 1n F ~ c urnS 3 !"hich inc'"des he "A" in'et ."d "he ls, 'z a.sd c' e~'s respectivel.:. ' h'es !1) ard (2) of thi s ro~o"" a "~ 'ncluced C ' for coo.boa s ~ .. o ~ p he las .ivc C stea.-.. c:cncratcr 'nsoec ~'ors All or the ecdy c rren- ind ca-icns were wi "L'~ I ~ ~

""e "'"st ~

in ew inches cf tub'ng direct)y above the tube shee" with the ex-ceotion of one in the V-hend a"ea of tNee "S" s tear.: generator.

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This indica ion in the "B." stean generator 0-bend area was on a per1phery tube and appears to be a one-of-a-kind construction-type defect of very small vo3.u.-.,e, 95% through t'e tube wall. The other incications with the exception of two, are postdated to be due to wastage, based on growth rates. The exceoted two

-52"

~es, in the "A" inlet, due to their large growth rat< co-"pare to the rean, ~ay have been caused "y concentrations o ccustics ~

Confirmation o~ his is not poss'ble s'ce the eddy current wxardnation r.;ethod cannot differentiate between 'nc'ications resultin- fzo> either was "aae or stress co zcs on cracking, but

~

can accuratelv ."..easure the:.-. x'.-..ur.. c'.efe " pen rat'on no~i st t's"'cal varia<<icn. The indicat'ons are seen cn'y 'n those areas>>here indica 'ons have been ore icus'y noted, wi h ..e exce tion cf the ind'caticn in the "3" s ea;.. ce..e ator i-bend area. There has been no expans'on o the 'ncication rea'n 'to other areas of. the stea.-.. cererators. 'Th's irspection ver' ed that there are

~

not any other "~ bes with ZD hindi ation 'n the pe rq cs ewer'ubes associated with the wedae areas where the e had been a leak ir. t ~ ~ k april 1976 I (see Licensee Even" Report 76-15) . The, cien evalua ion progra., "er o=. ed on bo .". steaa generators revealed no dents above 10 rils wi h cn'y a few of the tubes 'n each gene ztor being involved. Along with "Ne cent evaluaticn suooort -'a e intearit; exa;..'rat'on was per or.-..ed which P program, a ad not eveal ar.y prcble.-..s. The s;..a3.'1 ru~2er o tubes in he "A" inlet which have ex-er'ncec. deterioration, 'nconsis ent with the average, are bel'eved to have deteriorated from the concentrat'cn o resicual phosphates. in the ,secondary.s'de sludge deposi"s. .he e concen r tiors '.o phosphates

/

are caused by the er..aining tra es o s ludae deposits omed during the period of phosphate control of the secondary syste.-.. water cherastry before the conversion to A'i cheristry cont=ol 'n Noverker 1974.
"emoval nf residual phosphates from the secondary side over the Past 33 mon hs cf operation has been accomp3.ished by continuous*'. st .am cererator blcwdown and high pressure water 'ancing. The high pressure water Lancing pe formed on the secondary side des '.. d to c.-..ove as;..uch o f the s L udge as poss ib ', 'ich contains the undesirable residual phos."hates anc/c" caustics. BLcwdcwn sc.-..ples taken during normal c.-erat'n indicated cnly snal'mounts c hospha es .-. esent, al";"o'"-". ohos ".ates 'n the slucge could "eve t back into PG :- anc concentrate on '.".'e tube su aces which, depending on the ...clar rat.'o, would resu' in acidic or caus ic attack cf the tube. The corrective action taken tn cns rc the ccntinued rel'abilitv of he steam ceno "a ors 'ncl des the folio:;incr: ALL tubes wi tl; edd, curr nt in" cat'ons o waLL penet=a-tion greater than or ecua'~ 40'. were ~Luc~ed,;' A thorcuch 'ancina of t~e seco..derv side o he tube sheets was performed in beth s'am generators to remove as much as possible any remaining phos. n--tes and/or caustics con-tained within the sludge,"::Sludge lane'ng of beth steam generators wi31 be con i'n 'e". in an effort to keeo sl.udge content to a minimus . "" he lancing, cot pled w'h "lowcown during sta"tup and nor.-..al opera ion, shou'd considerably reduce the probab'i v o" signi 'cant tube degradat'cn during the plants'ubsecuent operat'on.

c. In addition, a mod f'cat'on of he plant's seconder~/

concensate sys ter,. is nder construction which 's de" signed to insure that the feedwater entering.'the steam genera ors " ll be o he highcs pu 'v ~ ".'his n.odif i-cation '~ill adc in-'.'ne de."..ine all=era o the condensa e s) s e a schec ~ ed +0 P . o aced 1 service i Augus" o ""'s vea" Scca se '" has been esca 'ished tha= all but li tubes fro'-- both stea.-.. ge.-.erators had less than 40$ cefect indications; because the=e were c.".'y e..oerience co;..=arati:elv ra"id deg aca 'on; anc: baca se s'u""e lancinc should further reduce the I'a'e prc" ab'itv c= "hosphate anc " .stic pcc):etn for...ing, <<hc s <<caw.a ge"e"- c"s he Jla ...e ons c e <<acc-e:uel'.c o" a e

':r~

the znser:;ce .~ns"eA" on the 1978 re=.cling.o="a~e,....:

'ith <<n A for ~

tho stea.-., genc=ators

<<AA 0 <<<iaate', -i'4 '.".-accordance 1

TADI E (1) EXi611NATION DATE STEiQ1 GENERATOR INDICATIOtVj. POSITIOtt "- ., SIC',('4f~ 'j FED; .1974 NOV;. 1974 ttAR.:1975 'ED.- 1976.: ",APR. 1977

"'i!~'-Qg'.- 329 -.<'631 '; ~ 230 ') .730 2'A.'jc4 '>) . 63: 59 59: 39 "iL" IN ET 25"'29 '30-,34.

50 3G;; '. 46 31 47;" 50'. 31 37 23 8 194 0 5;: 8* ll* lp, ~ 12"" )

~

3 Total "A" ht Inlet Tubes Ex'unined,; Each Inspection at 400lltlZ 3260'655 3192 " ..2003 STEA."l GEtlEBATOR:; a = ~ ",:..., ItlDICATION-.'.i 4 ~"

',- EXl81INATION DATE .p i'..

~ POSITION . . 'SIZE(4) FElf'.;1371. P.j.NOV 1974 ttAR. 1975, FED. 1976 APR. 1977

~

IAII :< 20 278 l. ~ ' 10 113 20

'-58"'Urt.EV , 0 0 O.t-.' 0 . ~ '* 0 ~,

Total "A" Outlet Tubes Examined 430 442 3192 268 ht ':ach Inspection at 400KIIZ tubes were explosively plug<Jell
1 TABLE (2) STElN GENERATOR INDICATION EXAHINATION DATE POSITION SIZE(%) FEB'974 NOlf, 1974 MAR. 1975 FEB. 1976 APR. 1907 'I

. ~ <

20-24 20 21 490 13::25...

.411 ".,~'9' - ~ . 764 719 '.,5 3 .12 ~ ID@

l 25-29 2 4 10) '8'::: .'i' 0;::,.';0i>> ;.3 30-34 0 1 '0 INLET "35-39

,40-44 .4'5-49 0 . 1 0 ....* ~ ';"i>>','.)30':

1 0, 0

~

iL 50 : 0 0 " - l5" ~ Total "B" IhlfhSTubes At Each Insphjtion at Examined 400 KllZ

'75 I'090...

193l 3247 1525 C STEAN

, ~ J' GENERATOR'NDICATION ...". .'OV. ' ~ '"' "" i'- 'EXAMINATION DATE POSITION'"':' SI<L',('L) . FEB. '1974 1974 '!1AR. 1975 FEB. 1976, jJ',APR 1977 "D". '

OUTLET.'

~ ~ 'i,. .j',-.;;5"20'.:

i~ 2o '::.' I'"..., 4 0 0 0 1003 2 s 1'; 90. j* Total "B" Outlet,';-.'(iiboU.'1;xami11ed 5j'6-,::. " ' At Each Inspection:nt 300.'KIIZ ~,; =' 39 442 3247 260-C" J, l.

NOTC: Two tubes in the "D" steam generator were explosively plugged in January 1976 and fifteen in April 76

TUBES HERE EXPLOSIVELY PLUGGED

I Nl E

'(-.gOX 'Yo 59 le FQD+ CLjRQQNT'NDlCATlONQ 1 ~

jI g JQ fo TO 59 fo yl~

< - Cr)O/o TO7'9 /a ><<< ~te>83 Cenerlltar D-Boy To eo.y, gl 8061L3OKBtl'IlllbH7I I:)LlL5lbll A515553510')C7'I5C'52II393735333I 29272523211917 l5 l3ll 9 7 5 3 I .S COLUMNS I )l1Wg BI 10 H L1 Lo Is St 54 51 sI't t4 ll X.L~S 2 I8 16I4 I2 I 864 2 2

S r 3

~ ~ l ss ~ ~

I ~ I S I

~

44 41 4Q

~~

38 38 I LQ 35 34 CO ~ t 33 223 32 30 28

~ ls 26 2Xl ~."i I ~ S 'Jl I

22 2g 21, i8', IS' I5 6: S S3j I 7

~S /~

i

~ ~

2

~l." ~ ~ ~ ~ ~ ~ ~2 Ql ~ ~ ~ ~

S( Jlg ~ SOS~ q Ss Sl ll 33)ills SI 3 (SsJQI Ss ~ S SS SS ~ Sl ISIS's ~ ~ I

~S iW).~Q ~ SS pl "3 S '3"3 gV )

I.='-( " '- 5.

..."t)i S St 5 QISC 1 BOAS:.

M4f ) tjghy N022LE ~
X- ZQT-'TO '59 lo HLCT. I ~ ' ~ e-40%TO 59 /. DoDY'upRe.NT t ND)cu,T~ord ~ c r n"lo TO'7CI lo t 'll :*= Prl go r. To 90/- Itt'tl; I:tclm Crltcrstor -\

'll ')t I

t116ltr'OKIlll'57t L'J L1 LSD Ltr'l51 5S 555I1'I414545 3 ( 4I 3937 35333l 292725232I I9I7 I5 l3 II 9 7 5 3 I cot uM~s '. qg I I I

}y.rr>' .6 I4 )Z lO 6 LL Lh Ll I.O 'S4 5l '< 44tI tC ) SL31 lL .42 I6 I4 l21 06'i 2 I I~ III ~ ~ ~ ~ ~

4~ I Ir I

~ ~ 4 ~ A~

I ~ 3

~ ~

40 33( 4i C-D t 3l 30 27 26 22 2(

~

g I~ I7. IG ISI (3: l2 II

~ ~ IO 9.l ' I3 7j 5'. \~ I I I~ ' L I 2

r-I I II ~ I ~ II~~ ~ 1&I ~ ~ >~ r

~ ~ ~ W I I ~ ~ ~ ~

LJ I

~ I H I)oe ~ ~ ~ I I ~ ~

ROAN>

~ ~ ~- Ma('(Vue(' $L ~

LZl&.~ g-%0/ %le% '/ ~ Q-40% I059 1', EDDY coRRt-:NT ~NDlmTioN

-GO /c TQ l 9 /a .~ggt) =l, ~ ~

J T Q -QoVe To 9c)9o IISIL Stcca Ccccrntor

~g / ~ 'II O'I81IQMQI1011751'bll L9L1 V~LELIM5155535I4'l4145434I 393735333I 292725232II9I7 15 l3ll 9 7 5 3 I COLuMNS ',

QQ,'IC ~ 81 1C 14 12 10 8 CL I 1 C2 C 4'1C44 IR I SL51M5 7.L IO l6 l4 I2 I 864 I

')0 C'. ~ 1 451 c

1 ~ ~<

~~ /1 11 40 30 ~ ~ 36 ~ Q 4 ~ ~~ ~1 .34 33'0 29 ~ ~

26 25l 22 23j 2l ) Ia I7 J

/ ~ ~ ~ 9 .I 5 .;

3. P i s"2 ~' LhV

)~rJ I

Xi: 1

't ROWS .~-M~r >ega NOZZLE 4

Lw 77-04 Cable Reversal for Tvo Control Rods 5-23-77 During initis~ cover esc>>tion to 505 foll.cwing refueling, a seres of flux maps reveal d. a lux ancmally. The Unit was tmen to hot shutdown+, e3.ectricians verified reve>>sered cover and rod zosition indication (H':) cables and restored cab3.es. to prope a.range ent. Du"ing installa-ion of nev control rod, pc'-er cables at reactcr head,, control and HPZ cables fo" rods L-8 and 4-7 ve e erroneously interchanged, A ter proper restoration, lov pover physics tes 'ng was contin-ued. and bank D ard. C vorth were =casu ed. aga'>>. Proper rod, response vas veri 'ied by control rod. exercise and further flux maps. During any future maintenance a. Q. C. ver'f'ca-tion of power and. HP3: co'oles ~1 be pe formed when cables are replaced. CAB >>26 vas issued to. document these act'ons. iso dange" to the heal h and, welfare of the gene"al publ'c vas identified. iER Reactor Coolant Chloride Concent.ation Ezceedins Stead 77-05'-20-77 State Limit During heatup after refueling, reactor coolant samp3.e showed 0.16 chloride. Standby mix d.. bed. deminerali.rer vas put in se Ace; sample f"ecuency vas increased. Chloride concehtrat'on retu ned, o below 0.15 ppm in 17 i.ours. Helease of chloride from old bed. of resin. iso further action .o pr-vent recurrence is necessa~. Ho danger to the hea" th and ve'a>>e of the genera'uolic vas identified. 77-o6 "C" Char ing Puma Varidzive 6-3.9-77 During nor al round,, auc'li g cperator noticed "C" charging pmp varidrive be3.t (1 of 2) smohng. T¹ "A" Charging Pump vas inoperative. steed. The "C" pump vas""~stopped and both belts vere replaced. The belt is US ectrica3. Motors Vari-drive par" 84-2. No fu>>ther corrective action vas necessary. iso danger to the hea h and. welfare of the gene al puol'c -as identizied.
77-07 Bus 14 Breaker for "C" SI Pumo 6-29-77 During the tes , the "C" SI pu p failed o star from bus 14 oreaker on 2 attempts. The pump vas s a. 'ed successf~~y vith bus 16. Suosecue tly, the ous started on bus 14. This 'ncident is sinil~" o 7 events involving bus 16 and, 1 eve t vi.th bus 1". A replacement breaker was ested and installed. In-spection of the circui breake" evealed no appe "en cause for failure. P e circuit breoMer is Westing-house Model DB-50, 500 V. A. C. It &3.1 be retu ned to Westinghouse for further investigation. No danger to the health and welfare of the general public vas-identified,. Lrz 77-08 "B" Stean Generator Leok 7-05-77 Durirg normal operations he air e)ector and. blo~do~w radiation. monitors alarmed. Analysis of the "B" Steam Generator blovdovn ve ified iodine activity from a calculated leak rate of 0.006 gpm. The leaking tuoe was loca ed. with a hydros atic test, and eddy current testing vas performed to dete~~ne if a pattern of degradation existed. About 300 tubes vere ex~ned vhich. included. tunes in the area of the leaking tube and. other selected. areas ~~th, previous indications. These examinations revealed four additional tubes, in the area of the leaking tube, vi h solar'(Z)) indi-cations . These four tubes and. the lea>'ng tube vere explosively plugged. The failur of the tube R45C5~ and. the defect indications in tubes R44C55,. 56, 57 a"d 58 are postulated to be caused by stress corros'on cracking from the inside surface of the .ubes. These inside dianete c acks a e theorized to oe caused by a dent at the tube to tube sheet interface vhich induce<, into the tube va11 resulting in cracking, ~"ere 'tress are not any che ical spec'es postulated to oe involved in this c acking ph meme o due to the purity oz the p ?may systen s Rater vhich f 'vs through the tubes

> ~

Corrective action. taken includ,ed eddy cu~ nt exaninat'on of surrounding tubes and tuoes in areas vhere previous inse~ce inspections had revealed sma>> defect indications. There mere no other tubes identifi d,oz those examined, which eM4bited fM~her degradation. T¹refore, the failed tube and four others "4 h solar (ID) indica-tions vere plugged. Pusher investigation is continu-ing with Westinghouse and RGH personne>>nvolvement studying he generic ~rfB tuoe ailur proole'. At the next refueling outag, a inse~ce inspection of th steam ge e ator tubes A3' clud tubes 'he this failure, No danger to the health and velfare oz areo of the g neral public vas identified. 77-09 Chp in Pumn Dischrrr ge Rel i e f Pi'gin Leo 0 7-12-77 During an ope ator inspection, a leak vas detected in the "3" Cha""ing Bxp Dischar" Reli f Piping. arith the Unit at colo. shu down and a redundant pump operaole, the "3" pump was 'sola ed. A proo-able cause vas inadeouate veld bu'ldup on a socket veld during modification of the discharge. Tne pipe to flange veld, vas cut out and repl ced. pe" approved maintenance and velding procedures, and a hydro test vas successfully completed. The present Q. C. program estaolished since the modification, assures proper inspection oz all safety-related. socket velds to require ents of velding specifica-tions. Ho danger to the health and velfare of the ge eral public was identifi d. 77-10 Redundant Serac Water Dischar e Line Su~sort Desia=

'7-13-77 "rr44r See attached. zeport, 4 pages. Ho de ge" to the health and, welfare of the general publ'c vas identified.

EZR 77-1> 'ontainment Fan Cooler Technical Specifications 7-13-77 During. the preparation of a charcoal fil er tes ing Tech.. Spec. change, it was determined that the-Tech. Specs. on Containment fan coolers vere not consistent v'th the design assumptions in the FSAR.. The FSAR gives eouip-ment assumed to operate to reduce containment pressure after DBA as 1 spray punp and. 2 fan coole s. Tech, Specs.. allow 1 of 4 fan ecole s to be inoperaole. n the event of bleckout and one failed Di sel, only 1 fan cooler may 'be immediately a~ailable. Administra-tive controls have been r vised to reau're ope ability of the necessary equip nt, and a proposed Tech. Spec. change is being prepa ed. Vo da ger to the health and velfare of the genezal public was idencified. 77-12 SZ Puma Dischar e Cneck Valve Leakinr 7"13-77 During plant sta~~up, decrease in 1< SZ accumulator level

.was noted. investigation shoved lA SZ pump discharge check valve leaking, allowing vater from accumulator to entez the R'~ST. M~

pump vas isolated .or valve repa'r; redundant systems vere operable. "-~er repair, the pump was tested and. deemed operaole. Ho dange to-the health and. welfare of the -eneral oublic "as identi ied. 44'63- '1, ,4'

~

T?cdundant Servic>> ' cr i)ioch t g ~ . Li ne Supp~ ".. nes i gn T:r ro: Event Pesczin ion Xnstallation of a redundant hous- scrv<<e as part of the high enc gy bacJ fit program began;n 1975 ~ st"uct'on of the line and associated discharge structure d in the s+r system has rot been charged o"'laced. 'n serv'cc. RGsZ wa adv'sod or. July 13, 1.977 by the arc."'ec"'-Cilbe " Associa"es ha '" scd on subsec,uent revie<~ ard analvsis pe" or...ed by thc..., t"e loading trarsnitted ran tne pip~ ng system to thc auxzllarc Lu-.ld-'ng s ruc a tu=e through sucoort Sh-70 could procuce, under des'gn basis ea" h-uakc cordit"on-, stresses in thc st=ucturaZ.suppor= steel in excess o app 1 'ab lc a 1.1owab lc:alues I

, 'W:.Zuly X4'AI. i.nfo.". ec?'- RGaZ t?.at;.four-..ad~mtionaL support-(S"-69, SN-73', ST/-78,, ST"-831- could. p "oduce stresses'in. thc su"port ~ .'den-ivied fo" STI-70". 're'."ously ~,

structure in excess of app1icab1.e aE:lowable,values urde" conci"iors

~

FSAR requires that. the auxiliary bui1ding st. uct~ze be de-r'he sigre" and constru ted as a seism'c struc".u e class 1. Gilbert Associa es design con rol p ocedures require design analysis for safety re'ated rodi 'cati'crs a-. Ginna Station to be completed prior to issuance of construe 'on drawings. Upon notification of this cor. dition bv the architect.'ngineer on July 13, further work on redundant house service ~ater line was stopped ard the architect engineer was in-I structed o initiate a corrective design as weal as perform a eview o" their design contro1. p ogram. The ex'sting house service wa er d's-charge line was unaffected by these redundant service water supports and was operable du"irg this pe"iod.
bauer nes ra r ~

~uring tha Eaf 1'974, the arch'act engineer, {G:.T', bagar. du-

<<g" of ".a rreundant service water piping to tha racuiren.ants of A 'rRq is ued drawings 'or the majority of thc pipe supports ~ <<ese supports. ware installed during L975 with the raraindar, at arden 'pon ical ccncaot, being instal'ad inside tha Auxiliary u ing a:ring 1976. However, it was not ntil tha latter p rt tha GD.I S"-u=t "zL'epartment began c".r l in~ t" a su".cc" c".at

'c' '-.""-~'d cr -"" """ct>>>> bv ~t is "L.~"c o T" '<<c" '9/7 A~'s p o: ~c ."."1 a Qdv'd PGf E "hat addit'anal anal.ys' an.'oss'ra la -por- ro "ificat'o.. o the struct I' ...ight bc required because G gP the added i;,posed pipe support 1.oa 8~ 'GAT:=believed a t t.".' ti.-.e q g, ~ ~

so.".. rani='cation to th structure aa'.neccssjri;,'u" t?.e cond'ion j ' pv vns-sa e a.'on'g as "Na. pipe rciramege~ptj.=.TPerefcra, routine resolution c 'his task continued. th"ough the spring of 1977 sirca. C the line had rot yet been placed in service.. On ZuIy Z2, 1977, durirg a tel.ephone con erence betwe. n a..-'n ars at CA! ard RG&E, tha nature of the pi."e support, leads for S'.!-70 tha i~posed on the struc"ural steal of the auxil'ary build'nc was d'scussed, anc GA! was requested to revie~ their analysis, a'ss"-..in~ that the redundant service wate Lire was en"'tv. C~'~! info- ad ~vs,< on July 13, 1977, that a prelininary calculation indicated tha" tha allowable stresse at. Sf>i-70 are exceeded ven if 5e'pipe is ar.".pty and snow loads are present during the de ign basis earthquake. irmediate hold was placed on t?:e redurdant serv'ce water line. RGE E was advised by teLephone on Jul.y 14, 1.977, that a total o" ive {5) supports including Sll-70 would have to be a;odified to r.-.eat the design crit ria {i.e., Line in service) . Subsequently, CAT cor:.plated their

-6S-.

v:iis ']d i s sued "txuctura l s eccl 4x~w i rg.l < 1( Lc l4 i'j i'x 'ting s. I'uc u al s teel a(J t

)'~ a new ~

J ~ ~ 7 d l PG~L'~t j L a thc QIQ '>> 'ca ~ " c;li '"'Lat'ns wcx'c the . C,hc s 4rcs ~as '~ e ei ra'xccedcci wncr ~ e ~ 'c <<n C-~"V)'t sho"ld bc rated hat hc firal analysis "..Ows -:" -~ ~ t! c line was f

-"vcr i'~c'hc structure uclnc'i '

c; 'excessive load'ng c or go" J l avc exec~ p~cc

~ 1 ~ ~

ca't'acted'-

~ 1 ti ~ ~ i<,>e ~ wr ir 'c'<< ~ i i iE ~ 4i ~ t w ii <<apt 4 ~

i 4a~ j el c ~ i ~ co ~ ~ >>ra%i>C4l reo~ q I

<<>5 tna I o4C ra 4 ~ t ~ 44 ~ ~ ~ i P ~ ~ '. 4>> d,i I qi s ~ >>>>L' di >>i+ \'sf( ai i i ex ac -4 ~

v4 $ '<<JQ+ eSlgix O an ' 4lanS I i44I 4+an'a I,l~ l

'r) -,~.'. ' . '

c'<<~ Lc <<i a <or his tvzik 1n Lxc. ' i4 rc Vy\ re a,, ~ << <<a

~ '7 I'q i ce ring I, Qr ace y g <<4-anc1 their at=" .'"=,cnt " ructure. <<t has bean. cancludcc'. by C'.Z an".

that ha" p<<o-cc" procedure:s been ~allowed, adccuate revi<<o the stuart st -turaL "e 'ith as'oc'atc: s 'ppor Load. 'apo cc. ' r.ew I'cdun dx"'c xn vice water line ':ou d h ~e den'"'"'completed ario= to release aii cor.s. "I c t'oa ~ i draw'r qs. Gilbert A'ssacia"es has conduc

~ ~ J ~

h, ed a managenent rcv ew and has conc L.ded th at 1 thi s."inc;"dart is an isalatad

\ ~

non-coealiance with cxis 'nq procedure. To recti y the present situation and to assuxe na ecuzxence Qf this non-compliance, Gilbert has init'ted the Lollow ng action. (L) The technicaL design requirett:ents for the service water l&e supports have been ccripleted, with drawings having been transmitteC for construction on July L8, LS77, An adcLitional review OC the piping riodif3.cationss des des< gned red by b

/% ~

Or G nnn Burin@ LQ ~ S pnr i~i( 4 1S ).z ~ C>> i@i ri~lt:.~;O assure no ether inte.",.~con hw'o .". Sscd ~ rnv i nrem expected to be co...o le ted bv Sea te...".o. 1, 19 77.

- inis trativelv (:.1 1);Crt gas lr e 1d o rc i ndoctr jng e Oct' p O 'CCt On~incgrS en t' >n. tnC1nioe pe +ssignod to )1~ projec in intr csee cent ol bnt:.:oen pro~oct d=sc'"'ine". Gilder. '.". <.'; 0s'cn: ll ~ ". Or.-. nn a:.di t v';.ich <'ill vitri fy i.-.tin.-..entstzon o" co cc 've ec io . ~

RG& ~ C ~ .'lated 'S "g 1 ' tion O~ "'L1e fi"e (5) Sup Orb ...0 wd rcdund=nt so ~ice ."ater line on ~uly 22, 1977. PCeL's Q.' Div sic . ~7h>> lie I( 0 cond" 8 rol oh'p o GPT. co"rect'v. a "'o" pie'. NT ~1L s i::.ty (nfl) dw ~ is
LrZ 77-13 "A" Steam Generator Snubbers 8-02-77 During the check of a 1 gal. reservoir for "A" Steam Generator snubbers reservoir, it was found. empty. Upon testing of the seals, 2 of 8 snubbers showed. excess've shaft seal leakage. During unit cooldown, the 2 snubbers were removed., seals re-placed and pressure tested and the snubbers rein-stalled. The snubbers are Anker-Eolth, rated, at 532,000 lb. tension and compression with displace-ment. less than 1 inch in 20:.min. A new test pro-gram includes .the Steam Generator snubbers. No danger to the health and welfare of the gene al public was identified. LER 77-14 Flux Difference Tar et Band Departure 8-09-77 Following reactor coolant dilution to compensate for Xenon buildup, control rods were inserted automati-cally, causing a departure from the flux difference target band,. Boric acid was added, clearing the target band alarm in 7 minutes. A lette has been issued. to all licensed personnel to remind them to continue to monitor the flux difference immediately after dilution.. No danger to the health and welfare of the general public was iden ified. LER 77-15 Sara Additive Dilution 8-22-77 During analysis of the spray additive tank sample, NaOH showed 29.5f concentration. A =second analysis was performed to verify this. Per PORC recommenda-tion, unit shutdown was started and, NaOE concentra-tion was increased to 30.3'f~. After verification, the unit was released for normal operations. Leakage through a check valve from the RWST. diluted. the NaOE tank. Sample frequency has been increased until valves are repaired at the next convenient opportunity. Leakage has been minimized by increasing ank pressure. No danger to the health and welfe e of the gene al pub-lic was identified. LER 77-16 Boric Acid Flow Path Isolation 8-23-77 ~ During repair of boric"acid filter bypass valves per approved emergency procedure, 1 or 2, boric acid flow paths f om the boric acid tanks- to the RCS was isola-ted. A path from RWST was availble. Shutdown of the unit was in progress. Following diaphragm and bonnet replacements, the flow path was restored. Isolation of valves to be repaired, resulted in reducing numbe" of flow paths. No danger to the health and welfare of the general public was identified. LER 77-17 NaOH Concentration Determination 8-24-77 During review of calculational procedure for NaOH concentration, an error was found and NaOH concen-tration was shown 'to be less than 305 by wt. 50/. NaOH was added to tank increasing concentration to within specification by 1130 hours on 25 August 1977. The procedure was corrected by the Super-visor of Health Physics and Chemistry and reviewed by PORC. No danger to the health and welfare of the general public was identified. LER 77-18 "B" Char in Puma Dischar e Relief Pimin Pinhole Leak 9-04-77 During an operator round, a pinhole leak was detected. in the "B" Charging Pump Discharge Relief Valve Piping. With 2 other pumps operable, the "B" pump was isolated. A subsurface defect in the weld wh'ch was part of past repairs. No inadequacies have been noted in the weld-. ing or liquid penetrant testing procedures. The de-fect area. was ground, cle'aned, checked, rewelded and a, liquid penetrant examination performed per approved maintenance and welding procedures. An inservice in-spection for leakage was also performed. No danger to

~ 'he health and welfare of the general public was. iden-tified.

r~ 77 19 Bus 16 Circuit: Breaker for 1B Zmer enc Generator 9-14-77 During a periodic test of the 1B Bnergency Generator (EG), the bus 16 breaker from EG failed to close. The

,1A EG was placed in service as required. The electri-cians inspected the breaker and found a secondary con-tact finger bent. A new secondary contact section was installed. The bent secondary contact 'nger is be-lieved to be caused by imprope ly return'ng.the breaker to service afte being in. the "rolled. out" position.

Training in proper performance of this operation will be,'given to the Auxiliary Operators. The breaker is a Westinghouse Hode1 DB-75, 3000 amp. 600 volt. No danger to the health and welfare of the general puolic was identified.
LER 77-20 "C" Char in Puma Dischar e Drain Line P'nhole Leak 9-20-77 During an operator round, a pinhole leak was detected in the "C" charging pump discharge drain line. With two other pumps operable, the "C" pump was isolated. The weld was cut out and replaced per approved. main-tenance and welding procedure. Ho danger to the health and. welfare of the general public was identi-fied. LER 77-21 1A Governor Settin 10-07-77 While performing.PT-12.1 Emergency Generator lA, the 1A Emergency Generator (EG) could be loaded no more than 1450 kw. The 1A EG was declared. inoperable, and the 1B EG was placed in service, constituting operation in a degraded mode permitted by a limiting condition for operation (T.S. 6.9.2.b (2). Misread. ing governor hydraulic actuator speed setting and subsequent adJustment by unlicensed operator during pre-start check. Maintenance personnel corrected setting. PT-12.1 was completed satisfactorily. Setting verification was deleted from pre-start pro-

, cedure. Ho danger to the health and welfare of the general public was identified.

LER 77-22 "B" Steam Generator (SG) Snubbers 11-02-77 During a check of the 1 gal. reservoir for the "B" Steam Generator (SG) Snubbers, the fluid reservoir was found empty. Visual examination of the units showecL.unit SGB-4 to be leaking fluid.. During the unit cooldown, the snubber was removed, seals re-placed and pressure tested and the snubber reinstal-led. The other 7 units for "B" Steam Generator were operable. The snubbers are Anker-Ho3.th Division, McDowell-Wel~~ an Company rated at 532,00 lb. comp. and en. with disp. less than 1 in in 20 seconds. Tape. and paint left on shaft by construction may have contributed to failure although no tape was noted in immediate area of seal. Tape and paint was removed from all other shafts on "B" Steam Generator units. Increased inspection and subsequent preven-tive ma'ntenance plans on attached. No dange to the health and welfare of the general public was identi-fied.
~ l II I t g I I It t
LER 77-23 Control Rod Ur ent Failure Rod Sto 11-16-77 During steady load, a rod, control urgent failure 'rod stop alarm lit and auto rod motion was stopped. Unit vas shut down by boration, with rod insertion control available in bank mode. I & C Techs. ex-amined, the involved. circuitry in lBD and 2BD end the logic cabinet. Normal rod dron. pover'abinets, vould not have been impeded upon trip s gnal. Random failure of 2 defective p. c. cards; westing-house slave cycler stationary decoder card, part 83359C62G02, and. slave cycler logic card integrated circuit chip, Motorola Model MC6601 vere replaced. with qualified spares. All potentially faulty connections from logic cabinet to 2BD and cage vere cximped or soldered.. Rod system wes,successfully tested, and. unit returned to operation. Ko danger to the health end welfare of the general public was identified. LER . 77-24 Control Rod Ur ent Failure Rod Sto 11-18-77 During return to full. load after'od control system maintenance,'e rod control'rgent 'failure rod stop alarm lit and auto rod. motion was stopped. rod..inserti'on controlin bank mode.. vere capable of'eing tripped.

'll Unload-ing, for unit. shutdovn vas started by boration with rods When rod stop was cleared during investigation of 1BD pover cabinet unit unloading vas stopped. Stationary regulation failure in 1BD pover cabinet apparently due to loose connectors. This was corrected vhen p. c. cards in 1BD for B and D banks wexe swapped, and urgent failure condition cleared. They vere returned to the original positions with no furthex problem. No danger to the health end welfare ox the general public ves identified.

LER . 77-25 Non-Re eneratEve HX Outlet Pi iri Pinhole Leak 11-29-77 During increased surveillance due to increased activity noted on local continuous air monitor readings a smell

. leak vas found..in nonregenerative HX outlet piping. iso significant increase vas noted on plant vent monitors.

(T.S. 6.9.2.b.(4) Excess letdown was put in, end normal letdown isolated., 1'nclusion in a 2 in. socket, veld during construction. Defect vas ground out and weld was repaired per approved procedure, end dye penetrant exam was performed. As this is considered a remdom fe'lu e, no further ection is reaui ed. iso denge to the health end welfare of the general publ'c ves identified.
LZR 77-26 RHR Puma Leak on Flow Orifice Inlet 12-02-77 During e RHR pump monthly test, a leak vas noted on a flov orifice inlet tep seal welded threaded con.'-. nection. Leak rate was estimated at 3 to 5 gpm at 125 psig. (T. S. 6.9.2.'o.(4). Unit was taken to hot shutdown at Superintendent's direction to iso-late and repair leak es it wes in nonredundant portion of return to RCS. A "Cold Lap" on seal weld applied by construction personnel elloved. leakage when threaded connection began to leak. Defect was ground out and seal veld, repaired. and examined by dye penetrant exam. Hydro et 350 psig wes performed successfully. This system is tested for leakage at 12 month intervals per Tech. Specs. No danger to the health and. velfare of the general public was identified..
OKKR EVEPZS OF IÃ3ZREST FUEL PERFORMANCE Primary system chemistry sampling from January 1, 1977 through December 31, 1977 showed no increases indicative of significant fuel cladding failure. Periodic flux map data and incore program results indicated normal flux dist-ribution and confirmed that hot channel factors were below technical specification limits. Predicted and measured boron concentration at various cycle burn-up intervals were within 20 PPM boron, well below technical specification limits. During this reporting period, the reactor was refueled. Cycle VI was terminated April 16, 1977. Thirty-two new fuel assemblies plus nine partially spent fuel assemblies from the spent fuel pit were loaded into the core. Cycle VII operation commenced May 21, 1977. For major events of interest for the year 1977, see "Highlights" section of this report. Major events during 1977 include the following:

l. 5/23/77 - Inoperable Control Rods K-7 and L-8

2. 7/05/77 - "B" S/G Tube Leak

3. 8/04/77 - "A" S/G Two Inoperable Snubbers

4. 11/04/77 - "B" S/G One Inoperable'nubber 5'. ll/17/77 Inoperable Control Rods

6. 12/03/77 - Leaking Pipe Tap - R.H.R. System Eight fuel assemblies that were located in the K baffle joint core region during cycle VI were transferred to the spent fuel pit for binocular observation.

No unusual conditions were observed which would tend to indicate problems with the internals Q baffles joint.
FUEL DATA The following outline addresses topics in which the NRC has expressed interest:

~Cele Vl ~Cele VIZ Fuel Vendor: Westinghouse (117) Westinghouse (121)

Exxon Nuclear (2) Babcock 6 Wilcox (2) Fuel Loading Data: Core consists of 121 fuel assemblies. Each fuel assembly consists of 14x14 array of 179 fuel rods, 16 RCC guide thimbles and one instrument tube. Active fuel length 142 inches. Core Loading Map of Cycle VII: See Figure 1 Spent Fuel Pit Storage: Licensed storage capacity = 59S Number of spent fuel assemblies in storage = 124 Future Reloads: Cycle VIII reload, 1978 refueling. 32 new fuel assemblies supplied by Exxon 3.1 w/o enrichment 94% TD, pellet density 142 inches active fuel length
C D E F C I J K L i~f K-28 J-11 K-14 13 13 54 75 I I 12 K-25 K-11 K-04 G-10 K-30 K-06 K-26 11 21 R-1.2 20 R-30 85 t(F ~if 12P64 H-05 J-27 J-22 G-31 G-35 G-01 J-07 J-30 H-04 83 57 R-29 SS-4 R-21 70 R-52 44 1 K-1? J-05 H-14 H-09 J-28 G-12 J-18 H-1.0 H-03 J-04 K-20 10 63 22 R-20 72 27 86 55 R-07 45 35 K-32 J-23 H-08 J"32 G-29 E-32 G-33 J-20 H-15 J-24 K-21 69 R-16 84 RS-2 8'1 R-23 68 RS-5 36 R-02 33 SFlif K-27 K-29 G-02 J-29 G-04 D-20 H-20 D-19 G-05 J-14 G-30 K-07 K-08 16 R-28 49 9 39 59 92 66 25 82 37 R-26 60 '270 7 J-31 G-14 G-27 G-09 E-33 H-19 D-28 H-18 E-31 G-13 G-03 G-16 J-10 I 19 67 R-10 56 R-24 12 R-05 76 R-13 64 R-01 38 10 K-22 K-01 G-28 J-21 G-15 D-18 H-17 D-17 G-34 J-16 G-21 K-12 K-09 14 R-03 71 73 65 61 91 30 26 2 58 R-06 47 K-16 J-12 H-07 J-26 G-32 E-30 G-24 J-08 H-16 J-03 80 R-51 34 RS-1 81 R-14 Pr2 RS-3 41 R-27 SFif K-19 J-02 H-11 H-13 J-25 G-19 J-19 H-02 H-12 J-13 K-18 15 18 R-25 48 79 6 23 31 R-19 3 24 H-01 J-17 J-06 G-36 G-06 G-07 J-15 J-01 H-06 17 8 R-11 4 R-15 SS-3 R-18 40 62 K-05 K-31 K-02 G-25 K-24 K-23 K-13 53 29 R-17 50 R-04 74 78 K-10 J-09 K-03 42 7 5 180o i%0 RT1l CYCLE: VII RG8cE GTHNA SThTION XXX XXY = Fuel Assembly Z.D. YYY YYY ii R = RCC RS = Pall. (. LQB8(:h Reel SS =- Second;(ry Source

~i.'o.= F1ov His.er St ('l =- Speci:(l. Fl.o(; lfixer i~!I.".'f = t'ew I:1o(i .'liver -T6-

STEAM GENERATOR INSPECTION During the year 1977 Eddy Current testing was performed on two occasions. A regular program was completed in both Generators during the refeuling outage in April. The plant was shutdown in July due to a leak detected in the B Generator and testing was performed in that Generator only at that time. The scheduled inspection (See LER 77- 03 for complete report) included 2003 tubes in- the "A" Generator inlet at 400 KHZ for wall thickness degradation, 195 tubes at 25 KHZ for a sludge profile, 207 tubes at 3.5 KHZ to verify support integrity, and 185 tubes .were.evamf.ned .over the U-bends (125 tubes at 400 KHZ and 60 tubes at 100'KHZ)': A similar program was performed on the outlet side of the "A" Generator - a lesser number of tubes '(286) being inspected at 400 KHZ and no U-bends were probed from the outlet side. The inspection in the B Generator included 1525 tubes in the inlet side at 400 KHZ for wall thickness degradation, 195 tubes at 25 KHZ for sludge profile,100 tubes at 3.5 KHZ to verify support plate integrity, and 185 tubes were examined over the U-bend. A similar program was performed in the outlet side with a lesser number (208) of tubes examined over the U-bends from the outlet side. The tubes inspected at 400 KHZ are categorized as follows: A Generator B Generator inlet outlet inlet outlet Reguired sample 387 200 445 202 Examined first time Baseline without 1166 155 785 177 E.C. indication Baseline with 837 1 }.3 740 91 E.C. indication Thirteen tubes in the A Generator showed defects greater than 40% and one tube in the B Generator. Eddy Current test results Site: R.E. Ginna Unit /I} Steam Generator A (inlet) Test Frequency: 400 KHZ Date: April 1977 Row Column Type. of Indication Location 17 26 0 D Defect 2 inches above Tube Sheet lt II 17 28 0 D Defect It 18 29 0 D Defect II 19 47 0 D Defect II 19 48 0 D Defect II 20 30 0 D Defect II 22 34 0 D Defect 33 Il 25 40 0 D Defect 3 II 26 44 0 D Defect } II 26 47 0 D Defect 27 49 0 D Defect 1 II 28 42 0 D Defect , II 29 49 0 D Defect }
1 Eddy Current test results Site: R. E. Ginna - Unit !tl Steam Generator B (inlet) Test Frequency: 400 KHZ Date: April 1977 Row Column Type of Indication Location 12 2 0 D Defect at top of U-bend In July 1977 the plant was shutdown due to a primary to secondary side leak in the B Generator. The Tube failure was located in the inlet side at Row 45 Column 54 (by hydrostatic pressure) and verified by Eddy Current testing. Since this tube was located in a wedge area, all wedge areas were tested in addition to about 100 tubes in the area of the tube bundle that had shown some indications during the previous inspection. The leaking tube showed stress corrosion cracking from the inside surface of the tube. Four additional tubes in the same wedge area showed similar defects and these five tubes were plugged. Eddy Current test results Site: R. E. Ginna Unit 81 Steam Generator B (inlet) Test Frequency: 400 KHZ Date: July 1977 Row Column Type of indication Location 45 54 ID Defect at the Tube Sheet 44 55 ID Defect at the Tube Sheet 44 56 ID Defect at the Tube Sheet 44 57 ID Defect at the Tube Sheet 44 58 I D Defect at the Tube Sheet

SUMMARY

OP COV<ZAii&TT INGRATE) IZAZ RAW~ TESTS The Reactor Containment Building Leakage Rate Test vas not per-formed during l977. It is currently expected that this test vill be conducted du ing the 1978 Refueling Outage.
DATA TABULATION

-8o-

i~r ~r. CTRZCAL POWER GENERATTON YEAR TO DATE Number of Hours Reactor Was Critica1 7,569.11 54,038.62 Reactor Reserve Shutdown Hours 49.77 1,101. 09>> Hours Generator on Line 7,490.75 52,518.38 Unit Reserve Shutdown Hours 8.5>> Gross Thermal Energy Generated. (MWH) 11,081,808 68,437,042 Gross Electrical Energy Generated. (KP2) 3,202,384 22,187,860 Net Electrical Energy Generated, (MHH) 3,028,488 20,982,294 Reactor Service Factor 865 Reactor Availability Factor 775 Unit Service Factor Unit Availability Factor 86$ Unit Capacity Factor (using iiDC) 66$ Unit Capacity Factor (using design MVe) 66$ Unit Forced. Outage Rate "Cumulative Data Commencing january 1, 1975
I~

~ ~ ~ ~ ~ ~ ~ ~ 5 ~ ~ ~ ~ 5 ~ 4 ~ ~ ~ ~ ~ ~ ' ~ ~ ~ 5 ~

I II

~ 5 5 5 5 5 5 5 ~ 5 I .' ~

I ~

- 5 o 5 5 ~ ~ I ~ ~ 5 ~ 5 ~ 5

I ~ I I

~ ~ ~

I ~

~ ~ ~ ~ 4 ~ ~ ~ ~ ~ ~ ~

I II I

~ ~

I e i ~
I I ~ I I I I I I I ~+ I I ~ I II I I I 1 . ~ I I I I I II I I

~ I I

I I I II I I I
Paragraph 6.9.1b 2f During 1977 there were 5 forced reductions in power. At no time were releases Crom the plant greater than 10% of the allowable annual limit. During July 5 - 13 outage for a steam generator tube inspection 22 persons exceeded 500 mRem.. The highest dose received by a person was 1400 mRem and other doses were distributed as follows: 500 - 750 mRem 6 persons 750 - 1000 mRem 7 persons 1000 -- 1500 mRem 9 persons There was no excessive exposure associated with 'the'Cher 4 forced power reductions.
Ai&HJAi REPORT k'13 JANUARY 1 1977 THRU DECEh1BER 31 1977 ENCLUSXVZ 6.9.1.b.3 During 1977, Rochester Gas 0 Electric Corporation provided monitoring for 677 individuals. The tabl'e belov summarizes the doses received by individuals during this year. The 2 individuals +ho exceeded 3.0 Rem vere permanent Ginna Sta ion employees and. the maximum dose vas 3.085 Rem. Number of Individuals Dose Ran es (Rem) in each ran e No measurable closure 147 measurable Exposure less than .100 112

.100 .250 70 .250 .500 79, .500 .750 52'8 .750 1.000 1.000 500 99 1.500 2-000 46 2.000 3.000 22 3.ooo 4.ooo 2 4.ooo + 0 h,

PLANT ORGANIZATION MD PZRSONNZL No changes in organization or personnel in 1977.
WLT II O~ceglsg Mlstojna sere JANUAAY FEOAUAAY MAAQI JUNE JULY AUGUST'EPTEMUEA OCTOIIEA NOVEMOEA DECEMOEA

. IOO yo 75 W

K

$O 60 W

IX Ill

+25 I

CD I 0
UNIQUE REPORTS
Review of Condenser Tube Maintenance On January 11, 1977 load was reduced to 50% to allow inspection of 1B2 condenser as indications of leakage were present. One (1) leaking tube was located and plugged. On January 25, 1977 load was again reduced for inspection of 1B1 condenser. One (1) tube was found to be leaking and was plugged. On March 21, 1977 the 1B1 condenser was inspected for a leaking tube after preliminary tests gave indications of leakage in that condenser box. One (1) tube was located and plugged. During the maintenance and refueling outage of April 6 May l977 as many condenser tubes were Eddy Current tested as practical yet not to interfere with critical path items. No tubes which required plugging were found at that time. No further indications of tube leakage were noted in 1977.
Primary Coolant SG Blovdovn Annual Report 1977 Total Eguiv. I Radioactivity Tritium Chloride Floride Oxygen I-131 Boron I-131

"/ '29.02 ~ci/2 .10 ~m <.Ol ~~ci/ ~>8o ~Ci/cc ~MDA Max. g5 -39 January 1-31 Avg. 24.63= .57 $ .05 <.01 ~ 33 . 434 Min. 18;04 .53 (. 05 < .Ol .29 385 Max. 25.19 .67 .Of (. 01 .46 301 Pebruary 1-28 Avg. 22 '5 .65 <.05 <.Ol .35 340 Min. 2o.- 6 .62 <.0 <.Ol 1 2 March 1-31 Max. 25.36 .76 (.05 C.ol C.ol '39 293 .. ( MDA Avg. 22.76 .'fo (.05 .31 240 Min. 18.2 .66 C.o <.01 6 0 April 1-15 Max. 25.54 .78 .14 <.04 2.00 2702 Avg. 15-32 .69 '07 (,Ol o.70 1017 Min. 2.8 (0 < 01 Max. 3.01 .31 .32 (.Ol .032 2270 Q MDA May 23-31 Avg. 0.90 .30 .13 <.Ol .012 1514 Min. 0.010 .2 .0 .01 . .001 6 Max. 2.99 .59 .11 (.01 .164 952 g MDA June 1-30 Avg. 2.21 .50 4. 05 4. 01 135 85o Min. 1.28 .4o 4.0 C. 01 F 100 004 Max. 5 77 .49 ..12 C.ol 10 .150 1130 5.07 E-7 July 1-5, 13-31 Avg. 4-93 .47 .Of Z. Ol Z5 ~

144'180 792 ( MDA I Min. 1.61 .44 .0 <.01 2 MDA Max. 5.93 .67 .14 (. Ol .177 1196 7.12 E-7 I August 1-31 Avg. 4.62 .50 .05 (. Ol ~ 150 743 (MDA Min. 1.1 .40 .0 .01 .12 642 < MDA Max. 5.82 .01 .09 .02 (5 . 170 64o 2.69 E-7 September Avg. 5.04 .74 4.05 (. 02 (5 .154 552 Q MDA Min. 4. o .60 (.0 C. 02 .141 44 < MDA 1-30'ctober Max. 6."ll .08 .11 Q. 025 (5 177 547 1-31 Avg. 5.20 .85 <05 (.02 (5 .161 499 Min. 4.15 .81 .0 C. 02 5 .1 4 o

+.02 E-November 1-30 Max.

Avg. hain. 5.90 4.57 o.76

.99 .77 .60 .Of .02 .01 W. 022 <. 022 g5 45 .176 .143 .o40 909 54o 34 (4 3.15 MDA MDA hoax. 5.90 .83 4.05 <. 02 45 .26o 47o December 1-31 Avg. 5.28 .76 (. 05 (,. 02 (5 .187 326 Min. 4.30 .69 Q. 01 <02 45 .152 263 hQA I = 2.1 E-'f

LEAK TESTS ON SOURCES Tech. Spec. 6.9.3 c Leak tests on sources containing greater than 10 CH3 30.71 Schedule 3 quantities vere made at 6 month intervals. No tests performed on the sources revealed the presence of

.005 microcurie or more of emovable contamination.

APPENDIX A AEPOA'T OF RADIOACTIVE EFFLUENTS (ND Nona Detected) FAOILITT Rucheoter coo 4 electric corporotion DOCKET YEAR 1977 I ~ L IIRIID AELEASES

~QTA ~>j ~22IS ~333 ~D5 j

AI IOI AL RCLCA5C Cue I CS .091& QQ206 . %~90 ~QQ129

~ I Avtoact taKCRIAAIIOu ACLCASIO 3 J&EQL 991&

2/)all LQI - 25& DD&esLIQ ~0&KAID 3&&E32 ~601K ll ~378E ll )AlFIL1L. 5.1IIM2 {') tl uaessaas raKIRIRAIIon octcAsco uCI uL 3.6~ .Sl~ 2-2&&='L 250K-9 Qam 21e.9 ~337E 9 e-s) 1.2 E-I)

2. IRI Isuu IOIAL RLICA5L tualt5 +66 . 0015 12.2 mms ~.k 3.9 sano vas)c Io OIStssaoct rauaa LI'ICSI5 la? le=9 2222Ll &le=I I . 5~2E- a+2e=a

.21K-I Asuu ~

W.&see I.ooe-& tuEI ~ I.loe 6 I.oses 2.ale 9 6.Sle 4 s~ N D .12E-

,OSE-II IID Ng NO 4.057 F.-S S,CQ .-14 &.sae s l~~

L 1.06K& 8.478$ 9.o&es .05E 4 6.13E-4 18$ eL. M239Jik 1 9&9 ek

6. Vuaaut Of OrauISIW ealtn I I ICR5 3 &.92eln ~ 38~9. 6&6~0 6. 7&~89 ~ewQ . 4k TO E76E 10 ~LE19 6&3 El 23 I

7. IDIIorLS RILIA5CIE IIE 5R 88)

II+8 8" u " Il riue I C5 s 6&EIO m9 98elQ QQOU MER~ ~O~ l.n ~IQ>> Nn Nn FAI

.RB9 s I'l 11,9, ~99 ~91 OOUA 290005)9 )

CE-141 . 00002 N.DI ~99913 18 V.EQ~ IIEQ~ N.Q ND N lii Nn .I)t)53s 8 R¹ 103 ¹.O. . 00001 . 00001 ~9999 ~QQI &2 ~00009 99025 .99000 899993 ~n'99915 flD .553B I tt IS/ ,ooosa . 00057 .00029 QQEQ& ilk ~9%~ ..90132 00063 mL4S . 00085 .OT9182

.00578 ~:5.)35 . 000 I 6 .000 I . 00006 9022l 109 ~Q~ML ~0003& 299092 . 00033 . 00008 rn CL.SI EW . t)009 ~QS ~.0 ~ D~ ~9999 ILD.

QQ2sl 99 N.D.

~&l ~QQKIL 99 N.D. N.D . 00109 .OO049 ¹.0.

00977

.DODOS N.D.

99932 89912 RD AQQ999

~09991 Nn 990098 Nn Nn ,99900 3000~0 Nn . 91860 Mls pn ~ es EA ~9993 ~99 QL ~001 ~99992 .00lhS ,00007 F9911 I I ¹8 3L, . OIXII0 . 00002 u9ll229 C

95

-rr 144 ~ ll~n 9 ~n.

N D 0001 M.Q N.D.

~99999 .00051 QC022 .00066 . 000~0 QQQQL ,l}N)02 . 00005 . OIXI16 . 00001 . 00001 NQ . 000046 .999993 ..00002 . 00001 00035 .00160 Ei

8. rfutful of IctssusrAL 5fccslICAIscel Llusl foe loIAL ACI IVIIV RILCA5so (; 001 4001 .009 ~ 012 C.OOI .001 C.OOI .001 .0001 . 002 KR-95 .00069 .00098 .00002 .OOOII .00001 ND,000002 Nn ND .00)711 ~8

.00002 7 ~ E-1 ND .00002 Bo/I/3-140 I

8
Sochcoccr Cao 4 Elcccrlc Corporac(on 1977 I I AIRUORNC RELEASES UNITS

~ r 255~

D. APR. DIN.V

~~I.E-CI AI>G. SEpr ~7~A ~

IJ4 IN~ C OASIS 98lQ 65 .67?xlk 143.91 204.31 50 6 31 1203 x $ 6 I la Ill llxloccNs Cua I CS 3J( L23EK 2.6$ ~I 6~K-4 1:SSY-6 4.2F-7

¹4 >hah 1.32 E-4 95 -5 2~62 E-2 IAIAI tANIIcuxxlc caoss RAoloACIIvl'Iv ( ~,Yl Cualrf 2.3K 6 7.2K 6 8892K 7 7.38$ -6 I.CSE-s 4. I IE-6 2.3 E-S S.1$ -6 S.l E-l 1.76 K-6 ).ole E-S IOIAD filll>686

5. Iulxa tARllculAIc II8055 AIAtllARAoloACIIYICY

~2 4.988-8 -8 '.5$

X.Q3~ 1.5E-S 2.097 2~3 E-e 5.2 F;8 SKb 3 ~ 606 E-7 6.0E-S 2.)E-S 1.3E-s s.seE-S Nn ND ND 6 IIAX686886 88OOCC CAS RCIASC RAIC ~ I SIC 251 1120 ~200. 1770 3QQQ MSQ gQIQ 3630 41.7 12 000 1~ Plucllll of AI'tllcAOII llllllCORI Noaxf CASSCS uxl OCI NIS

. 160 203 ~3)7 699 .366 ~l ao.&2 F669 L669 o48 ~Op>t ~ 136 033 .0$ 5 181 2.77 O,

C. tAN ~ ICuxxlcs Z 001 .025 .001 O. ISulctl NICIASIO6 coal ca tAIIIICINAIIS CS. I 37 NA CA >40

.3 &IEA Kk¹6 2&¹6 Md) I 69E=) 6 ~8- 9 Nll QXZ-7 LM~K-2 89EM L36¹6 1Jl6¹6 I A'1<ED L96F" LA36%3. 2>F~O 3 275M CS I 34 SN $ 9 J629E- 3 II- 5.57¹2 LJ30- I'.16$ -7 9.9)e- N > 3.28¹6 8 ALE6 CO-SS gQ3$ -8 2 82¹6 Mdh¹7. ND 1.65 E-8 4.911 E-6 68AI ucl NS 36NLl-i 2+9$ -4 %32 - 4 25¹3 SEE .538=(6 T30- 2 ISM 9.21 E-$ 4.26 K-s 2.5CI E-2 l82K-4 8.94E-S E.9$ -5 ~8e,-s OK-S . 4~Y 3.92 E 5 2~69 $~3LK-C I I35 CASI S AN $5 961I.DII I

AC ~ l33 MIJXL 33LQQ I98>.408 III~8 28( ox78 j

.427 XE-133>( ~DK 092 NO ND t>D ~RI3 ~68 ~ 32 ~k .13 .06 182 1.266 0 .$ 46 .033 3.761 ~lu- xc >3&

xl-I 35 I. 8 4.$ 5 ~lQS. 3.00

$1 .489 I 95K NO i.Q5 618 .604 26962 .747 ~SS 14.379 All 4l onuus As Attaotal Ale (Stcclffl KJ} .LQO¹L ~.D ~NQA 4. 6 ED> ND ND tlo (dA- .Q LB'2 MS¹L 9~4- ~513$ -7 4 DL668 ELLE I4683 98(LK=& .l>EL .L&5¹&

LJl)- 3 28'38K= 3.10E 7

$ ~02E-7 6.42$ 7 8.11$ -7

3. CIE-7 ND L37k2 ND ND 2.97 E~ } 846 F.-6

. 2 QSEK .3.31¹6 QDIQ¹1 1.11$ -6 6.$ 9E 8 ~(Q ND ND .056 E-6 ~686 Dc=59 J-li)¹&. MQ2¹1 2 09¹8 I(.n ND L62¹7. d.l~>-

(> ~Q J 16K BQ U(Q I(I> 6551&-.M 09 EJI Iln354 J 62SFDM JL68- n M(Q Bo .12 ¹7 8 =23 27- 4.1Y,-7 I 6.25 E-8 4. 7264897. Tu-132 AK IIODN 2.08K 8 2.08 E-8
SOLID WASTE JANUARY 1, 1977 through JUNE 30, 1977 During the siv month period, 10,306 cubic feet of solid waste containing 676 curies of radioactive material was shipped offsite for burial. All the solid waste was sent to the Barnwell, South Carolina burial ground operated by Chem-Nuclear Systems, Inc. Curias Cubic Feet 11 January 0.045 1904" 23 February 0.105 1904>> 10 March 92. 60 15 March 0.062 1352>> 24 March 92. 60 29 March 3.90 368 4 April 2.66 790 11 April 0.118 640 13 April 460. 60 2 May 2.66 556 6 May 6.61 650 12 May 1.84 612 19 May 5.18 558 26 May 4.76 360 3 June 3.63 432 January June Total 676. 10,306 "Spent Fuel Pit Racks (See SM 5$ )
SOLID WASTE JULY 1, 1977 THROUGH DECKER 31, 1977 During this six month period, 2032 cubic feet of solid vaste con-taining 14.21 curies of radioactive material vas shipped off-site for burial. All five shipments vent to the Barn-ell, South Carolina burial ground operated by Chem-Nuclear Systems, Incorporated. DATE SHlPPED CUBIC FEET 5 August, 3.54 4O4 16 September 1.94 368 21 September 2.82 419 28 September 1.96 36O 5 October 3.95 481 July - December TOTAL 14.21 2032
ANNUAL REPORT III'13 JANUARY 1 1977 TO DECiZBER 31. 1977 1NCLUSV1E 6.9.3.a Environmental Monitorin 1977 A summary of the survey results is presented below: (1) (ab) (d) (c) NO. OF NO. OP RESULTS TYPE LOCATION SAMPLES FREQUENCY AVG. MAX. Atmospheric Dust 560 Weekly .138 1.14 pCi/m3 (a) 2 Fall Out 55 Monthly 80.1 451 pCi/m (a) Radiation - F'lm 12 Monthly <10 4 10 .mRem 23 92 Quarterly 16.6 23.4 mRem Lake Ontario Water 205 Weekly 4.8 17.2 pCi/1 Deer Creek Water 2 (b) 17 Monthly 7.0 15.7 pCi/1, Well Water 10 Monthly 9.8 15.6 pCi/1 i~filk 1.6 Monthly .78 9.38 pCi/l(a) Fruit/Vegetables Annual .018 nCi Csl37 Marine Organisms Pish 23 Quarterly 3.36 5.12 pCi/gm 3.83 pCi/gm Lake Bottom Annual No Sediment in Area 6.9.3.a (2) No sample or measurement indicated statistically significant levels of radioactivity above the background, other than Chinese fallout samples. (a) High value caused by Chinese atmospheric bomb test of Se'pt. 1977. (b) One sampling location discontinued in June. (c)'verage without the one high value is 0:21.
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) PhelPt 10 I5 Sampling Station Scale Miles FIGURE; OF RADIATIONMONITORING )I'OCATIONS AND SAMPLING STA'LIONS (Outer Ainle)

G INNA TVlO ONE SITE TIIAEE MILE taILE FOUR MILE AOAO 4'- (. aa SHEpIIEAO AO 0 PUTNAM L 6 AOAO lal Q 0 R 0 C Vl D OAICK CRURCN AO ld 2' A OSSA ROAD O 0 WSW GEELEY AO 4700% 6Y 0lA 0 0I ~ UJ El l 0 Y X L (( Vl ul X l3 ill OEAG AOAO Y cg I- R 4. 0 KENYON AOAO ESE z 0000% GI I- 44 a 0 0 N T A R 0 +ssE

+

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- Locations of daix'y herds within 5 mlles of the p

Ginna react:or.
l 1
GLOSSABY The terms, words, and phrases used in this report are commonly used throughout the nuclear industry, and no special dei'ini-tions or exolanations are necessary.
l, <r f f I J
u>VAL OP~TWC rZPOaT f115 OF R. E. GIWiiA iWV~~ STATION ROCHESTER GAS 6 GZCiiGC CORPORATIO:I 1979 IZCK~ ~10. 5g-2 LICENSE hO. DPR 18
PAGE 1 PROCEDURE W-23.2.2 Containment ,e Procedure PWi 78-2705.

%P-10.1", Qualit Contiol of Countin S stems, PCiN 78-2683.

"GS-3.0 Securit Call List PCiil 78-2679.

~i-il;4:4 Charoino Pum s Vaiidrive Overhaul Unit f/ PH 78-2730.

>PT-13.1.9'alon S stem Testin (Resettin Onl ) S stem Numbers 3

, an , PCiN CS-8.0; D~~ Tours b Securi Guards PCN 78-2706. 'SC-3.15.14; Ginna Station Fire Doors" PCN 78-2685.

"6-6.11; Routine 0 erations Check Sheet'CN 78-2694. PT-23.13B Containment Isolation Valve Leak Rate Testin "B" Steam enerator Sam e 'N PT-23A; Containment Isolation Valve Test Connection Bound Contro P i '"A-54.3, 0 en Flame, Veldin and Grindin Permit PCiN 78-2481.

-9.3; Air Ejector Gas Sam lin 'CN 78-2680.

WC-3.16.11, 0 eratin~ Instruction - Self-Contained Breathin A aratus, PCN
PAGE 2 PROCEDURE PT-13.4;1; 1>>>>ultimatic Delu e Valve S stem Testin - S stem //1 Tur me Con enser Pit, CN PT-13.4.2; >>ltultimitic Deluioe Valve S stan Testin - S stem //2 Tur one Oil Resexvior, FCN PT-'13.4.11 Multimatic Delu e Valve S stem Testin - S stem //ll Ca e Tunnel, PCN RSSP-15.10 IST. H dio Test of Class "B" Pi in, (BHR S stem Lov Pressure RSSP--1'5.1i TSi JI'dio Test of Class "B" Pi in (BHR S stem Hi h Pressure , P iaaf-73.10'eldin PCN 78-2480. ":A-30.3 Plant Procedure Content and Format Re irements'ViJ N>> -67.5 Halon S stem Naintenancem Co uter Room,'nd Rela Room P PT-13.1.9 Halon S stem Testin (Resettin ) Com uter Room and e a .oom W-ii.4.'ll; Chai i'n Piim

. C linder Block Re lacement for C r znp Pum PCN A-102.3; R. E. Ginna HP Orientation Pxo ram'CN 78-2677.

HP-11.3; Noble Gas Sam lin and Anal sis Utilizin a Narinelli Bea. er
PAGE 3 PORC

ITEM f/ PROCEDURE HP-7.8; Alarmin Do simeter Accurac Test PCNi 78-2707.

RSSP-13.9'SI H dro Test of Class "C" Pi in (Co nent Coolin Mater - Outs' onta~nt . BSSP-13.10; ISI H dio Test of Class "C" Pi in Component Coolin<; ltater - nsi e ontamment A-1701, Qualit Assurance Records, PCN 78-2658. 79-30 A-50.9, Facili Staff Trainin Pro ram Ginna Station Personnel Traxnxno Pro ram PCN 79-31 'MM 78-1890.2'eedwater Line Drain Valves After the Containment C e Va ves PCN 79-32 %M 78-1594; A-1 Installation of S ent Fuel Pit Suction Strainer 79-34 SC-1.7D; Emir enc Radiation Monitorin Off-Site Surve Team SC-1.7F" Emer enc Radi.ation Monitorin Off-Site Surve Team F GRE1W P&i. SC-1.7H,'ngr enc Padiation Monitorin Off-Site Surve Team 79-35 WC-l.i2D Mana ement Call List, PCN 78-2733. 79-36 'SC-l.l2C', S ecialized Call List'CN 78-2732.
PAGE 4 PROCEDURE WS-8.0; Detex Tours b Secure Guards PCN 79-01. %P-1.1; Issuin Personnel Dosimeteis'CN 78-2748. PC-ltd Solid Detemnination'CN 78-2746. RD-1.3; Tritium in Containment Air Sam lin and Anal sis ~i ~-48.2; Testin of Reactor Cavit Seal R'CN 78-2738. %D-2; Containment Pur e Release', PCN 78-2749. %P-9.2 Prima to Second Leaka e Detection and Measurements PCN %P-4.3; Work Permit Use, PWi 79-09. "-PT-13.1.10 Smoke Detector S stem Testin PCN 79-17. "<A-30.2; Plant Piocedure Classification Review, A roval and Distr'. utz.on e umements "8P-10.1 guali Control of Countin S stems PCN 78-2752. %-3.5.1 Deboratin Demineralizei {B) Rinse,'CN 79-55. ~-1002'uali Control Procedure Deviation,'evision 5 Chan e ii Tramps e cerements. %Z-10.l'uxili Buildin Crane interlock Checkout, PCN 79-79.
PAGE 5 PORC PROCEDURE 79-65 M-48.7 Cross-Ti.e of Bus 17 to Bus 18 PCN 79-57. M-51.1; Isolation of a Reactor Protection Rela M-58.1.'rea Monitorin Maintenance PCN 79-62. M-25.1; Re lacement of RTD's on C Safe Valve Su rt Stan-c ions PCN M-7.5 S ent Fuel Pit Filter Re lacement'CN 79-78. 79-66 PT-23, Containment Isolation Valve Leak Rate Testin PCN 79-19. PT-23.18B Containment Isolation Valve Leak Rate Testin "B" Contact ra ea er PT-23.18A Containment Isolation Valve Leak Rate Testin "A" Containment ra ea er 79-67 M 37.18B Isolation of the Gas Deca Tank Reuse Valves. M-43.7; S/G Hi h Pressure Wash for Decontamination. M-43.22 Condensat'e Stora e Tank Warmu . M-43.24'ns ction of S/G Second Side Tube Sheet. M-46.1 Pur in Gas From the "A" Accumulator. M-46.2 Pur in Gas From the "B" Accumulator.
PAGE 6 PORC Iikf // PROCEDURE M-52.1'nstallati.on of Detector arid Cable on Minia-ture Detector F ux Ma m S stem. M-45.1A; Ins ection of Safe rd Motor For 79-68 ~-1.6; Neutron E osure'CN 79-22. 79-69 M-l.l; Issuin Personnel Dosimeters' P& 79-23. 79-77 "=A-52.4; Control P of Limitin Conditions for 0 eratin E i ment '9-78 CM 78-1845.1; Guide Stud Stora e Racks,'Qt 79-,41. 79-79 %-3.6" Amcili Buildin Heat Tracin S stem 0 eration PCN 79-43. 79-80 4C-1; A List of Sam le Chemical Parameter and Sam lin Schedule PCN 79-82 4C-13.3 Phos hate Determination PCN 79-65. 79-83 %-4.5.11' B Letdown Deboratin D. I. Resin Re lacement PCN 79-84 4C-12.0; Dissolved 0 en Determination Indi o Carmine Method PCN 79-86 %D-2 Containment Puroe Releases'CN 79-69. 79-87 GS-3.0 Secuii Call List'Ciil 79-80.
PAGE 7 PORC iTEM // PROCEDURE PT-'24.1; S ent Fuel Pit Charcoal Filter B -Pass Flow PCN 79-88 M-43.9; Steam Generator Permanent Rin Nozzle Cover Gasket est M-'75.1'afe In'ection Suction*Pi in From Boric Acid Stora e T s U trasonic Ins ection o Me s PCN M-73.1'i in Re airs on Pr' stem Branch Pi in 'CN 79-60. (g-1701 Qualit Assurance Records'CN 79-35. 79-89 S-9A, S ent Fuel Pit Purification and/or Cooliri S stem'Wi S-4.5.7; Letdown Mixed Bed D. I. (A or B) Resin Re lacement PCS M-52.3 Incore Thimble Cleanin PCN 79-54. SC-3.15.15; Emer enc Ins ction PCN 7-Fire E i ment Locker Invento and S-3.36 CVCS Deboiat'emineralizei Bed 0 eration Usin "B" e ratm nest PT-2.7, Service Mater S stem PW 79-85. 79-90 S-4.5.11'B" LetdoÃm Deboratin DI Resin Re lacement'CN 79-77.
PAGE 8 PORC ITEM "// PROCEDURE S-3.2A'har and Volume Control S stem Pre-Startu Ali~nment7 S-3.5.1; Deboratin Demineralizer (B) Rinse PCN 79-64. SH 78-1594A.1 Instaiiation of SFP Suction Strainer'CN 79-83. S-'4.5.ii B Letdown Deborati D. I. Resin Re lacement'CN 79-91 PT-24; S ent Fuel Pit Filter Bank; Mass Aix Flow Check PCN 0-6.i2'lant 0 eration Dirin Coastdown P&i 79-18. 79-92 ASM 77-1499.1; Rod Insertion Limit Circuit PCN 78-79-93 ""SYf 78-1872.1 Mani ulator Ciane Gri rS stem Modi-zcatxon, 79-102 'CSI-5 Edd Current Testin of Series 44 Steam Generator es 79-104 %-13A, RHR S stem Lineu for Safet In'ection, PCN 79-105 ~-12.2 Medical Check; Fittin and Trainin of Per-sonne Us Res ~ators, 79-106 %P-12.1; Usa e of Res irators PCN 79-104.
1 C l ( C )
PAGE 9 PORC ITm // PROCEDURE 79-108 %-37.14, Ins ection arid Haintenance of "8" Loo Accum-ulator Dz.sc ar e C ec Va ve V- PVif -1

~%&150; Tem or Re air of Auxili Feedwater S stem Hanua Iso at>on a ve , PCN 79-109 'CP-617.0, Com nent Cooliri Water s Dischar e Pressure PIC- , PCN 79-110 "-$ -3.5.1; Deboratin Demineializer (B) Rinse, PCN 79-79-111 %-4.5.11; 8 Letdown Debroatin DI Resin Re lace-ment, P 79-112 <<P-1.2; External E sure Limits, PCN 79-88.

79-114 ~~S-28.0; Ins ection of Personnel and Vehicle and Packaoe PCN 79-115 >A-18; tfultileaf Trouble Re ort and Work Order PCN 79-36. 79-116 A-54.2'inna Station Staff Res nsibilities for Fire Protection N-43.1.1'team Generator Insert Removal Steam Generator, 79-127 A-102.2'. E. Ginna Administrative Controls Trainin Pro ram A-1102 Qualification of Test Personnel, PCN 79-7.
PAGE 10 PORC ITEM PROCEDURE A-1103; Test Ta Control Pro ram, PCN 79-28. A-603 Control of En ineeiin Documents b Central Recor s, A-604'ontrol of En ineer Documents on Modifi-cat>on Project P 79-128 ~-217 Instillation of a New RCS S le Deli Coil 79-129 PT-17.2 Process Radiation Monitor R-11 - R-21 and I ine onztor an 79-130 SM 76-21.4'atte Room Aii Conditionin - Air Condi-tzoner Dxsc e ct out n o atte Room P SM 76-'21.6; Batte Room Air Conditionin - Air Su 1 ct to t e Con itioner, SM 76-21.5; Batte Room Air Conditionin - Service ater z m nsta at>on SM 76-21.7; Batte Room Air Conditionin - Miscellane-ous, PCN SM 74-'28.1; lnstallition of Mike-U Lines to Condensite Stora e T s SM 75-48.30, Rework of the Auxili Feedwater Crossover Pz M z. z.cation
PAGE ll i~PORC PROCEDURE SM 77-1030.1; Neutralizin Tank Lo ic Madification, PQI'M 77-2110.1; Chem. Lab DI Stora e Tank Cable Routin ', PCN SM 77-ilats:i Diesel Fire Pum Heater, F&i. 79-135. A-36 Station Holdin Rules PCN 79-117. ST 78-1 Geneiator Shoit Circuit Test', PCN 79-87. 79-140 ~-4.3'od Permit Use PCN 79-141. 79-141 ""PT-17.2 Process Radiati.on Monitois', R-11 - R-12 and me Monitors R- ana - , N 79-142 %-43.14 Removino Steam Generatoi Blast Proof Loo Nozz e over, team enerator, e PCN 79-143 -P-2 Reactor Coolant S stem Precautions and Limita-talons, 79-144 N~ -7.4; Boric Acid Stora e Tank Filter Re lacement PCN 79-145 RC-3.15.3 Portable Extin~sher Ins ection,'CN 79-148. 79-146 %-43.2 Initial Radiolo ical Surve 'CN 79-146. 79-147 ~%-43.15.1 Installation of Steam Generator Cover osure Pr'anwa
PAGE 12 PORC IT&f'/ PROCEDURE 79-148 "%-43.16.1 Steam Generator Tube Sheet Photo-Ma in PCN -1 79-149 ~4-43.2l; Steam Generatoi Final Clean-u and Ins ection'9-150 H-36.1'A Waste Gas Co ressor Maintenance PCN M-36.2 1B Waste Gas Com iessoi Mairitenance'CN GS-21.0; Site Access Control (Securit ) and Personnel I entz z.cation S-3.1J Boric Acid Stora e Tank Filter Isolation, PCN 79-151 ~-8; Li. id Rad Waste Co ositin and Anal sis, PCN 79-152 HP-2.4 TLD Readout PCN 79-155. HP-3.2; In-Plant Re ortin of Current E osures'PCN HP-8.2 Leak Testin of Licensed Sources'CN 79-157. HP-8.3 Calibration of Gamma Seal Souices PCN 79-158. HP-10.2' erational Test of Portal and Hand and Foot on>.tors
PAGE 13 PORC ITEM "tI PROCEDURE HP-10.5 Efficien Calibration of Gamma S ectrometers PCN - l. RD-1.2'ontainment Radio as Sam lin and Anal sis ~i, RD-7 Li 'd Waste Releise, PCN 79-164. PC-4 H dro en Concentration and Radio as Activit in* Pr Coolant-S m an Ana sos PCN RD-9; Pie irin Waste for Shi ment or Stora e'CN 79-ES-2.3; Iodine - 131 Anil sis of Milk PCN 79-152. WC-2.0; Metrobm E-415 Titrator Calibration', PCN 79-153. 79-153 PT-5.10 Process Instrumentation Reactor Protection e x. Test e PZ-5.20 Process Instrumentation Reactor Protection C anne Trx Test C e , CN PZ-5.30'rocess Instrumentation Reactor Protection C e Trz Test C e 79-154 A-50.1 R. E. Ginna Administrative Control Trainin ro am A-50.9; Gixina Station Personnel Trainin Pro ram PCiil
PAGE 14 PORC iTEM // PROCEDURE 79-156 S-4.4; S ent Resin Removal to Shi in Casks, PCN 79-172. S-7A RWST Purification PCN 79-171. 79-157 A-601; Plant Procedure Document Control; PCN 79-48. CP-1012'alibration and/oi Maintenance of "A" >haste Con ensate eve CP-1013 Calibration and/or Maintenance of "B" Paste Con ensate Leve CN 79-159 'CM 78-l594A.2; Standb S ent Fuel Pit Pum Cable Rout-x.n, 79-i6O CM 78-'1594A.3'nstaiiation of S ent Fuel Pi.t Cooiin Bac. u stem 79-166 'MM 75-14.1'atch Tank Recirculation Heat Trace Installation 79-165 %P-7.6 Ta in of Instruments Re uirizi Calibration or a~tenance a-i6:li; Monitoiino and Enrichment of Accumulator Boron Concentration 79-166 ,~-7.6 Ta in of Instruments Re uirin Calibration or amtenance W-i6.ii Monitorin and Enrichment of Accumulator Boron Concentration
PAGE 15 PORC iTEM // PROCEDURE

~-21; Cleanin Boric Acid Tank Level Sensin Lines PCN 79-167 ~-7.3; Caiibiation of Al ha Surve InstrUments PAC-4S'9-168 4P-1.3 External E sure Records, PCN 79-188.

79-169 ~i -36:i" iA Waste Gas Co ressor Mairitenance, PCS 79-

~~ -36:Z 'B Waste Gas Co ressor Maintenance PWi 79-79-170 ~-7.1 Calibration of Canna Surve Instruments-Low Ran e, PCN 79-171 '4-3.1N Isolation of Miscellaneous Valves in Boric cz. toraoe oom 79-172 %M 77-1682.5; Penetration Testin Modification-Penetration 79-173 %-3.1B Pre-0 erational Line U of Boric Acid S stem,'-3.1G Acr Stora e Isolatin 'lus or 'nd ajor Drainin~ the "A" Boric a ve or x m am-tenance an Ins ection, PCN %-3.1H Isolatin 'lushin and Drainin the "B" Boric Aci Stora e Tank or Major Valve Tank or Pi m Main-tenance an ns ection,

i t,
PAGE 16 C-,3. 1K 1A Boric Acid Tiansfer Pum Isolation/Restora-tron PCN %-3.1L 1B Bori~ Acid Transfer Pum Isolation/Restora-tron, PCN 4-3.1M Isolation of Batchin S stem, PCN 79-200. A-1011 Performance of Test PCN 79-06. A-1401 Station Holdin Rules PCN 79-116. M-53.3 14'iameter E ment Air Lock Removal and Re lacement'CN CP-'1039'alibration and/or Maintenance of /l4 Gas Deca Tank Pressure C e CP-1038 Calibration and/or Maintenance of /I3 Gas Deca Tank Pressure C e I. CP-1037; Calibration and/"or Maintenance of ii2 Gas Deca Tank Pressure e CP-1036 Calibration and/or Maintenance of //1 Gas Deca Tank Pressure e CP-12.0; Rod Insertion Limit and Delta T Reactor Control Rack'al RSSP-13.8.2; H dro Test of Loo "A" Under round Service Water x xn creen ouse to ur ine ui
PAGE 17 PROCEDURE HP-11.7; Dra er Multi Gas Detector Use'CN 79-205. HP-12.7 Constant Flow Breathin Air S stem Setu PCN 79-206. CP-11.8; Condensed H drocarbon Content of Bieathin Air PCN "SH-2714'.1; A Steam Generator J-Tube Modification', PCN 78-2693. WM-2714.2; B Steam Generator J-Tube Modification PCN 78-2692. CP-12.1 'elta T Si al; Summer Unit TM-405D'CN 79-232. CP-12.2; Delta T Re eater Unit TM-405E,'CN 79-233. CP-12.3'elta T Re eater Unit Tion l7 'ut art en t Rod R s 79-215 %M 78-2133.1'alves 866A and 866B t"fodification for Testin 79-216 %M 79-'1832A.l Circuit Se aration Fuse Installation'CN 79-333.

+A-50l; Plant Procedures Pre aration and Classification'A-502; Plant Procedure Content and Format Re irements "A-602'lant Procedure Distribution PCN 79-49. +A-1302; Control of Material Handlin and Handlin E ment, PCN

PAGE 21 PORC IT'EM II PROCEDURE

-A-1602 Preventive Action Re ort PCN 79-90..

WP-2039; Check and/or Maintenance of S "A" Level Control an A arm Swztc es

%P-11.9; MSA 0 en Indicator Use', PCN 79-222.'P-208.0'alibration of Area Monitor Drawer R- 'PCN 79-231. %P-11.10 Air Sam lin With Siersat Low Volume Air S ler PCN 79-225 ~-802 Identification and Mark'f Material PCN 79-301. "-PZ-13.4.13 Alarm Valve S stem Test' Fire S stem 813; Sewn.ce Bum m S r . er, PCN ""HP-2.2 Riole Bod Counter 0 eration'CN 79-273.

79--226 %P-5.2'ostin of Radiation Areas and Container Labelin ,

~-'3.2 In-Plant Re itin of Current E osures'CN 79-268.

Ni -7.4'oric Acid Stora e Tank Filter Re lacement PCN 79-79-232 %-11.4, Ins ection and Maintenance of In ersol Rand Pum s s an 79-233 gC-'304'ontrol of Modification Activities b the Ginna x >cation rogect
PAGE 22 PROCEDURE M-12.2; Medical Check Fittin and Trainin of Personnel Usmo Res irators, PCN ""'PT-30, Containment S ra Nozzles Check"of itAt'nd-i'BiiKin s PCN %-4.4.1; S ent Resin Packa e-Site Recei t and Shi ment 4-7B, Reactor Coolant Low Pressure Purification PCN 79-263. 4-7C'ransferrin and Purification of RWST Water From RWST to SFP PCN Wi -45.18; Residual Heat Removal Pum Motoi tfaintenance at Co S ut own, PCN %-12.4 RCS Leaka e Surveillance, Recoid Instructions PCN %-4.4,' ent Resin Removal to Shi in Casks'CN 79-227. WS-41.0' lo ee Screenin Pro ram'CN 79-224. 4S-'39.0; Protected Vital/Area Access PCN 79-223. +A-l. 1; Locked Radiation Area, PCN 79-219. ~-13.7 Fire Hose Reel Assembl Tns ection, PCN 79-284. %M 78-1845.1 Guide Stud Stora e Racks PCN 79-276.
PAGE 23 PORC ITEM PROCEDURE 79-268 PT-12.1; Emer enc Diesel Generator lA PCN 79-278. PT-12.2 Emer enc Diesel Generator 1B'~ 79-285. 79-250 'CM 79-2428; RCP Lube Oil Level Indication. 79-260 %M 77-1431.1; AFltE Flow Control Valve - Mechancia*l Installation PCN 79-266 'CP-12 Rod Insertion Limit and Delta T Reactor Control Ra CN 79-265 CP-12.24'. I. L. BISTABLE TC-405 J/O'CN 79-373 ~ 79-266 <P-209.4; Nuclear Measurements Co oration Air Monitor'CN 79-267 CP-213.4; Check of R-13 and R-14 Flow Control S stem PCN 79-268 ~-221.2'alibration of R-21 Detector; PCN 79-359. 79-'269 ~-468.0 Calibiation And/Or Maintenance of Steam Genera-tor Pressure Channel , PCN

- 1 .

79-270 CP-468.3; Steam Generator Pressure Transmitter PT-468 PCN CP-469.3, Steam Generator Pressure Transmitter PT-469
PAGE 24 PORC PROCEDURE CP-478.3; Steam Generator Piessure Tiansmittei PT-478'P-479.3; Steam Geneiator Piessure Tiansmitter PT-479'P-482.3, Stean Geneiator Piessure Tiansmitter PT-482; CP-483.3; Steam Generator Pressure Transmittei PT-483 79-271 "HP-3.1; E sure Re orts to Individuals and the Nuclear Re ato oman.ssion 79-272 4P-4.2; Self Read& Dosimetei Use, PCiil 79-293. 79-273 NSI-1.1.9 Qualit Grou "A" Inservice Ins ection'9-274

%-11.4.5 Char in Pum Vaiidrive Low S eed and Ili h e ec naca Sto Sett A justment 79-275 M-38.6; 1A Batte Char er Maintenance or Re air, PCN M-38.7 1B Batte Char er Maintenance oi Re air PCN 79-276 't1-37.20'ns ection and Re air of Main Steam Isolation a ves,

4

/

J.$
PAGE 25 PORC iTEM II PROCEDURE 79-277 W4-67.4, Alarm Valve S stem Maintenance, S stem Numbeis 1, Ware ouse, PCN 79-278 %D-10, Shi in Radioactive Material PCN s 79-307 and PCN t 79-283 S-9E Drainin S ent Fuel Pit Transfer Canal to Refuelin ater Stora e S-9F Transferrin S ent Fuel Pit Transfer Canal to the CVCS Ho u T Waste o u T or Mone.tor T s P 79-286 ~-12.13 R.X.L. Recorder TR-40S PCS 79-37i.

-XST.-5 Ed Current Testin of Seiies 44 Steam Generator es PCN Wi-ii.4.4; Char in Pum Vari-Diive Overhaul Unit /I PCN 83-15.1 "A" or '"B" Diesel Generator Removal From Service +i-37.1A; Re ackin of Pressurizer S ra Valves 431K and %-37.57; Containment DI Check Valve 8419 Naintenance'-2.5 Plant Shutdown From Hot Shutdown to Cold Shutdown When Con enser Steam Dum zs Unavax e PCN s - an

PAGE 26 PROCE1XRK W-7; Ali ent and 0 eration of the Reactor Vessel Ovei-ressure Protection S stem, PCN APE-2, Protective Rela Calibration and Tri Test 1A Emer-en Dxese PCN '%PI'-23.15; Containment Isolation Valve Leak Rate Testin Containment A~x S e Out, CT-29.3; Auxil Buildin Ventilation Main HEPA Filter B Testm, ~-53; C cle VIII - IX RefueliYi PCN s 79-'343 an m-'ii.8'ressurizei Bistable PC-431B PCN 79-390. WP-l1.0 Calibration and)or Maintenance of P.L.P. RiCk M u es Not Covere Ot er Ca z rat>on Proce es PCN s - an CP-12.7 Deviation Bistable TC-408F, PCH 79-366. CP-12.6 Deviation Bistable TC-407F PCN . 79-367. CP-12.5, Deviation Bistable TC-406F PCN 79-368. CP-12.4 Deviation Bistable TC-405F'CN 79-369. CA 77-1682.10 H drostatic Test'f Penetration Px xn M z zcatzon PCN
PAGE 27 PORC iTEN ll PROC EIXEK 79-289 A-102.9 'aintenance Tiain Pro iam'CN'9-174. A-102.11 Emer enc Plan Trainin Pro ram PCN 79-221. A-102.12; Firewatch Trainin PCN 79-220. A-1104 Ginna Station Technical S ecification Sur-ver. ance ro ram, A-i6pi; Coirective Action Re rt'CN 79-89. GS-43.0 Off Loadin Portal Piocedure PCN 79-208. PT-17.4; Li id Waste Flow Indicatoi and Rotameter Check RF-54'affle Re air PCN 79-304. 79-290 'CM 79-1832A.2 Circuit Se aration Installation, PCN 79-351. 79-302 CP-401.7 Ta Re eater, TM-401C PCN 79-418. 79-306 +A-102.2 R. E. Ginna Administrative Controls Trainin Pro am PCN - 9 . 79-307 +A-1701 Ouali Assuiance Records 'CN 79-395. 79-308 MM 77-1891.1 Electric Heat Tiacin for Valve 825 A 4 B P 79-309 PT-2.8'o nent Coolin Water Pum S stem PCN 79:448.
PAGE 28 PORC ITEM PROC EDURl". RF-ZD, Fillin the Refuels Canal PCN 79-247. RF-8.0'uel Assembl and Core Com onent Movement Prere i-sites an Precautions PCN RF-8.2; Fuel Handlin Instruction Pre-Loadin & Periodic Valve Test RF-8.3 Core Loadin Periodic E ui ment Stitus Check SM 1594A.4 Qualification arid Leak Testiri of Standb SFP Coo xn Com onents SM 78-i872.'i; Mini ulator Crane Gri er S stem Modifica-txon SM 79-2417.1 A Steam Generator J-Tube Modificati.on PCN. SM 79-2417.1'A'tean Generator J-Tube Modification

'PCN SM 79-2417.2; 'B Steam Generator J-Tube Modificition'M 79-2417.2 B Steam Generator J-Tube Modification 79-310 "A-48'est Ta Control Pro rim PCN 79-246.

79-311 CP-31.3 Calibration of Source Ran e N-31 PCN s
4 PAGE 29 PORC ITEM // PROCEDURE CP-32.3 Calibration of Source Ran e N-32 PCN's CP-35.4; Intermediate Ran e N-35 Bistable Rela Drivers Calibra-tron, PCN 'I CP-36.4; Intermediate Ran e N-36 Bistable Rela Drivers Calibra-tron ISI 5 j Ed Current Testin of Seiies 44 Steam Genera-tor es M-43.15.1 Isolation of Steam Generator Manwa C osure ~i Pi'over PT-23.19; Containment Isolation Valve Leak Rate Testin Sa e n ection stem PT-23.22 Containment Isolation Valve Leak Rate Testin Ro ~ ~ ~ 1s e, PT-23.23'ontainment Isolation Valve Leak Rate Testin S A Dzsc r e RF-2E Drainin of Refuelin Canal; PCN 79-442. RF-'9.1 Ste b Ste Fuel Loadin and Ma s PCN 79-434. RF-53; C cle VIII - IX Refuelin PCN s 79-431 79-432 S-9S; Standb (Skid-Mounted) SFP Heat Exc er 0 eration,
PAGE 30 PORC iTEM d PROCEDURE S -9T; Stanch (Skid- Mounted) SFP Heat Exchan er Removal PCN S-27.209 Isolation of CVCS Relief Valve 209 PCN 79-440. 79-312 A-102.4, Indoctrination and Tiainin of Quali Control Personne, PCN A-102.5 Trainin of Modification Project Personnel; PCN A-102.6'. E. Ginna S stems Fimiliarization Pro ram, PCiil A-102.7 R. E. Ginna Auri.l' erator Qualification Pro-am, PCN A-102.10 Health Ph sics Technician Trainin 4 Res nsibil-it L~ts PCN A-'102. 13 R. E. Ginna NRC Licensin Trainin Pro ram PCN A-102.14; R. E. Ginna 0 erator Re lification Pro ram'9-'312A CP-'221.0; Calibration and/or Maintenance of RS Channel R- PCN CP-22i:i'alibration or Ratemeter Drawer R-21, PCN 79-358. CP-221.3; Re lacement of Detector for RMS Channel R-21
PAGE 31 i~PORC II PROCEDURE e-ill.i7 1C Safet Injection Alternate Suction Re ie ave so at>on or amtenance PCN 79-317 +A-102.14; R. E. Ginna 0 eiatoi Re lification Pro ram 79-318 N~ -43.33 Examination and/or Removal of Objects from the Steam enerator o ns ection o es Steam enerator 79-320 MP-12; Rod Insertion Limit and Delta T Reactoi Control Ra PCN 79-321 'C-3.3E 8 in VCT foi Gas Removal PCN 79-447. 79-322 ~-2.4; Coldlefuelin bfotor 0 crated Valve Suiveillance PCN s - an 79-323 %SSP-l.l; Interlock Verification Residual Heat Removal S stem PCN 79-324 ~-2D Fillin the Refuelin Canal'CN 79-481. 79-325 "-S-7C'ransferrin and Purification of RUST >later From RUST to SFP PCN 7-79-32ll ~IP;3; Receivin Ins ection of New Fuel PCN 79-489. 79-327 'CS-43.0 Off-Loadin Portal Procedure PCN 79-487. 79-328 4S-40.Q Loss of Perimeter L tin PM 79-488.
PAGE 32 PROCEDURE 4-3.2D Tzansferrin Water From CVCS HUT s to RWST or SFP WP-449.0; Pressurizer Pressure Channel '449', PCN 79- +A-17 Plant 0 rations Review Comittee 0 eratin Pro-ce ure, PCN %P-7.1 Calibration of Gamma Surve Instruments - Low Ran e HP-4.3; Work Permit Use, PCN 79-441. HP-2.2; Whole Bod Count 0 eration PCN 79-497. CP-408.5 Delta T Re air TM-408P PCN 79-499. PR-2 Protective Rela Calibration and Tri Test 1A Emer enc Diese, PCN PR-'3'rotective Rela Calibration and Tri Test lB Emer enc mesc PCN AR L-24, Holdu Tank 1B Hi h Level; PCN 79-471. AR L-32 Holdu Tank 1C Hi Level'CN 79-472. AR L-16, Holdu Tank lA Hi Level PCiiI 79-473. HP-9.1 Steam Generator Blowdown Activi PCN
A PAGE 33 PORC II PROCEDURE PC-7; Iodine 131 E valent Calculation PCN 79-79-337 RSSP-l. 1 'nterlock Verification Residual Heat Re-mova S stem PCN SM 78-1464.1; Re lacement of Volume Control Tank Level Transno.tters, SM 78-i464.2; Re lacement of Accumulator Level Trans-ao.tters an 4. SM 77-1623.1; Char in Monorails, PCN 79-470. l SM 78-1890.2'eedwater Line Drain Valves After the Containment C e Va ves PCN SM 78-2133.1; Valves S66A and 866B Modification for estrin, ~i SM 79-2417.2 'B'team Generator J-Tube Modification PCN 79-'338 S-13B; RHR Isolation PCN 79-484. 79-340 A-1105 Calibration Surveillance Pro ram for Instrumen-tation E ment o Sa e Re ated Co nents, Pelt A-901 Control of Veldin PCN 79-50. A-'902 Heat Treatin Control PCN 79-51.
PAGE 34 K)RC ITEM // PROCEDURE A-904 Weldin E ui ment Performance Verifications PCN A-503; Plant Procedure Adherence Re irements PCN 79-329. A-605; Control of NRC Corres ondence PCN 79-458. A-1703; S stem and E i ment Histories PCN 79-469. PZ-2.4.1 ColdjRefuelin Motor 0 crated Valve Surveil-ance, ~i. A-1003 Control of Inservice Ins ection Activities A-1002 Qualification of Surveillance and Ins ection Personne PT-2.9.3; Check Valve Exercisin Quarterl Re irement, M-37.58 Re air of Alo co Motor 0 crated Gate Valve foi a ve er S-27.823 Isolation of RMW to Co nent Coolin Valve 79-353 %M 77-1431.2; H drostatic Testin of Auxili Feedwater M x z.cation 79-356 +A-1601 Corrective Action Re rt PCN 79-89. 79-357 +A-19 Chan es in Written Procedures'CN 79-535.
la,. PAGE 35 PORC ITEM 7/ PROCEDURE 79-358 +A-30.3 Plant Procedure Content and Format Re rements. 79-360 ~-32.0 Reactor Tri Lo ic Test 'A'r "B'rains'CN 79-552.

~-'303 Contiol of S stem Modification Activities PCN- -"RF-42; Television Visual Fuel Assembl Ins ection PCN- %F-53 C cle VIII - IX Refuelin , PCN 79-551.

CF-8.3 Core Loadin Periodic E 'ent Status Check'

~SP-i3.i'Si H dro Test of Class "C" Pi in (Cpm nent Coo xn Water Inset e Contaxrment %SSP-13.9 ISI H dro Test of Class "C" Pi in (Co onent Coo xn ater - tsar. e ontaument %-13B'HR Pum Isolation ~i 79-605.

79-361 +AR-K-29, S ent Fuel Pit Hi T 'CN 79-517. 79-362 +A-601 Plant Procedure Document Control, PCN 79-614. 19 364- CP-112.0 T Leve Calibration and/or Maintenance of Volume Control C e
PAGE 36 i'PORC PROCEDURE CP-139.0 Calibration and/or tfaintenance of Volume Contiol T Leve C e PCN 79-365 ~P-'412.0 Reactor Coolant Flow Channel "412 PCN 79 537 79-366 'CS-18.0; Trainin arid Qiali in of Guards 'CN 79-549. 79-367 CS-35.0; Issuin and Destruction of Ginna Photo-Identi-z.catv.on Car s PCN 79-368 CS-39.0; Protected /Vital Area Access PCN 79-515. 79-369 "HP-5.1 Area Radiation Surve s PCN s 79-508 and 79-550. 79-37O Ni -43.15.1; Installation of Stean Generator Pi Nanwa 79-371 Cf-43.26; Installation of Steam Generator Second Hanwa Cover S 79-372 %-43.24.1; Ins ection of Steam Generator Seconda Side er nterna s 79-373 0-1.2'lant From Hot Shutdown to Stead Load PCN 79-532. 0-2.2 Plant Shutdown From Hot Shutdown to Cold Condi-tz.on 79-374 M-12.1; Emer en Diesel Generator lA PCN 79-563. 79-376 %SSP-1.5; Valve Interlock Verification - Feedwater Isola-tron PCN
PAGE 37 PORC iTEM PROCEDURE 79-378 M-41A Ali nment of Auxili Feedwater S stem Prior to Power 0 eratxon PCN 79-379 -41D Moto D ive n Auxili Feedwater Pum PCN Isolation'9-380 A-102.8 Ginna Station En ineers (Cadet, Assistant Station an tata.on raxm.n ro ram A-1201 Calibration and Control of Test E ui ment PCN 79-19-388 %11 77-1431.4 Installation of Electrical ater E i ment for

-631.

Ama. Fee F ow Contro 8 ass a ves PCN 79-390 CM 218 Grout Pier for NC.-BH14; Pi e Su ort, PCN 79-659. 79-392 +A-1001'ns ection and Surveillance Activities PCN 79-393 MSi-7; Visual Leaka e Ins ection of Hi h Ener Pi PCN 79-394 MSi-l.1.9 Quali Grou A Inservice Ins ection PCN 79-395 ""XSi-4.1.6; Hi Ene Inservice Ins ection PCN 79-625. 79-396 %M 78-1838.1; Containment Wall-Mounted Jib Crane PCiiJ 79-397 %-3.2; Reactor Cavi Clean-U and Decontamination PCN
PAGE 38 PORC iTEM fI PROCEDURE l 79-399 +A-102.2 R. E. Ginna Administrative Controls Traini Pro ram, PCN -5 19-4$ +A-102. 12 Fire Watch Trainin PCN 79-657. 79-401 -A-1701; Quali Assurance Records, PCN's 79-467 and 79-79-402 CP-934.0, Calibration and/or Maintenance Procedure of Accumula-tor Leve e CP-935.0; Calibration and7or Maintenance of Accumulatoi Level CP-938.0 Calibration and/or Maintenance of Accumulatoi Leve C e CN CP-939.0'alibration andjor Maintenance of Accumulatoi Leve e l. 79-409 4-33'uadrant Power Tilt PCN 79-598. 79-404 NSI-1.1.9; Quali Grou A Inservice Ins ection PCN 79-624. 79-405 WSI-4.1.6 Hi h Ener Inservice Ins ection PCN 79-625. 79-407 Wf-72.1 Re lacement Pr Loo RTD - PCN 79-619. 79-408 PT-34.0 Startu P sics Test Pro ram PCN 79-634. PZ-'34.1 Initial Criticali; and ARO Boron Concen-trate.on, PCN
PAGE 39 PORC iTEM PROCEDURE PT-34.3; RCC Barik Worth Measurement PCN 79-633. 79-409 QClP-1; Steam Generator Piima Side) Preclosure Ins tron, PCN QCIP-2; Pre-Closure Core Verification'Ql 79-571. QCIP-5; Cleanliness Ins ection of Co nents PCN 79-573. QCIP-9 Pressurizer Pre-Closuxe Cleanliness Ins ection PCN QCIP-15'isual Ins ection Duxin H drostatic and Steam Pressure Teston QCIP-21 Shi 'acka e LL-50-100 Ins ection PCN 79-qCiP-22'hi in Packa e HN-100 Seiies 1 Ins ection 79-4io ~-2E, Drainin of Refuelin Canal PVil 79-568. 79-412 "-S-3.2A; Char in and Volume Control S stem Pre-Staitu A x nment PCN 79-4u 4-4. 1U Veloci Flush of R-18 PCN 79-623. 79-4'-7CRWST Transferrin to SFP N and Purification of RWST Water From 79-420 A-203; Ginna Modification Pro'ect 0 anization PCN
PAGE 40 I~ PORC A-401; Control of Procurement Documents Pre ared at Ginna, PCN A-'402 Contiol of Procurement Documents Pre ared b the G~a Station M x z.cation rogect PCN A-403; Re isitionin Seivices from General Miintenince M-702; Su lier Qualification Technical Evaluations PCN A-1203; Calibration and Control of Mechanical Measur-Too s an or e rene es A-. 1702 Records Stora e Facilities and E i ment PCN A-1801 Ginna Station Res onse to Internal Audits PCN CP-80.4; Calibration Procedure for Cite o //1 Mechani-ca i easurm oo s, CP-81.0 Calibiition TQZP 650 Dual Bench Tester foi Tor e Wrenc es CP-81.1 Calibration Procedure for Tor e Wrenches PCN CP-934.4'alibiition and/or Maintenance of Accumulator Leve ower u
PAGE,41 PROCEDURE CP-935.4 Calibration and/or Maintenance of Accumulator Leve Power Su LQ- PCN CP-938.4 Calibration and/or Maintenance of Accumulator Leve Power Su 1 , LQ- , PCN CP-'939.4; Calibration and/or Maintenance of Accumulator Leve Power Su LQ- PCN ISI-7; Visual Leak e Ins ection of Hi h Ener Piin

'-7L Mixed-'Bed DI Saturation with Boron PCN 79-664.

~-219 Re air of Safe In'ection Pi e Su ort PCN -EM-220 Re air of Pressurizer Sur e Line Pi e Restraint MC-SP- PCN ~-221 Re air of RHR Pi e Su it MC-RH-9 PCN 79-695. <SI-5 Edd Current Testin of Series 44 Steam Geneia-tox' es s - an ~-'224 Pe air of RCS Diain Line Pi e Han er MK.-D1 PCN 79-718. ~-225 Re air of Auxili S ra Line Pi e Restraint ASL- ~-223'e air of Letdown Line Pi. e Su ort Near AOV-227'CN 79-
~ ~ PAGE 42 PORC i'd% "/I PROCEDURE 79-434 -EM-222'e air.of Safet Injection Pi e Su rt tK-SI-5 79-440 ~-224; Re air of RCS Drain Line Pi e Han er MK-Dl, PCN 79-737. 79-441 ~-226; Giout Placement on Pi e Su ort ACH-41A PCN 79-732. 79-442 ~-227'e air of RHR Pi Restraints Between RHR Heat Exchan er an Va ves PCN 79-543 %M-228; Re air of Cli s on Safe Injection Pi e Su rt 79-%at'-52.2 Control of Locked Valve 0 erati.on ~i 79-696. 79-457 +A-102.8 Ginna Station En ineers (Cadet Assistant Sta-tion, an tatxon Tram~ Pro ram CN 19-448 %P-6.1; Contamination Surve s PCN 79-713. 4-2.3.2; Fillin and Ventin the Reactor Coolant S stem 79-450 CC-1.1'r'oolant Anal sis Schedule and Limi.ts PCN 79-727. 79-451 %D-8 Li id Radwaste Co ositin and Anal sis PCN 79-452 %-3.2A Char in and Volume Control S stem Pre-tartu z nment
PAGE 43 PORC

// PROCEDURE 79-453 "-S-8A Co nent Coolin Y4ater S stem Startu and Norma 0 ration Va ve A i nment, PCN 79-454 a-i7'i Containment S ra S stem, PCN 79-694.

79-455 +1-11.4.5 Char in Pum Varidrive Low S eed and Hi h S ee Mec ica Sto Settin~ A gustment an Actuator Maintenance PCN

""~if-48.2 Isolation of Bus 14 PCN 79-686.

Ni-50.1; Isolation of 12A Tiansformer, PCN 79-714.

%-2.3.2; Fillin and Ventin the Reactor Coolant S stem'C %-7 Ali ament and 0 eration of the Reactor Vessel Over-Pressure Protection S stem, N M-8A Com nent Coolin Mater S stem Startu and Noroal 0 erat>on a ve A r ament, < s - an - 2.

79-457 A-701, Recei t and Acce tance of ~ifaterials/Parts', A-705; Control of Purchased Services PCN 79-601. A-1202, Calibration of Process S stem Instrumenta-tion PCiit SC-15.8, Fire S stem Locked Valve C clin 'CN 79-
PAGE 44 PORC PROCEDURE 79-464 -229; Re air of RHR Pi e Su ort tK-RH-PCN 7-79-469 A-54.3' en Flame'eldin and Gxindin. Permit'CN 79-410 W-73. 10 Weldin, PCN 79-728. 79-471 -A-1104, Ginna Station Technical S ecification Surveillance Pro ram, PCN 79-472 'CS-35.0 Issuin and Destruction of Ginna Photo-ldentifi.ca-tron Car s, PCN 79-473 m-l.i issue Personnel Dosimeter PCN 79-739. 79-474 NSI-5 *Edd Current Testin of Series 44 Steam Generator T es PCN 79-475 %-40, Surveillance and Maintenance of H draulic Snubbers, 79-476 &-43.0, Steam Generator Maintenance Test and Re air Proce-es5

&-43.1 Steam Generator Manwa Cover Removal Steam Genera-79-478 %team Generator Insert Removal- Steam Generator'9-479 "H-43.5'solation of Steam Generator Blast Proof Loo Nozz e Covers

PAGE 45 PORC iTEM" /I'ROC1MRE 79-480 '7'%-43. 14, Removin Steam Generator Blast Proof Loo Nozzle Cover Steam Generator Le , PCN 79-481 "M-43.15; Installation of Steam Generator Manwa Insert PQl 79-482 %-43.21,'team Generator Final Clean-U and Ins ction 79-483 %-2.5 Plant Shutdown From Hot Shutdown to Cold Shutdown en Con enser Steam xs navar a e PCN 79-484 4-6 0 eration and Piocess Monitorin , PWi. 79-760. 79 489- -"dT-2.1; Safet Injection S stem s PCN 79-781. 79-486 "-PT-2.2'esidual Heat Removal S stem'CN 79-769. 79-487 4T-2.3 Safe d Valve 0 eration, PQi 79-783. 79-488 PT-13.7'ire Hose Reel Assembl Inspection'CN 79-PT-13.4.7 Protomatic Delu e Valve stem Testin S stem i tora e oom S PT-13.4.8 Protomatic Delu e Valve S stem Testin , S stem Mam Trans ormer PCN PT-13.4.9; Protomatxc Delu e Valve S stem Testin stem rans ormer
PAGE 46 PROCEDURE PT-13.4.10A; Protomatic Delu e Valve S stem Testin S stem A, -A Trans ormer PCN PT-13.4.108, Protomatic Delu e Valve S stem Testin S stem B -B Trans ormer PCN %-3.6, Auxili Buildin Heat Tracin S stem 0 era-tron PCN KC-1.12B'tation Call List PVil 79-784. -A-52.2; Control of Locked Valve 0 eration PCN 79-751 "~-i:i; Safet Injection S stem Actuition PCN 79-752. X-l.l Plant Heatu from Cold Shutdown to Hot Shutdown PCN s an 4-1.1B'stablishin Containment Inte rit PCN 79-753. "Q-l.2; Plant From Hot Shutdown to Stead Load; PCN 79- ~-7 H dro Test of Reactoi Coolant S stem'CN 79-A-801, Control of Acce ted Material; Parts and Com-onents at azna tatxon, A-802 Identification and Marking of Acce ted 1fater-z.a arts an o nents

'AGE 47 PROCEDURE A-1501 Control of Nonconfo 'tems'C%i 79-700. ~-ii O 0 eratin Procedure for IL-351 AA/AE S ectro-otometer P 4-1.2; Plant Fiom Hot Shutdown to Stead Load'CN 79-807.

%-1.2 Plant From Hot Shutdosm to Stead Load PCN 79-836. ="A-102.2'. E. Ginna Administrative Contiols Trainin Pro-ram, PCN >A-ip2.'ii Emer enc Plan Trainin Pro~ram, PQl 79-833. "A-601'lant Procedure Document Control PCNi 79-817. A-602; Plant Procedure Distiibution PWi 79-805. E-1.2; Loss of Coolant Accident, ~i 79-825. E-1.3, Steam Line Break Accident, PCN 79-826. E-l.4; Steam Geneiator Tube Ru ture Accident PCN 79-827. MSI-2.1.7 Quali Grou B Inservice Ins ection, PQf 79-K-l.2'lant From Hot Shutdown to Stead Load; PCN 79-834. 0-1.2.2, Critical Rod Position Calculation Peril 79-831.
PAGE 48 PORC iTEM "// PROCEDURE 0-3.1; Boron Concentration for the Xenon Free All Rods In-Most Reactive R Stu Out S t own Mar m, ~i 0-6.6; Coriectin Measured Boion Concentration to Reference Fu ower E cte Boron Concentration PCN 79-519 KC-l, Radiation Emeroenc Plan PCN 79-779 ~ 79-520 ~-2.10.1; RCS and SI Headei Check Valves (Lao A 4 B Co Le s P 79-521 RSSP-1.2 Valve Interlock Verification - Safe In'ec-tz.on stem, RSSP-2.1; Safe Injection Functional Test PWi 79-802. RSSP-2.1A, Safet In'ection Functional Test Ali nment PCN 79-522 SC-1.3B Site P.adiation Emei enc (Emer enc Coordinator an urve enter Ass> nees PQ-SC-1.3C; Site Radiation Emer enc @on-0 eratin Personnel)' an 79-523 TICP-4, Test Instrument Calibration Procedure, Cate-0 x. x.ta tz. et>on deter TICP-6 Test Instiument Calibration Piocedure, Cate-. o I , Mz. zvo t otentzometer PCN 79-524 0-2.1; Normal Shutdown to Hot Shutdown PCN 79-835.
PAGE 49 PORC ITmi i/ PROCEDURE 0-1.3; Reactor Startu for Trainin PCN 79-820. PT-6.1; Source Ran e Nuclear Instrumentation S stem, PCN PZ-16; Auxili Feedwater S stem'CN 79-819. S-27.955/966C'OV-955 and AOV-966C; RCS Loo S le Va ves Iso ation PCN T-18C, Turbine Overs eed Tri Test, PQ1 79-839. 79-525 A-52.2; Control of Locked Valve 0 eration'CN 79-837. S-16A, Safe Injection S stem Ali ament'CS 79-838. T-43A,'li nt of Auxili Feedwater S stem Prioi to Power eratxon 79-527 A-903; Non-Destructive Examination Control, PCN 79-52. HP-2.5; Whole Bod Count Evaluation'CN 79-804. 79-538 "-S-30.1'afe In'ection S stem Valve Position Verification" 79-539 -S-30.2 RHR S stem Valve Position Verification PCN 79-856. 79-%0 %-30.3 Containment S ra S stem Valve Position Verification PCN 79- 57.
PAGE 50 PORC XTEM // PROCEDURE 79-541 M<-230; Pi. e Re aii and/or Re lacement Adjacent to Blend S stem FCV- 1 A, PCN 79-544 "<A-l, Radiation Control Manual; PCN 79-840. 79-545 N>> -64.2; Limitor ue Valve 0 erator Maintenance and Ins ection 79-546 %-1.1C,'recritical Technical S ecification Check Sheet PCN 79-547 %-6.11 Routine 0 exations Check Sheet', PCN 79-887. 79-548 PZ-13.4.2," Multimatic Delu e Valve S stem Testin - S stem Tur one Oz Reservoir PCN PZ-13.4.111 Multimatic Delu e Valve S stem Testin - S stem Ca e Tunne PCN PT-13.4.12 Alarm Valve S stem Testin - Fire S stem //12 Tur one Xs an S rxxL er PCN 79-549 "-SF-2 Reactor Refueli Outa e 0 erations and Activities PCN - 5 79-550 CC-1.3A Site Radiation Emer enc (Shift Foreman and Contro Room , 79-551 ~S-3.13 Pre-0 eiational Line U of Boxic Acid S stem, 79-552 N-44.2 Standb Auxi1i Feedwater (SAR<) S stem A x nment or orma eratxon,
PAGE 51 PORC PROCEDURE 79-553 '%-6.11 Routine 0 erations Check Sheet PCN 79-898. 79-554 0-6.4'ore Quadrant Power Tilt Calculation PCN 79-866. CP-6.10 T a and Delta T Ali nment at 70K Powei or Greater Loo A Unzt , PCN 79-555 QC-401 Control of Procurement Documents for Purchased Materia arts Com onents an Sena.ces PCN QC-701; Recei t and Acce tance of Materials PCN 79-QC-705 Control of Purchased Seduces PCN 79-861. QC-1403; Ins ection Status Control PCN 79-862. QC-1801 Ginna Station Res nse to Internal Audits'9-556 A-1502 Nonconformance Re rts PCN 79-762. PT-13.4.3, Flood Valve S stem Testin Fire S stem fI3 PT-'13.4.4 Floor Valve S stem Test'ire S stem!/4 PCN PZ-13.4.5, Flood Valve S stem Testin Fire S stem //5; PT-13.4.6; Flood Valve S stem Testin Fire S stem I!6
PAGE 52 PORC ITEM 7I 79-566 ""S-30.2,"RHR S stem Valve Position Verification'CN 79-899. 79-568 +A-64; Piessurizei Level Safet Injection Bistables 79-569 ~-231 Verification and/or Maintenance of Valve 1598 PCN 79-576 %-4.4; Char in Vari-Drive Overhaul Unit // - 'CN 79-575 +1-40; Surveillance and Maintenance of H draulic Snubbers'CN 79-576 "6-1.1B,'stablishin Containment Inte rit 'CN 79-897. 79-576 :%-1.1B, Establishin Containment Inte rit PCN 79-897. 79-577 M-67.1; Protomatic Delu e Fire S stems II's7 8 9 and 10" M-67.2; Delu e Valve Fire S stem // s 1 2 and li PCN 79-M-67.3, Flood Valve S stem Maintenance S stem Number 3' M-67.4 Alarm Valve S stem Maintenance S stem II's 12 13 M-67.5; Halon S stem Maintenance,'o uter Room and Rela Room,
PAGE 53 PROCEDURE M-67.6 Smoke Detector Maintenance to Piovide Instructions or Personne to Maintain t e Smo e Detector PCN M-67.7 'Contaixmant Post-Accident (kecirc) and/or Auxili Fi ter R. T. D. Maintenance PCN M-67.8; Star Co oration Heat Detectoi S stan Maintenance'-'67.9 Fire S stem - Hose Reel Isolation Valve Re lacement Va ve No PT-'13.1.8; Alaxm Valve S stem (Resettin Onl ) S stem ers, an PCN PT-2.9.1 Check Valve Exercisin guarteil Re irement CDT Disc e 79-578 E-15.1 Malfunction of Pressurizer Power Relief or Safe Va ves P ~ 79-579 KC-1.3A, Site Radiation Eme en (Shift Foreman and Contro Room N 79-580 %-3.2A, Char in and Volume Control S stem Pre-Startu A i nment, 79-581 %-15.2 Flux Ma in Emer en 4 Calibration Procedure, 79-583 N-'4lA Ali nt of Auxili Feedwater S stan Piior to Power 0 ration PCN
PAGE 54 PORC Xi'1 79-584 ""T-44.2 Standb Auxili Feedwater (SAFM) S stem A z nment or Norma eratzon, 79-586 +A-'52.2 Control of Locked Valve 0 eration, PCN 79-898. 79-587 ~-53 C cle VIIX-IXRefuelin, PCN 79-879. 79-588 PT-36, Stindb Auxili Feedwatei S stem Flow Check'CN S-4.5.5A, A Boron Rec cle Cation DX Resin Re lacement S-4.5.5B,'B Boron Rec cle Cation DI Resin Re lacement'-'4.5.4A A Boron Re cle Base Removal DI Resin Re lice-ment S-4.5.4B 'B Boron Rec cle Base Removal DI Resin Re lace-ment PCN S-'4.5.3A'A" Boric Acid Eva orator Condensate DemineralCer Resm e acement, S-'4.5.3B "B" Boric Acid Eva ritor Condensate Demineralizer Res>a .e acement 79-599 ~-230; Pi e Re lacement Ad acent to Blend S stem F 79-600 CC-1.2, Local Radiation Eme en Piocedure PCN 79-906.
PAGE 55 PORC iTEM j/ PROC1KQRE 79-60i +A-1401 Station Holdin Rules PCN 79-904. 79-602 +A-53.2; Three Month Lubrication and Maintenance Ins c-tron, PCN 79-606 WC-1.3B,'ite Radiation Emer en (Emei en oor ~tor an urve enter ssx. ees 79-605 "-PC-1.3; Dail Chemist Anal sis Results PCN 79-937. 79-608 A-53.0'reventive Maintenance Pro ram PCN 79-915. A-53.1, E i ment Ins ction Period and Lubricant List 79-609 +A-502; Plant Procedure Content and Format Re ements 79-610 <-15.1; Malfunction of Pressurizer Power Relief or Safet Va ves, PCN 79-611 %P-2.5, Qhole Bod Count Evaluation PCN 79-947. 79-612 '4-1.3, Reactor Staitu for Trainin PCN 79-939. 79-613 P-3 Precautions Limitations and Set oints P-3 eau.ca an o ume ontro stem P-8 Waste Dis sal S stem -PCN 79-942. 79-614 ~-'2.2; Residual Heat Removal S stem PCN 79-936.
PAGE 56 PORC iTEM f/ PROCEDJRE 79-615 ~-2.3 Safe d Valve 0 eration'CN 79-9Sl. 79-616 CT-4 Residual Heat Removal Loo Annual H dip Test of Low ressure 79-617 CF-14.4.2 Removin Reactor Vessel Guide Studs and Stud Hole u s nsta xn an enszonm ea tu s, 79-618 RC-1.7E Emer enc Radiation Monitoiin On-Site Surve Team H Oran e PCN s - an 79-6i9 S-3.1E lA Boiic Acid Senora e Tank Isolation/Restoration S-3.lF 1B Boric Acid Satori e Tink isolation/Restoration PCN 79-621. %-12.4; RCS Leika e Surveillince Record Instructions,'CN 79-623 0-6.2; Main Control Board S stem Status Verification PT-2.2; Residual Heat Removal S stem, ~ 79-902. S-30.1 Safet Injection S stem Valve Position Verifica-tion PCN S-30.3'ontainment S ra S stem Vilve Position Verifica-tron PCN 79-624 QC-701 Recei t and Acce tance of Mateiials, PCN 79-926.
PAGE 57 PROCEDURE (g-705; Control of Purchased Services PCiil 79-927. (g-1403; Ins ection Status Contiol PCN 79-928. QC-801, Contiol of Acce ted Materials'arts and Com n-ents PCN QC-802 identification and Marlcm of Mateiial PCN 79-QC-150l; Control and Dis sition of Deficient Materials'-803, Contiol of Items to be Reconditioned PCN 79-876. PT-36.2, Standb Auxili Feedwater S stem Recirculation F ow Test, PCN S-'4.5.7A "A" Letdown Mixed Bed DI Resin Re lacement, PCN S-4.5.7B'etdown Mixed Bed DI Resin Re lacement PCN S-ll.l Transfei of "A" and/oi "B" Boric Acid Stoia T to atc or oron nrzc nt an t e e-turn om Bate T to Boric Acr T s A ter En'.c-ment P "-PZ-13 Fire P 0 eration and S stem Ali nment PCN 79-954. S-30.1'afe Injection S stem Valve Position Verification, PCN
PORC iTEM y S-30.2 RHR S stem Valve Position Verification PCN 79-986. S-30.3'ontainment S ra S stem Valve Position Vexification PCN 79-634 "GS-31.0; Door Alarm S stem,'CN 79-953. 79-635 +A-52.2, Control of Locked Valve 0 exation PCN's 79-979 and 79-996. 79-636 %-16A,'achet In'ection S stem Ali nrrent PQl's 79-978 and 79-997. 79-637 +A-52.4; Control of Limitin Conditions for 0 eratin E i ment PCN 79-638 -23'ontainment Isolation Valve Leak Rate Testin PWi 79-957. 79-639 <S-ll.l'oric Acid Stora e Tank Transfer to Batch Tank Transfer to Bate Ta, PCN s - an 79-660 A-17, Plant 0 erations Review Committee 0 eratin *Procedure'CN A-58 Installation of Power Control or Instrumentation Cables at Gula N A-501 Plant Procedures Pre aration and Classification'CN 79-962. A-1001; Ins ection and Surveillance Activities, PCN 79-964. A-1101 Performance of Tests'CN 79-965.
PAGE 59 PORC PROCEDURE A-1102 Qualification of Test Personnel'eril 79-966. A-1703 S stem and E i ment Histoiies, PCN 79-967. A-903 Nondestructive Examination Control'CN 79-963.

<GS-43.0 Off-Loadin Poital Procedure'RES) 79-952.

79-644 CS-16.0 Pro er Removal'CN 79-325. 79-665 S-4.5.3 Boric Acid Eva ratoi Condensate Demineralizei Resin Re acement PCN S-4.5.4, Boron Re cle Base Removal DX Re lacement PCN 79-816. S-4.5.5'oron Re cle Cation DI Resin Re lacement PCN 79-815. S-4.5.7 Letdown Mixed Bed DX (A or B) Resin Re lacement PCN 19-666 "AR/C-l3, Containment Ventilation Isolation Reset in Reset Position, P 79-648 %-30.5 Standb Auxilia Feedwater Pum Valve Position Vera meats.on PCN

%-30.4 Auxilia Feedwater S stem-'Valve Position Verification'Vi'A-1303; Stora e and Preservation of Materials at Ginna Station',

PAGE 60 PORC ITEM // PROCEDURE

+A-1301 Control of Materiai Handlin and Handiin E i ment PCN 79-650 %-37.1, S stem Modification Re irements'Wi, 79-1002.

79-660 +A-55 Re ests for En ineer Desi Services PCN 79-97 19-66i +A-203; Ginna Modification P~oject Oi anization, PCN 79-989. 79-t'62 "-A-i:7pi'it Assurance Records PCN 79=ipi6. 79-663 <P-2ii.4, Check of Flow Contioi S stem for R-ll and R-12'CN 79-'664 ~8P-i.6'eutron E sure PCN 79-1015. 79-665 %P-li.10 Air S lin with Siersat Low Volume Air Sam es PC 19-666 &-11.8J Reactor Coolant . Motor Major Ins ection

- Mechanxca PCN - 9 79-667 %-1,1; Plant Heat U From Cold Shutdown to Hot Shutdown PCN 79-668 4-1.1C Precritical Technical S cification Check Sheet PCN 79-669 -'PC-5; Gage Isoto ic Anal sis of De assed Prima Coolant'9-670 WC-15.2, S ecific Conductance PCiii 79-990.

PAGE 61 PORC iTEM // PROCEDURE 79-671 'CC-1.15 Ins ection of Emer enc E i ment PCN 79-i0pi. 79-612 %T-5.20; Process Instiumentation Reactor Purification Protection C e rx est, CN 79-673 PT-13.4.3; Flood Valve S stem Testin Fiie S stem //3 H2 Seal Oil S stem,'CN 79-1010. PT-13.4.4, Flood Valve S stem Testin Fire S stem //4

-A Dz.ese Generator PCN PT-13.4.5; Flood Valve S stem Testin Fire S stem /I5 -B Dzese Generator PCN PT-13.4.6 Flood Valve S stem Testin Fire S stem //6 Auxxl'ee ater Lube Oil Reservoir PCN 79-675 A-60.1 Ginna Station Technical S cification Surveillance Pro ram A-60.3 Calibiation Suiveillance Pio ram for Instrumentation/

E ment o Sa e e ate Com nents CN 79-676 %-30.6 Safe d Valve Position Veiification (Inside C. V.) 79-686 +A-'601; Plant Proceduie Document Control PCN 79-925. 79-685 CT-2.2 Residual Heat Removal S stem PCN 79-1017. 79-686 "-P-9 Precautions'imitations, and Set ints P-9 Radiation Monztorm stem
PAGE 62 PORC ITEM iI PROCEDURE 79-687 A-301,'ontrol of Station i~fodifications', PCN 79-968.

/CD-5; Cleanliness Ins ection of S stems and Co. onents PCN 79-689 A-52.4' Control of Limitin Conditions fox 0 eratin E ui ment PCN 0-1.1; Plant Heat U From Cold Shutdown to Hot Shutdown PCN 0-2.2; Plant Shutdown from Hot Shutdown to Cold Shutdown PCN 0-2.3; Plant at Cold Shutdown'~i. 79-1047.

0-2.3.1; Drainin the Reactor Coolant S stem PCN 79-1044. 0-2.3.2; Fillin and Ventin~ the Reactor Coolant S stem, PCN 0-2.4 Plant Shutdown from Hot Shutdown to Cold Shutdown Durin B a out, PVil 0-2.5'lant Shutdown from Hot Shutdown to Cold Shutdown Mhen Con enser team is navai a e 0-7'li. nment and 0 eration of the Reactor Vessel Ove ressure Protection S stem PCN S-2.1, Reactor Coolant Pum 0 eration, PCN 79-1048. 79-690 ~A-52.2'ontrol of Locked Valve 0 eration'CN 79-1051.
PAGE 63 PORC INYf // PROCEDURE 79-691 +A-'52.4 Control of Limit Conditions for 0 eratin E ui ment'CN 79-692 +A-602 Plant Procedure Distribution PCS s 79-1060 and 79-1062.

"A-1301, Control of Material Handlin and Handlin E i ment PVi1 79-696 WP-6.10 T a . and Delta T Ali nment at 70% Power or Greater'oo , nest 79-695 <P-ll.0; Calibration ind/or Maintenance of P.L.P. Rack Modules Not Covere Ot er a ~ ration roce ures PCN 79-'696 %P-9.1 Steam Generator Blowdown Activit PCN 79-1067.

19-697 %-1 Precautions Limitations and Set pints P-1 Reactor Control an Protection S stem PCN 7-79-698 -PT-12.1 Emer enc Diesel Generatox lA 'eril 79-1058. 79-699 ~-16 Auxili Feedwater S stem'CN 79-1024. 79-700 ~-46' ecial Nuclear Material Ph sical Invento PCN 79-1054. 79-701 'AS-4.1V; Transfer of Waste Eva gator Feed Tink to Waste Holdu 79-702 %-26.4 0 crit'nstruction Co uter Rod Position Alarm Pro ram h 79-703 %-30.4; Auxili Feedwater S stem Valve Position Verification, PC5
PAGE 64 PROCEDURE "-S-30. 5, Standby Auxili Feedwater Valve Position . Veri ication PCN 7-WC-1.12C; S ecialized Call List PCN 79-1064. ~T-27.1, 1A Emer enc Diesel Generator Pre-Startu Ali nment PCN AT-27.2; 1B Emer enc Diesel Geneiator Pre-Startu Ali nment PCN "-'Z-44.2 Standb Auxili Feedwatei (SA'EV) S stem Ali nment for Norma 0 ration, PCN <N 75-9.24'WST Jet Shieldin Installation Rework'CN 79-1020. +A-502 Plant Procedure Content and Format Re uirements PCN 79-973. %-37.13 Ins ction and Maintenance of "A" Loo Accumulator. zsc ar e ecc a ve

%-37.14; Xns ection and Maintenance of "B" Loo Accumulator Dxsc ar e ec. Va ve V- P <

%-3.3D'VCS Cation Demineralizer Bed 0 erations Us'A" De rat'nit PCN 7 -1 %-23.5 Post Accident Charcoal Filter 0 eration, PCN 79-1084. +A-52.2, Control of Locked Ualve 0 eration, PCN's 79-1051 and 7- +A-603'ontrol of En,ineer'nd Desi n Documents B Central Recor s
PAGE 65 PORC iTEM PROCEDURE

+A-604 Gontrol of Construction Documents 'CN 79-975.

79-749 +A-803 Control of Items to be Reconditioned, PCN 79-1085. 79-750 CP-450.0 Ove ressure Protection Loo 450'CN 79-1078. CP-451.0 Ove ressure Piotection Loo 451; PCN 79-1079. CP-452.0; Ove ressure Protection Loo 452 PCN 79-1080. 79-751 CS-3.0; Securi Call List, PCN 79-1091. 79-752 Wf-ll.88 Reactor Coolant - Seal Ins ction and Service Mich-anz.ca PCN 79-753 <P,-l Precautions'imitations and Set ints P-1'eactor Control a Protect>on S stem P i 79-754 PT-5.10; Process Instrumentation Reactor Protection Channel Tii est PT-5.20 Process Instrumentation Reactor Purification Protection C e rx est, PT-5.30, Process Instrumentation Reactor Protection Channel Tri Test C e 79-755 -S-8A'om onent Coolin Water S stem Startu and Normal 0 eration a ve x. nment 79-756 %-30.4; Auxili Feedvater S stem Valve Position Verification'CN
PAGE 66 PORC ITEM 79-757 -S-30. 5, Staridb Auxi.Iia Feedwater Valve Position Vera. z.cat>on PCN 79-758 %-30.6; Safe d Valve Posi.ti.on Verificition (Inside CV)'CN 79-759 KC-3.15.8," Fiie S stem Locked Valve cl PCN 79-1i26. 79-762 A-101; Ginna lit Assurance Pro ram I lementati.on'CN 79-980. A-201 Ginna Station Admini.stritive and En ineerin Stiff Res n-sx. z. sties P < A-202, Girina Station Stiff Res nsibilities for Fiie Prevention PCN A-302're aration Review and A rovil of Des'n ut Documents or Manor Mo x. xcatzons, CN A-303; Pre aration'eview and A royal of Safe Anal sis for Minor M z. xcatzons or ec~ Tests P QCIP-31, Shi m Packi e //6144 Ins ection PCN 79-1081. TICP-12, Test Instrument Calibratiori Procedure o ta e a a. rator Cate o II DC 79-763 75-6.23 Service 'reiter Redundant Return Liiie Su oit Assemblies Insta at>on PCN

%M 75-50.31, Jet Shieldin Rework Main Steam and Feedwater PCN

PAGE 67 PORC PROCEDURE

%M 76-01.1 Safe rd Buses DC Control Volta e Monitor'CN WM 76-21.8; Reioute of Service Water Su 1 to Bitte Room Air Con at>oner, PCN '6M 77-1474.1; Reactor Coolant Pum Seal B ass Modification* PCN ""SM 77-1499.1, Rod Insertion Limit Circuit PCN 79-1114. "SM 77-1623.1 Char in Monorails, PCN 79-ili3. ~9M 77-1623.2'ed e Washer Installation - Char in Monorail; KM*77-1891.1 Electric Heat Tracin for Valves 825A and 825B'CN "SM 78-1464.1; Re lacement of Volume Control Tank Level Transmitters %M 78-1464.2; Re lacement of Accumulator Level Trinsmi.tters LT-935'SM 78-1890.2'eedwater Line Drain Valves after the Containment C e aves P i

5M 78-2133.1'alves 866A ind 866B Modification foi*Testin PCN

"-SM 78-2273.1; Armor Plate on the East Vill of the Control Room.

PAGE 68 PORC ITEN // PROCEDURE 79-778 <A-2.1 Receivin , Invento and Shi ment of Fuel'CN 79-1121. 79-779 -A-2.8, S ecial Nuclear Material Invento and Pecord Re irements PCN 79-780 &~ -37.18K Re air of the "A" Safet In'ection Dischar e Check Va ve PCN 79-783 QC-1301 Control ofYfaterial Handle and Handlin E ui ment PCN QC-1302 Stora e and Pieservation of Materials, PCN 79-ii29. 79-786 4-9; Piecautions Limtatxons and Set pints, P-9 Radiation Moni-tor~ S stem, PCN 79-787 PT-2.1, Safe Injection S stem s'CN 79-1145. PT-2.2 Residual Heat Removal S stem, PCN 79-1147. PT-2.7 Service Water S stem, PW 79-1146. PT-2.8 Co nent Cool'ater S stem PCN 79-1143. PT:2.9.1, Check Valve Quarterl Re irements Dz.sc e Exercis'CDT PCN - 1 PZ-3, Containment S ra s and NaOH Additive S stem','PCN PT-i6 Auxil Feedvater S stem PCN 79-1142.
l PAGE 69 PORC iTEM II PROCEDURE 79-788 %-7A RUST Purification PCN 79-1141. 79-789 >SC-3.15.8'ire S stem Locked Valve C clin PCN 79-1128. 79-795 <A-1.6 ~8A Committee 0 eiatin Procedure PCN 79-1184. 79-796 M-il.5B Major Mechanical Ins ection of AMP, PCN 79-1155. M-11.5C; Minoi Mechanical Ins ection of AFlIlP'CN 79-1154. M-11.5K Turbine Driven Auxili Feedwater Pum Major or Mec z.ca ns ection H-11.10; Major Ins ection of Service%Cater Pum PCN 79-1162. M-ll.12.1 Safe Injection ; Mechanical Ins ection PCN M-il.15; RHR Pum s Ins ection/Maintenance'CN 79-1156. 79-797 "%-11.5E; Pi efitters Ins ection of Motor Driven Auxili Feed PCN 7 - 1 79-798 ""SC-1.2 Local Radiation Emer en Procedure'CN 79-1185. 79-799 CT-5.20 Piocess Instrumentation Reactor Protection Channel Tri Test e 79-800 S-4.2.12, Gas Anal zer 0 eration PCN 79-1172. S-5 Pr S stem S lin PCN 79-1173.
PAGE 70 PORC PROCEDURE 79-801 +A-52.2; Control of Locked Valve 0 eration'CN 79-1152. 79-802 +A-53.0 Preventive Maintenance Pro ram, PCN 79-1198. 79-803 +A-54.1 'icensed Personnel Authorit PCN 79-1168. 79-804 +A-102.il Emer en Plan Trainin Pro ram* PCN 79-1196. 79-805 +A-502; Plant Procedure and Format Re irements PCN 79-1203. 79-806 +A-i40i Station Holdin Rules, PCN 79-1194. 79-807 +A-1701 Qualit Assurance Records PCN s 79-1135 and 79-1136. 79-808 E-l.l ', Safe In ection S stem Actuation PCN 79-i204. E-1.2 Loss of Coolant Accident PCN 79-1205. E-1.3 Steam Line Break Accident, PCN 79-1206. E-1.4 Steam Generator Tube Ru ture Accident PCN 79-1207. 19-809 %P-1.3 External E osure Records PCN 79-'ii74. 79-810 %P-5.2; Postin of Radiation Areas and Container Labelin 'Qi 79-811 4-'9'adi.ation Monitorin S stem, PCN 79-1209. 79-812 PC-1. 1 Pr 'oolant Anal sis Schedule and Limits PCN 79-1192.
PAGE 71 PORC ITEN 1I PROCEDURE PC-1.2 Non-Prima Coolant Anal si.s Schedule and Limits PCN PC*-1.3; Dai.l Chemist Anal sis Results'Vil 79-1193. 79-813 ~-21 Cleanin Boric Acid Tank Level Sensin Lines PCN 79-ii97. 79-814 'AS-3.1F; 1B Boric Acid Stora e Tank Isolati.on/Restoration', PCN 79-816 "-S-13A RHR S stem Lineu for Safe Injection'CN 79-1182. 79-817 %-13B'HR Isolation PCN 79-1179. 79-818 %-16A Safe In ection S stem Ali nt, P& 79-1180. 79-819 %-16.6 Drainin the B Accumulator PCN 79-1181. 79-820 -e-i6:ii Nonitoi and Enrichment of Acainailator Boron Concen-tratzon, 79-821 %-16.14; Isolation and Restorati.on of SI Pum s Suction Line from Boric cx s P 79-822 ~~-i6.i6 Safe In ection Pum Isolation'CN 79-1158. 79-823 %-30.2 RHR S stem Valve Position Verification'CN 79-1183. 79-824 "-T-41B Turbine Driven Auxili Fied Pum - Removal from Service'CN

-1

PAGE 72 PROCFJ3URE M-41D; Motor Driven Auxili Feedwater Pum Tsolation PCN "-~C-i0.i; S ecific Conductance,'CN 79-1170. A-37.0, Conduct of 0 erations for Safet Evaluation as Related to Facz z. M i z.cations S ecia Tests or eriments PCN 79-11 7. A-37:i ' stem Modification Re iiements PCN 79-ii66. QC-301 Work Start Authoiization PCN 79-ii6i .. QC-303 Control of S stem Modification Documentation'CN 79-1164. QC-304; Control of Modification Activities b the Ginna M x. >cation Prospect PCN CP-221.0, Calibration and/or Maintenance of RMS Channel'eril CP-221.1; Calibration of Ratemeter Drawer R-2 PCN 79-1187. CP-221.2, Calibration of R-21 Detector PCN 79-ii88. CP-221.3, Re lacement of Detector for K'6 Channel R-21 -'SC-1'adiation Emer enc Plan PCN 79-1218. ~Termnat~on 77-'1431.3 an Auxi.li C e out, Feedwater Flow Control PCN B ass Modification

- PAGE 73 PORC iTEM iI PROCEDURE 79-840 +A-52.4; Control of Limitin Conditions for 0 eratin E i ment'CN 79-841 -A-54.3, 0 en Flame Weldin and Grindin Permit'CN 79-1224.

79-842 +A-701 Recei t and Acce tance of Materials/Parts'CN 79-1223. 79-843 %P-8.4; Radioactive Source Invento PCN 79-1219. 79-844 %-67.3, Flood Valve S stem Maintenance S stem Number 3't 5CN 79-845 %-3.3Cj H or 0 Re val.From Pr' stem B B Volume

~Contto TaiiFVit, PCN 79-846 C-4.1A; Li id Waste Process Startu PCN 79-1201.

79-847 '4-13A RHR S stem Lineu for Safe Injection PCN 79-1211. 79-849 M-'73.2 Weldin~ on Stainless Steel Pi in or Co onents PCiil 79-32. M-73.3'eld on Carbon Steel Pi in or Co nents PCN 79-31. QC-'101 Ginna QA Pro ram I lementation PQ'1 79-1215. QC-201; Ginna Quali Control 0 anization PWi 79-1214. QC-702, Recei t of New Fuel PCN 79-1227. QC-904 Nondestructive Examination, PCN 79-1213.
PAGE 74 PROCEDURE (g-1204, Calibration of Process S stem Instrumentation PCN

-1502 Nonconformance Re rts'CN 79-1212.

(g-1703 Record Stora e Facilit and E i*ment PCN 79-1225. >>A-17; Plant 0 erationt Review Committee 0 eratin Procedure'PCN >>A-54.4, Du En ineer s Res nsibilities,'CN 79-1232. >>AR/E-12 NIS Power Ran e Lowei Detector Hi h Flux Dev. oi Auto De eat PCN 7 -1 >>AR/E-26, NIS Power Ran e Channel Deviation, PWi 79-l244. >>CP-81.0 Calibration Procedure for TQTP 650 Dual Bench Tester for Tor ue Wrenc es PCN 7 -1 "CP-81.1 Calibration Procedure for Tor e Wrenches PCN 79-1229. >>E-l.l Safe Injection S stem Actuation PCN 79-1270. ~E-1.4; Steam Generator Tube Ru ture Accident PCN s 79-1153 and CS-3.0, Securi Caii List PCN 79-1236. aS-26:i'noccu ied Vital Area Ke Control and Accountabili PCN
PAGE 75 PORC ITEM i/ 79-872 %-15.1; A or B Diesel Generator Removal From Service'CN 79-1262. 79-873 %>> -73.10; Weldin PCN 79-1255. 79-874 m-i7.2 Process Radiation Monitors R-ii - R-21 and Iodine Monitois R-1 A an R-1 B, PCN 7 -1 7 79-875 ~-36.2, Standb Auxili Feedwater S stem Recirculation Flow Tes 79-877 4-30.5 Standb Auxilia Feedwater Pum Valve Position era. xcatxon P i s - an 79-878 CC-1.7C'onitorin Site Radiation Level B TLD'CN 79-1266. 79-879 ""SC-1.7D Emer en Radiation Monitorin Off-Site Surve Team /39D Re PCN 79-880 "-SC-1.7F Emer enc Radiation Monitorin Off-Site Suive Team //9F reen , 79-881 KC-1.7H,'ier enc Radiation Monitorin Off-Site Surve Teim /i9H Oran e , PCN 79-882 %M 77-143l.3 Auxil'eedwater Flow Control B ass Modification Termaatxon an C e out PCN 79-885 A-54; Ginna Station Administrative and E ineerixi Stiff Res n-sz z itches PCN A-54.2'ixirii Station Staff Res nsibilities for Fire Prevention'
PAGE 76 PROCEDURE SC-3.15.6; Pire Hose Reel Ins ection PCN 79-1269. E-1.5 Void Formation in the Reactor Coolant S stem PCii1 79-1208. HP-7.9 1000B Gamma Calibrator 0 eration PCN 79-1230. %M 79-241I9.1 Safet Injection Lo ic Modification'CN 79-1278. %-5.1 Load Reductions PCN 79-'1242. -PT-5.10 Process Instrumentation Reactor Protection Channel Tri Test C e CN -PT-5.20; Process Instrumentation Reactor Protection Channel Tri Test C e P < CT-5.30, Process Instrumentation Reactor Protection Channel Tri Test C nne PCN s ~-5.40; Process Instnmantation Reactoi Protection Channel Tri est e +A-304 Pre aration Review and A royal of Desi n Out ut Documents or > xnor M z. xcatzons 4-8; Natural Circulation in the RCS PCN 79-1247. KC-3.19; Maintainin Access to H drants Dur'evere Snow Storms'CN %-22.1 Malfunction of the Char S stem PCN 79-1312.
PAGE 77 PROCEDURE <X-22.2, Co lete Loss of Char in Flow Due to Ru ture of S stem -E-22.3 Malfunction of the Letdown S stem, PCM 79-1310. m-i'.:4 Noble Gas E osure PCN 79-i3iS. ~-2.1 Llhole Bod Countiri Guide'CN 79-1316. %P-2.3'LD Reader Calibration, PCN 79-1314. "-HP-6.3 Personnel Decontamination PCN 79-1317. %P-6.4 Contaminated Clothin Re rt Form Use PCN 79-1318. %P-8.1'adioactive Source Use PCN 79-1319. "RD-4, Vent Radi, is Back round and Factor Determination ~i ~-ll; Recei t of Radioactive Materials, PCN 79-1321. t -A-1; Radiition Control ~1finuil ~i. 79-1276. +A-201, Ginna Station Administrative and E meerizi Staff Res nsi x x.tres, PCN +A-1702 Record Stora e Facilities and E i ment" PCN 79-1297. +AR/D-18 Intermediate Ran e Reactoi Tem . PCN 79-1300.
PAGE 78 PORC iTEM Il PROCEDURE 79-913 E-12.1 Malfunction'od Cluster Control Full Len th Rods'GV E-'13.2; Intermediate R e NIS Malfunction (IR-35 or -36) PCN E-13.3'ource Ran e NIS Malfunction (SR-31 or -32) PCN 79-1289. E-13.4, Malfunction of Start-u Rate Com arator or Flux Deviation C e N- N- or U er an Lower Ion Ch er PCN 79-1 E-18.1 Loss of S ent Fuel Pi.t Cool'ue to the Failure of the ent Fue Pat Pum PCN E-19 Continuous Insertion of RCCA Control Bank P&i, 79-1292. E-37.4; Stickin of a Fuel Asseaibl Inside the Reactor Vessel or Insz. e t e Trans er Bas et E-38 Loss of Service Water PCS 79-1295. 79-916 "-HP-'2.4, TLD Readout PCN 79-1313. 79-915 ~-6.1 Neutron E sure PCN 79-1275. 79-916 'AHP-9.1; Steam Generator Blowdown Activit 'CN 79-1277. 79-917 %-52.3'ncore Thimble Clean'CN 79-1309. 79-918 %-6.4.1 Refeience E ilibxium Indicated Axial Flux Difference Deteracnatxon PCN 7-79-919 %-9 Radiation Monitori S stem ~ 79-1274.
PAGE 79 PROCEDURE ~-2.5 Air 0 crated Valves, Quarterl Surveillance PCN 79-1283. ~-2.9.1 Check Valve Exercisin Quarteil Re iiement (RCDZ Dxsc e, ~-36.2; Standb Auxili Feedwater S stem Recirculation Flow Test CM 77-1431.3, Auxil Feedwater Flow Control B ass Modification Teraunatxon an C ec out CN N-27.2; 1B Emer en Diesel Generator Pre-Staitu Ali nt PCN %-36.1; Station Service Water Header Valve Ali nt for Two Loo ration, <T-'41A'li nment of Auxi.li Feedwater S stem Prior to Power 0 ration PCN CYf-233; Rewora of Pi e Su its Base lates and Anchor Bolts PCN WSI-9; Inservice Ins ection of Wed e e Anchor Bolts PCN A-102.1 Facili Staff Trainin Pro ram Ginna Station Personnel Traxnm Pro ram PCN A-ip2:11 'mer en Plan Trainin Pro ram PCN 79-1355. A-102.13 R. E. Ginna NRC'icensin Train'ro ram'Ciil 79-1356.
PAGE 80 PROCEDURE E-29.1 Loss'f Normal Feedwater (Not Recoveiable)'CN 79-1351. E-29.2 Loss of Normal Feedwater (Recoverable) PCN 79-1352. %-37.11 Piessurizer Power 0 crated Relief Valves 430 and 431C Re aux an Ins ection, PCN

%-1.2 Plant From Hot Shutdown to Stead Load PCN 79-1353.

~-2.1 Safe Injection S stem s PCN 79-1341. PT-2.5.1; Air 0 eiated Valves'iarterl Surveillance (Contairiment) PCN PT-'2.5.2; Air 0 rated Valves Quarterl Surveillance (Valves liRB an C, PT-2.6 Cold/Refuelin Shutdown Air 0 crated Valve Surveillance'CN 'APT-2.9 Check Valve Exercisin Quarterl Re irement PCN 79-1337.

¹7 13.4.8 Protomatic Delu e Valve S stem Testin S stem (/8 (Maiii Trans ormer PCN

%-23.2.2 Containment Pur e Procedure PCN 79-1343. KC-3.3.2 Off-site Notification of Fire PCA 79-1329. 'CM 77-1431.3 Amili Feedwater Flow Control B ass Modification ermnat~on an e out
I PAGE 81 PORC iTEM 1/ PROCEDURE 79-954 %-27.1; 1A Emer en Diesel Generator Pre-Start Ali nment P& 79-955 N-27.2, 1B Emer en Diesel Generator Pre-Startu Ali nt PCN 79-956 M-41K; Alternate Mater Su 1 foi Auxil'eedwater s PCN 79-956A eSi-8 Inse~ce Ins ction of Feed ater Nozzle Velds'CN 79-1324. 79-9568 CYf-232 Re air of Feedwater Pi in Inside Containment PCN 79-1358. 79-957 CM 79-01.1; Feedwater Drain Lines Inside Containment PCN 79-1359. 79-958 AR/H-31'acuum Primin S stem'CN 79-1345. AR7tL-12, Condenser Pit Screen House Hi Level PCN 79-134'-i . E-7 Dro of a Full Len th Rod Cluster Control Assembl 'CN 79-1 E-'21 Malfunction of Reactor Make-u Control PCN 79-i949. 0-1.1D Pre-Heatu Plant Re ement Check List PCN 79-1357. PR-9A Protective Rela Calibration and Tri Test Reactor Tri6 Un er e enc Protection Bus , PCN PR-'9B, Protective Rela Calibration and Tri Test Reactor Tri n er e en rotection us
PAGE 82 PORC lf PT-5.50; Auto Sto Oil Pressure Switch and Rela Test PCN 79-1332. PZ-13.2 Diesel Fiie Standard Protection Test,'CN 79-1333. RS*SP-13.3 H dro on WDS Class "C" Safet Related Pi in - Part 1 Waste Hol u Tank Area WHUT PCN 7 -1 RSSP-13.4 H dro on WDS Class "C" Safet Related Pi in - Part 2 S Ta c Pum Area, PCN -1 S-3.2F Drains the A; B or C CVCS Holdu Tank to the Waste Ho u Tam Vza .t e Sum T Pum , PCN -13 79-958A E-13.4; Malfunctiori of Start-u Rate Com arator or Flux Deviation C e N- , N- or U er and Lower Ion Cham>er PCN 7 -1 7. E-22.1 Malfunction of the Char9 in S stem PCN 79-1350. 79-962 >XSI-9; Inservice Ins ction of Wed e T e Anchor Bolts PCN 79-965 MSI-8 Inservice Ins ection of Feedwater Nozzle Welds, PCN 79-1413. 79-966 ~-36.2,'tandb Auxi.li Feedwater S stem Recirculation Flow Test PCN 79-967 E-l.6'VCS Leak PCN 79-1302. M-37.55.1' ra Addi.tive Valve Controller Re air (836A or 836B). S-3.3H; Non-Condensible Gas Bubble in the RCS PCN 79-1296.
PAGE 83 PORC iTEM'I EUXEXRE 79-967A ~-234 Re air of Feedwater - Steam Generatoi Nozzles PCN 79-1460. 79-968 EM-163 Re aii of 10'ire Main Between Turbine Buildia and Bm. zn, EM-'165 Boric Acid Pi e Line P.e airs Between Valve 827B and 1B Horse Ac> Stora e T PCN EM-166 Boric Acid Pi e Line Weld Re airs Between Valves 827A and B an Va ves A an We Jolt No. PCN EM-167, Safe Injection Suction Pi ' dro PCN 79-1381. EM-168 Safet Injection Pum Suction Pi in H dro for Re aired Pz m PCN EM-171 Divert Line Leak Re air Between 112A Letdown Diversion D Divert to CVCS HUT PCN EM-172; "A" Mixed Bed Demineralizer Pi in Lei1c Valve Re ii'CN EM-176, Li d Penetrant Indication Removal on Letdown Line to Re en- eratxve Heat Exc er PCN EM-177, Re air of Pi to Valve Bod Weld on Downstream Side of Va ve B PCN EM-178; Re lacement of Alternate Char in Check Valve 383B PCN EM-i8i Re lacemhnt of Mani ulator Crane Ceramic 300 Watts 3 Ohm Resistor,
PAGE 84 PORC ITEN // EN-182 Li id Penetrant Indication Removal on Pr'oolant Pi in PCN 7 -1 KH-189 Auxili Buildin Crane - Re air of Misali nment Rail En s, EM-191'e air of Weld Downstream of Non-Re enerative Heat Exc er CN EM-192'e air of Leak on BHR S stem Near Valve 718A PCN 79-1370. EN-193 Enlai e Two Holes in the Instrument Shield Protection at Va ves an PCN 79-1 GS-22.0'o utei Guard Check'CN 79-1395. 79-969 HP-9A Actions foi an P.-21 Alarm'CN 79-1362. PT-13.1.13 Star Co oration Heat Detector S stem Test PCiil PT-15.1, Reactor Coolant S stem Power 0 crated Relief Valve Timin PT-32.1'lant Safe d Lo ic Test "A" or "B" Train PCN 79-1428. RSSP-2.5; Service Water Pum Dischar e Check Valves'CN 79-1427. RSSP-10.1'onditions for Hain Steam Safet Valve Test PCN
PAGE 85 PORC I RSSP-13.5, H dro on Class "C" Safet Re ated Pi in (S ent Resin Stora e Tanks an Resm Dxsc r e Lanes om CVCS DI s PCN RSSP-15.1 H dro Class "B" Safe an Containment S ra Suet>on Px ~ Related Pi. in (Safe

, to Inc u e NaOH Px, 'CN In ection RSSP-15.2, H dro Class "B" Safet Related Pi in (Reactor Coolant Let own - sz. Pressure Rate Sect>on PCN 79-971 CP-429.0, Pressurizer Piessure Channel "429"; PCN 79-1410.

CP-429.7 Pressurizer Pressure Bistable PC-429B PCN 79-1404. CP-449.0; Pressurizer Piessure Channel '449"; PCN 79-1411. CP-449.7'ressurizer Pressure Bistable PC-449B PCN 79-1408. 79-972 ~XSI-8, Inservice Ins ection of Feedwater Nozzle >lelds PCN 79-1433. 79-973 "Of-37.18K, Re air of "A" SI Dischar e Check Valve 889A PCN 79-974 -2.1,'afet InjecCion S stem s'CN 79-1414. 79-975 >M-2.3.1 Post Accident Charcoal Filter Dama e PCN 79-1366. 79-976 PT-2.4, Cold/Refuelin iMotor 0 eiated Valve Surveillance, PCN
PAGE 86 PORC iTEM // PROCEDURE PT-2.4.1 Cold/Re&ielin Motor 0 rated Valve Surveillance (BHR S stem Va ves PCN FZ-2.7 Service Mater S stem, PCN 79-1434. PT-3; Containment S ra Pum s and NaOH Additive S stem'CN 79-977 PT-5.10 Process Instrumentation Reactor Protection Channel Tri Test C e P PZ-5.20 Process Instrumentation Reactor Protection Channel Tri Test C e PT-5.30'rocess instrumentation Reactor Protection Channel Tri Test e PT-5.40 Process instrumentation Reactor Piotection Channel Tii. Test C e PCN 79-978 CT-'13 Fire Pum 0 eration and S stem Ali nment PCN 79-1365. 79-980 M-17.2 Process Radiation Monitors R-ii to R-21 and Iodine Monitors R- A an R- B PCN 79-981 ~-20 Main Steam Isolation Valve Solenoids Tri Test'CN 79-1425. 79-982 PT-23.1; Containment Isolation Valve Leak Rate Testin Pressurizer Re xe as Ana zer me PT-23.2 Containment Isolation Valve Leak Rate Testin Nitro en Su to ressur~er e ze
I PAGE 87 PROCEDURE PZ-23.3; Containment Isolation Valve Leak Rate Testin Hike-u Mater to Pressurizer e e~ T , PCN PT-23.7 Containment Isolation Valve Leak Rate Testin Letdown from Reactor Coo ant S stem PCN PZ-'23.8; Containment Isolation Valve Leak Rate Testin RCS Char Lme PCN PT-23.10'ontainment Isolation Valve Leak Rate Testin Alternate C m me PT-23.11 Containment Isolation Valve Leak Rate Test RCP Seal Water Return an Ecess Let own PCN PZ-23.12A Containment Isolation Valve Leak Rate Testin Steam S ace S e, PCN PZ-'23.12B Containment Isolation Valve Leak Rate Testin Pressurizer z x. ace am e PT-23.12C'ontainment Isolation Valve Leak Rate Testin RCS S le Loo PCN %ro sed Technical S cification C e - Ovei-ressurmatzon Protection. 4SSP-15.12; ISI H dro Test of Class "B'" Pi in (A and B Steam enerator e ater 4Yf-170'ontainment S ra Additive Valve Controller Re air (836A or B
PAGE 88 iTEM "II PROCEDURE 79-997 %M-235 Furoumitin NGV-700 RHR Fiom "A Loo PCN 79-1516. 79-997A ~-236; Fuitnanitin Valve 296 Anil' ra to Piessurizei PCN 79-9978 -'KM-237; Weld Re air Connection at "A" Feedwater Line from MDAFWP 79-997C 'KM-238; Weld Re air Connection at "A" Feedwater Line from TDABP 79-998 WA 77-1660.50; RCS Ove ressurization Protection S stem cz.at>on 79-10Oi +A-52.2'ontrol of Locked Valve 0 ration PCS 79-1W7. 79-1002 +A-52.4 Control of Limitin Conditions for 0 eratin E i ment' 79-1003 +A-1105 Calibration Surveillance Pr ram for Tnstrumentation/E ment o a e Re ate om nents CN 79-1004 CP-ii':i, Pressurizer Pressure Controller PC-43lK PCN 79-1478. CP 426 0j Calibration and j or Maintenance "426" Pressurizer Level PCN s an CP-426.1 General Defeat Piocedure "426" Pressurizer Level PCN CP-426.2 General Reinstate "426" Pressurizer Level PCN 79-1466.
I j Pi l; j t) (
PAGE 89 PORC iTEM /I PROCEDURE CP-426.5 Pressurizer Level Bistable LC-426 A)B; PCN 79-1467. CP-'427.0 Pressurizer Level Channel 427 PCN 79-1471. CP-427.i Defeat of '427'ressurizer Level PCN 79-1472. CP-427.2; Reinstate 427'ressurizer Level PCN 79-1473. CP-427.5 Pressurizer Level Bistable LC-427 A/C PCN 79-1470. CP-428.0; Pressurizer Level Channel 428 ; PCN 79-1469. CP-428.1 Defeat of 428 Pressurizer Level PCN 79-1468. CP-428.2 Reiristate 428 Pressurizer Level PCN 79-1474. CP-428.5 Pressurizer Level Bistable LC-428 A/E PCN 79-1475. CP-429.1'eneral Defeat Procedure Pressurizer Piessure Channel CP-449.1 General Defeat Procedure for Pressurizer Pressure Channel 79-1005 ¹N 175; Re lacement of Main Steam Vent Valve 3503 PCN 79-1515. 79-1006 +l-37.11, Pressurizer Power 0 rated Relief Valves 430 and 431C Re mr an Ins ection PCN 79-1007 Wi-52.3 Incore Th~nble Cleanin PCN 79-1368.
PAGE 90 I~PORC PROCURE 79-1008 "6-2.2; Plant Shutdown from Hot Shutdown to Cold Shutdown; PCN's 79-1009 PT-23.13A, Containment Isolation Valve Leak Rate Test "A" Steam Generator S e P PT-23.13B; Containment Isolation Valve Leak Rate Testin "B" Steam Generator S le PCN -1 PT-23.14; Containment Isolation Valve Leak Rate Testin Air Sam le In et PT-23.15; Containment Isolation Valve Leak Rate Test* Contaiament Axx Sam e Out et, PT-23.16A; Containment Isolation Valve Leak Rate Test'A" Steam Generator B ow own ~i PZ-23.16B Containment Isolation Valve Leak Rate Testin "B" Steam enerator B ow own PT-'23.17A Containment Isolation Valve Leak Rate Testin Contaia-ment Pressure Sensa'ransmitter PT- an PZ-PT-23.17B, Containment Isolation Valve Leak Rate Test'ontain-ment Pressure Sensm Transao.tter PT- an PZ- PCN PT-'23.17C Contaixment Isolation Valve Leak Rate Testin Contain-ment ressure Sensm ransau.tter - an PT-23.18A Containment Isolation Valve Leak Rate Test' Con-talent S ra ea er
PAGE 91 PROCEDURE PZ-23.18B Containment Isolation Valve Leak Rate Testin "B" Con-tmnment S ra Hea er PCN PT-23.19 Containment Isolation Valve Leak Rate Testin Safe Injection S stem, PCN PZ-23.20; Containment Isolation Valve Leak Rate Testin R.C.D.T. Gas Hea er PCN PT-23.21 Containment Isolation Valve Leak Rate Testin R.C.D.T. to as Ana zer PT-23.22 Containment Isolation Valve Leak Rate Testin R.C.D.T. Dms e, PCN PT-23.23 Containment Isolation Valve Leak Rate Testin S "A" Dz.sc e, PCN "-PT-32.1'lant Safe d Lo ic Test A or B Train PCN 79-1489. ~SP-2.2 Diesel Geneiator Load and Safe d Se ence Test'CH 4Yf-239 CV S ra Rin Header Pi Cl Re lacement, PCN 79-1540. ~-'240, Rework of Pi e Su rts Pi e Su rt ECN-2512 PCN ~-241'solate and Drain the Standb Auxil Feedwater Lmes or Rewo o Pz. Su orts APV- an AR
PAGE 92 PORC Imi /I PROCEDURE 79-1023 ~-242 Isolate and Drain Service Water Line for Rework o Pa. Su orts SW- SW- 1 and SW-1 PCN 79-1573. 79-1024 ~-243 Fillin Ventin ', and H drostatic Testin of Portions of th SAFW an Portion o t e Service Water S stem PCN -15 1. 79-1026 %-36.1 Station Service Water Header Valve Ali nment for Two Loo 0 ration PCN 79-1029 WM 79-1662.1; Installation of Snubber Platforms, PWi 79-1510. 79-1031 ~-200 Re lacement of Rework of Solenoid Valves for CV Pur e E ust Valve 5 7 PCN 79-1 79-1033 AR/G-28; Steam Generator "A" Lo Lo Level Sin le Channel Alert'CN AR/G-30 Steam Generator "A" Lo Lo Level Sin le Channel Aleit'CN 79-1034 CP-10.1 Defeat of Delta Flux Si nal Channel 1 PCN 79-1518. CP-10.2 Reinstate of Delta Flux Si nal Channel 1 PCN 79-1522. CP-20.1'efeat of Delta Flux Si 1 Channel 2'CN 79-1519. CP-20.2 Reinstate of Delta Flux Si 1 Channel 2 PCN 79-1524. CP-30.1; Defeat of Delta Flux Si 1 Channel 3 PCN 79-1520. CP-30.2 Reinstate of Delta Flux Si 1 Channel 3; PCN 79-1525.
PAGE 93 PORC iTEM // PROCEDURE CP-40.1; Defeat of Delta Flux Si al Channel 4; PCN 79-1521. CP-40.2'einstate of Delta Flux Si nal Channel 4 PCN 79-1523. CP-41.2 General Reinstate Procedure foi N-41 POi 79-1'526. CP-42.2; Reinstate Power R e Channel N-42 PC>V 79-1529. CP-43.2; General Reinstate Procedure for N-43 PCN 79-1528. CP-44.2'eneral Reinstate Procedure for N-44 ~i 79-1527. 79-1035 ~-236; Furl~itin Valve 296 - Auxili S ra to Pressurizer PQ'

-155 79-1036 NSi-9; Inservice Ins ection of Wed e T e Anchor Bolts', PCN 79-1037 %-37.11 Pressurizer Power 0 crated Relief Valves 430 and 431C Re air an ns ection, 79-1038 "~&43.26; Installation of Steam Generator Second Manwa Cover S , PCN 79-1039 "6-7; Ali nment and 0 eration of the Reactor Vessel Ove ressure Protection stem 79-1040 >'PT-2.8,'o nent Coolin Water S stem'PCN 79-1511 .

79-1041 %T-3; Containment S ra s and NaOH Additive S stem, PCN
PAGE 94 PORC limni // PROCEDURE 79-1042 ~-13.4.il; Multimitic Del e Valve S stan Testin S stem*//11 Ca e Tunnel PCN -15 79-1043 "-ii-i6;i, Auxili Feedwatei S stem Flow Balance PCN 79-1542. 79-i044 PT-23.24; Containment Isolation Valve Leak Rate Testin Reactor u rt oo ers In et an t et , 1 PZ-23.26 Containment Isolation Valve Leak Rate Testin Auxili Coo ant S stem to A Reactor Coo ant Pum PCN - 5. PT-23.27; Containment Isolation Valve Leak Rate Testin Auxilia Coo ant S stem to Reactor Coo ant ~i PZ-'23.28; Containment Isolation Valve Leek Rate Testin Auxili Coo ant S stem om Reactor Coo ant P PT-23.29 Containment Isolation Valve Leak Rate Testin Auxili Coo ant S stem om B Reactor Coo ant PWi - 5 PZ-23.30 Containment Isolation Valve Leak Rate Testi Auxili Coo ant S stem Excess Let own Su an Return PCN PZ-23.32; Containment Isolation Valve Leak Rate Testino Instrument Azz, PT-23.33; Containment Isolation Valve Leak Rate Testin Service Axr PCN PZ-23.34 Containment Isolation Valve Leak Rate Testin De res-surz.zatxon at Power P
PAGE 95 PROCEDURE A-1.6.1 Documentation of '"As Low As Reasonabl Achievable" (ALARA) Pro ram, PCN 7 -1 33. M-37.6l Valve HCV-105 Isolation Xns ection and Maintenance PCN

-A-'52.4, Contxol of Limitin Conditions foi 0 eratin E 'ent'A-7pi Recei t and Acce tance of Mateiial/Parts'PCN 79-1632.

+A-1001 Ins ection and Surveillance Activities PCN 79-1611. AR/AA-6; RCS Ove ressure, Arm/Inhibit Loo A Select'CN 79-1625. AR/AA-7 RCS Ove iessure Arm/Xnhibi.t Loo B Select'CN 79-1626. CP-'431.0, Calibration and/or Maintenance of Pressurizei Piessure C e PCN

/

'CP-431.2'eneral Reinstate Procedure Pressurizer Presssure Channel WP-449.1 Geneial Defeat Procedure for Piessurizer Pressure Channel PCN ~-461.0, Calibiation and/or Maintenance of Steam Geneiator Level C e PCN WP-462.0 Calibration and/or Maintenance of Steam Generator Level C e
PAGE 96 PORC IT'EM "// PROCEDURE 79-1071 C el, CP-463.0; Calibiation and/or Maintenance of Steam Generator Level PCN e, CP-471.0; Calibration and/or Maintenance C PCN of Steam Generatoi Level CP-472.0; Calibration and/or Maintenance of Steam Generator Level C e 79-1072 CP-473.0; Calibration and/or Maintenance of Steam Generator Level C e P 79-1072 CP-473.0; Calibration and/or Maintenance of Steam Geneiatoi Level C e 79-1073 CP-626.1 Defeat of Residual Heat Removal Flow Channel 626 PCN

'P-626.2, Reinstate of Residual Heat Removal Flow Channel 626; PCN 79-1074 ""EM-173' r Re air of Main Steam Vent Valve 3503 Usin urmanxte Process PCN 79-1075 CZ-232'e air of Feedwater Pi ixi Inside Containment,'CN 79-1590.

79-1076 "-KM-246 F ~enite Re air - Pressurizer S ra Valves 431A and B 79-1O77 %P-2.2 Whole Bod Count 0 rations PCN 79-1617. 79-1078 NSI-8 Inservice Ins ction Feedwatei Nozzle Welds'Vi/ 79-1602.
PAGE 97 PORC PROCEDURE 79-1079 Ni-'3.2, Reactor Cavi Cleanu and Decontamination, PCN 79-1612. 79-1081 %-1.1; Plant Heatu From Cold Shutdown to Hot Shutdown'CN's 79-1082 ¹1.1D Pre-'Heatu Plant Re xement Check List,'CN 79-1614. 79-1083 %-1.2 Plant From Hot Shutdown to Stead Load PCN 79-1609. 79-1084 %-1 Reactor Control and Protection S stem, PCii1 79-1576. 79-1085 ~-2.2 Residual Heat Removal S stem PCN 79-1636. 79-1086 ~-2.9; Check Valve Exercisin Quarterl Re 'nent, PCN 79-1627. 79-i087 PZ-5.10, Process Instrumentation Reactor Protection Channel Tri Test C e PCN PZ-5.20; Process Instrumentation Reactor Protection Channel Tri Test e PT-5.30 Process Instrumentation Reactor Protection Channel Tri Test C e PZ-5.40 Process Instrumentation Reactor Protection Channel Tri Test C e 79-1088 ~-7 H dio Test of Reactor Coolant S stem PCN 79-1628. 79-1089 PZ-23.48 Containment Isolation Valve Leak Rate Testin Deadwei ht ester
1 PAGE 98 in'/ PORC PROCEDURE PT-23.49; Containment Isolation Valve Leak Rate Testin Con-structzon Fire Service Mater PCN -1 PT-23.50A Containment Isolation Valve Leak Rate Testin Contain-ment Post Aces. ent Axe Sam e C ean Interme sate Bur. PCN PZ-23.50B'ontainment Isolation Valve Leak Rate Testin Contain-ment Post Acci ent Au.. S e Containment Interme z.ate Bum PT-23.50C'ontainment Isolation Valve Leak Rate Testin Contain-ment Post Acct ent S e uzi Bm. m CN PZ-23.51A; Containment Isolation Valve Leak Rate Testin "A" H ro en Reco oner Pi ot an Mam PCN PT-23.51B'ontainment Isolation Valve Leak Rate Testin "B" H r en eco e'er z. ot an .ann PT-23.51C Containment Isolation Valve Leak Rate Test'A" and "B ro en eco xners en eu 79-1Q9Q "8SSP-15.12 H dro Test of Class "B" Pi in ("A" and "B" Steam Genexator Fee ater Px. , PCN s an - 595. 79-1091 '5-13A RHR S stem Lineu for Safet In 'ection PCN 79-1631. 79-1092 CC-3.3.2; Offsite Notification of Fire'CN 79-1601. 79-1093 'SM 77-1660.50; RCS Ove iessurization Protection S stem Annuncia-tion
PAGE 99 i~PORC lf PROCEDURE 79-1097 ~:Z-41A; Ali nment of Auxilia Feedwater S stem Prio to Power rations CN s - an 79-1098 M-44.2 Standb Auxili Feedwater (SAR/) S stem Ali en'or Normal 0 eration PCN s 79- and -1 79-1107 .~-247; Rework of Pi Su rts for S stem PCN 79-1684. 79-1108 ~-16.2; Turbine Driven Auxili Feed Lube Oil Te erature 79-1110 "CP-431.12'ressurizer Pressure Bistable PC-431F'CN 79-1645.

%D-13.1; EfQuent Monitor Set ints PCN 79-1569. %-27.2238 Valve 2238 Isolation PCN 79-1558.

79-1112 "A-20, Control Room Lo s, PCN 79-1692. 79-1113 +A-602'lant Procedure Distribution PCN 79-1323. 79-1114 +A-1702, Record Stora e Facilities and E 'ent PCN 79-1698. 79-1115 +AR/C-27 Pressurizer Lo Pressure Safe In ection Sin le Channel ert 79-1116 AR/C-28 Pressurizr Lo Pressure Safe In'ection S le Channel ert PCN AR/D-19 Pressurizer Lo Pressure PCN 79-1653. 79-1117 +AR/F-10 Pressurizer Lo Pressure'CN 79-1650.
PAGE 100 PORC ITEM "// PROCEDURE 79-iii8 m-i5.i Malfunction of Pressurizer Power Relief 'or Safe Valves'CN

-1 79-1119 M-43.20A; "A" Steim Generator Second Side Pressure Test PCN M-43.20B "B" Steim Generator Second Side Pressure Test'CN 79-'ii20 68-76.i Instillation and Test S 1'f Gioutin 'Ci'~ 79-1682.

79-ii2i a-i:iC; Precritical Technical S ecification Check Sheet,'CN

-1 79-1122 . ¹1.2 Plant From Hot Shutdown to Stead Load'CN 79-1681.

79-ii23 &-7 Ali nment and 0 ration of the Reactor Vessel Ove ressure Protect>on S stem, PCN 79-i124 "4-i'eactor Control and Protection S stem'CN 79-1701. 79-1125 ~-5.10 Process Instrumentation Reactor Protection Channel Tri Test e 19-1126 ~-8 Li id Radwaste Com ositin and Anal sis PCN 79-1694. 79-1127 "-RSSP-i.4; Valve Interlock Verification - Reactor Coolant S stem PCN 79-ii28 %SSP=iS.i2 H dro Test of Class 'B Pi in tA and B Steam Generator Fee ater Pz m PCN
PAGE 101 PORC iTEti PROCURE 79-1129 S-13A; RHR S stem Lineu for Safe Injection PCN 79-1686. S-16A Safe Injection S stem Ali nt,'CN 79-1690. S-30.1; Safe Injection S stem Valve Position Verification PCN S-30.2 BHR 'SYstem Valve Position Verification PCN 79-1680. S-30.3; Containment S ra S stem Valve Position Verification PCN S-30.4; Auxil'eedwater S stem Valve Position Verification,'CN S-30.5'tandb Auxili Feedwater Pum Valve Position era. z.cation 79-1130 e3C-3.3.2 Offsite Notificstion of Fire'CN 79-1655. 79-1140 CM-248 Pressurizer Pressure Controller (PC-431K); PCN 79-1719. 79-114l ~ 79-1837.1 Com uter Room Ceilin PCN 79-1712. 79-1144 %-30.4; Auxilia Feedwater S stem Valve Position Verification' 79-1145 Mf 78-1875.2 'A Feedwater Venturi Monorail Installation of Hoist'9-1146 WP-2.4.0 Pod Position Indication S stem 'Part Len th Bank Hot t own A x nt,
n PAGE 102 PORC IT&f d PROCES% 79-1147 ~-2.4.1, Rod Position indication S stem 'Tart Len th" Bank at Power Ali ent PCN 79-1 35. 79-1148 SM 75-5.38, Standb Auxili Feedwater S stem 0 erational Testin PCN SM 75-5.39 Standb Auxil'eedwatei S stem Rework'CN 79-1729. SM 75-5.41, Standb Auxili Feedwater Cable and Conduit Instal-ation Rewor , PCN SM 75-5.42 Electiical Installation and Cable Ter'mination Rework ox Air Han in Units, PW SM 75-5.43; Rework of Standb Auxili Feedwater S stem, PCN SM 75-5.44, Rework of SABA Seal Pi in PCN 79-1725. SM 75-10.28 Service Water Pi Bui in A iation Rewo i to Aii Handlin Units for Aux-SM 75-34.23 Pi e Restraints and Jet Shields Rework for Steam Generator B ow own Lines PCN 7 -1 SM 77-1660.50, RCS Ove ressurization. Protection S stem Annuncia-tion PCN 79-1152 +A-52.1 Shift Or anizati.on Relief and Turnover PCN 79-1713. 79-1193 +A-102.14 Ginna erator Re lification Pro ram PCN 79-1757. 79-1154 +A-1401 Ginna Station Holden Rules PCN 79-1235.
PAGE 103 PORC ITEN /P PROCEDURE 79-1156 CP-2.3 Rod Positi.on Indication S stan Shutdown Bank Hot Shutdown Ali nment PCN-1 6. CP-2.3.1; Rod Position Indication S stem Shutdown Bank at Power A x nt PCN CP-2.5.0,'od Position Indication S stem A Bank Hot Shutdown nt CP-2.5.1, Rod Position Indication S stem A Bink at Power Ali nt'CN

-17 CP-2.6.0, Rod Positi.on Indication S st'em B Bank Hot Shutdown Az nt CP-2.6.1, Rod Position Indication S stem B Bank at Power Ali nt, CP-2.7.0, Rod Position Indi.cation S stem C Bank Hot Shutdown Ali nt PCN CP-2.7.1; Rod Position Indication S stem C Bank at Power Ali nment' CP-2.8.0 Rod Position Indication S stem D Bank Hot Shutdown Ax nt P CP-2.8.1; Rod Position Indication S stem D Bank at Power Ali nt'P-2.9 Rod Position Indication S stem AC to DC Correlation Check

PAGE 104 PORC ITEM fP 79-1157 E-l.l Safe Injection S stem Actuation PCN 79-1702. E-l.3 Steam Line Bieak Accident PCN 79-1733. 79-1158 HP-1.1; Issu'ersonnel Dosimeters PCN 79-1710. HP-1.2 External sure Lucio.ts PCN 79-1769. 79-ii59 :tP-9.3 Air Ejector Gas S lin PCN 79-1752. 79-1160 %-1.2 Plant from Hot Shutdown to Stead Load, PCN 79-1768. 79-ii6i 2.2, Plant Shutdown from Hot Shutdown to Cold Shutdown PCN 79-1162 ~-2.3 Safe d Valve 0 erations PCN 79-i73i. 79-ll63 ~-2.4; Cold/Re&iel Motor 0 crated Valve Surveillance PCN 79-1166 aPZ-2.7; Sets1ce 'Hater S stan, PCN 79-1715. 79-1165 ~-4, RHR Loo Annual H dro Test of Low Pressure Pi in PCN 79-1166 PT-5.10 Process Instrumentation Reactor Protection Channel Tri est PT-5.20 Process Instrumentation Reactor Protection Channel Tri Test Channel PCN 9- 7
PAGE 105 PORC ITEN PROCEDURE PT-5.30 Process Instrumentation Reactor Protection Channel Tri Test C e PCN PZ-S.40, Process Iristriimentation Reactor Protection Channel Tri Test C e PCN s - an 79-i167 PT-23.9A Containment Isolation Valve Leak Rite Testin "A" RCP Sea Water me PCN PT-23.9B'ontainment Isolation Valve Leak Rate Testin "B" RCP Sea Water Lane, PCN 79-1168 %D-7 Li 'd Waste Release,'PCN 79-1708. 79-1169 'AT-36.1 Station Service Water - Header Valve Al nment for Two Loo 0 rat>on PCN 79-1181 A-47; Record and Document Retention'CN 79-1770. M-37.32, Re ack~ of Accumulator Motor 0 crated Dischar e

o Valves'9-1182 >AR/G-30; Steam Gerii rator Lo Level Siri le Channel Alert'CN 79-1183 CP-2.10 RPT. S stem Maintenarice Calibration Check PCN 79-1765.

CP-2.20.1; Calibration of Pulse to Analo Convertor Pover Su 1 CP-2.20.2 Calibration Ali nt of Pulse to Analo Convertor Bank PCN
PAGE 106 PORC ITEM 8 PROCEDURE CP-2.20.4," Calibration Ali nt of Pulse to Anglo Convertor Hank PVil 7 -1 CP-2.20.5; Calibration Ali nment of Pulse to Anglo Convertor Bank CP-ll.l Pressurizer Pressurer Contioiier PC-431K PCN 79-1772. CP-11.2 Pressurizer Re eater PM-431G PCN 79-1773. CP-Ii.3 Pressurizer S ra Conti..oIler PC-491C PCN 79-1775. CP-ii.4, Piessurizer S ra Re eater PM-431A PCN 79-1774. CP-11.5; Piessurizer S ra Contioller PC-431H PCN 79-1776. CP-11.6 Pressurizer S ra Re eater PN-43IB PCN 79-1777. CP-11.7 Bistable PC-431D/E PCN 79-1778. CP'-II.8 Pressurizer Bistable PC-431B PCN 79-1779. CP-11.9 Bistable PC-430B PCN 79-1780. CP-ii.10 Bistable PC-430C'CN 79-1781'. CP-ll.ll Bistable LC-428B)C PCN 79-1782. CP-ii:i2 Bistabie LC-428D PCN 79-1783.
PAGE 107 PORC ITEM PROC@ERE CP-11.13, Bistable LC-427B/D PCN 79-1784. 79-1184 KP-10.5," Delta Flux Coritroller QL (TC-401R) PCN 79-1759-79-1185 %-16.1, Hi Activi - Radiation Monitoiin S stem PCN 79-1788. 79-1186 s89-3.1 8 sure Re orts to Individuals snd tlie NRC 'PCN 79-1771. 79-1187 %P-4.3 Work Permit Use PCN s 79-1798 and 79-1810. 79-1188 %-6.2 Mairi Control Board S stem Status Vera.fication', PCN 79-1769. 79-1189 ~-2.9.2, Accumulator Dischar e Check Valves Quarterl Exercisin PCN 79-1 b. 79-1190 "PT-3; Containment S ia and NaOH Additive S stem PCN 79-1191 ~-17.2 Process Radiation Moriitors R-11 thrii R-21 arid Iodine Mons.tors R- A an R- B PCN 79-1193 "-S-30.1, Safe In'ection S stem Valve Position Verification PCN 79-1194 "SC-1.12A'mmediate Call List'CN 79-1797. 79-1201 -A-17 Plant 0 erati.ons Review Committee 0 ratin Procedure PCN 79-1202 '%-13el Powei Ran e NIS Malfunction PCN 79-1813. 79-1203 CS-18.0 Trainin and Qual'n of Guards PCN 79-1807'.
PAGE 108 PORC ITEM 79-1204 ~-169, Valve HCV-109 Isol.ation Ins ection and Maintenance PCN 79-1205 ~A-7.2 Invento of the First Aid Emei enc Kit Hos ital Radiation Kit Hos ita Ra iation E ment PCN 79-1206 +A-705,=Control of Purchased Services'CN 79-1815. 79-1207 CP-20.1 Defeat of Delta Flux Si al Channel 2 PCN 79-1791. CP-30.1 Defeat of Delta Flux Si al Channel 3, PCN 79-1793. CP-63.3.1 General Defeat Procedure '3-'3'uto Sto Pressure PCN CP-63.4.1 General Defeat Procedure "63-4'uto Sto Pressure PCN CP-63.5.0 Calibration arid/or Mainteriance of 63-5'uto Sto Pies-sure e t CP-63.5.1 General Defeat Procedure "63-5" Auto Sto Pressure PQV CP-102.1 Defeat of Boric Acid Tank Level Channel "102" PCN CP-102.2 Reinstate of Boric Acid Tank Level Channel "102" PCN CP-'103.1 Boric Acid Tank Tem erature Controller, PCN 79-1821.
PAGE 109 PROCEDURE CP-103.2 Boric Acid Tank Tem erature Controller Alarms PCN .CP-ipse:i Boric Acid Tank T erature Indicator TI-104 PCN CP-105.1, Bori.c Acid Tank T rature Zndicator TX-105 PCN CP-106.1 Defeat of Boric Aci.d Tank Level Chanriel "106" PCN CP-106.2'einstate of Boric Acid Tank Level Channel "106",'CN CP-107.1 Boric Acid Tank Te xature Coritioller PCN 79-1833. CP-lp7.2 Boric Acid Tank Tem erature Contr'plier Alaxms PCN CP-110.1 General Defeat Procedure for Boiic Acid Contiol Flow C e CP-ill. 1 " General

" Defeat Procedure Reactoi Makeu Water Flow e PCN KP-30.0; Calibrati.on and/or Maintenance of Delta Flux Controllers C e , PCN CP-40.1 Defeat of Delta Flux Si nal Channel 4 PCN 79-1794.

CP-40.2 Reinstate of Delta Flux Si nal Channel 4'CN 79-1795.
PAGE 110 PORC ITEN 79-1210 CP-102.9 Boiic Aci.d Tank Level Nitro en Bubbler Su 1 Pressure Switch PS-1 PCN 7 -1 3 ~ CP-102.10'oric Acid Tank Level Nitro en Header Pressure Switch P CP-106;9, Boric Acid Tank Level Nz.tro en Bubbler Su 1 Piessure Sm.tc P-CP-106.10 Boric Acid Tank Level Nitro en Header Pressure Switch PAS- , PCN 79-1211 M-10", Mal&iriotion Rod'Poai.tion Iridzcatot, PCN 79-1760. . 79-1212 E-26.1 Bier en Shutdown Resultin from a Reactoi Tri From 8.57. Power or Less PCN E-26.2 Emer eri Shutdown Result'rom a Reactor Tri When Between . an ~ . ower S GI1 E-26.4; Turbine Tri without Reactor Tri PCN 79-184l. 79-1213 M-26.3, Emer enc Shutdown Resultin Fiom a Reactor Tri When 0 ratin at Greater Than 50 . Power, PCN 79-1840. 79-1215 CS-i.2 Securi Event Re ort PCN 79-1806; 79-1216 CS-24.0 Securi Surveillance Re irements and Procedures PCN 79-1217 %P-1.3 External E osure Records PCN 79-1828. 79-1218 <M-12.1 Usa e of Res irators PCN 79-1809.
PAGE ill PORC ITEM 1f 79-1222 KC-3.15.15; Emer en

-1 Fire E i ment Locker Invento and Ins ection, PCN 1 79-1223 "-T-27.1; lA Emer eric Diesel Generator Pie-Start Ali nt'CN 79-1224 %-26.2, 1B Emer en Diesel Generator Pre-Start Ali nment PCN 79-1236 %-3; Precautions Limi.tations and Set ints P-3 Chemi.cal and Vo ume Contro S stem PCN 79-1237 %-16.16; Safe Injection Pum Isolation'CN 79-1847.

79-1238 +AR/AA-21, Auxili Feedwater Defeat Switch PCN 79-1808. 79-1239 ~A-1.6, ALARA Committee 0 eratin Procedure, PCN 79-1866. I 79-1240 +A-1.6.1, Documentation of "As Low As Reasonabl Achievable" (ALARA) Pro ram, PCN 79-1241 +A-7.2,'nvento of First Aid Emer ency Kit Hos ital Radiation Kit os xta Ra z.at>on E z ment, 79-1242 +A-52.4; Control of Limitin Conditions for 0 eratin E i. ment t 79-1243 +A-52.5'ontrol of Limit Conditions foi S stem S eci.fications 79-1244 +A-1602 Preventive Action Re rt" ~i 79-1849.
PAGE 112 PORC IT&f ff 79-1245 CP-110.0'alibration and)or Maintenance of Boric Acid Flow Channel

, PCN CP-110.8, Boric Acid Control Bistable YC-110 PCN 79-1862.

CP-ill:0 Calibration " PCNand/or Maintenance of Reactor Makeu Water F owC e " CP-111.8, Reactor Makeu Water Flow Bistable YC-111, PCN 79-1861. 79-1246 CP-ii2.0, Calibration and/or Maintenance of Volume Contiol Tank eve C e " " PCN CP-112.3, Volume Control Tank Level Transmitter LT-112; PCN 79-1247 CP-112.1; Geneial Defeat Procedure Volume Control Tank Level C e CP-139.1 General Defeat Procedure "139" Volume Control Tank Level e, 79-1248 WP-139.0 Calibration I and/or Maintenance of Volume Control Tink eve ~ ~ ~ 79-1249 M-139.8 Calibration and/or " Maintenance of Volume Control Tank Leve Power Su "LQ- PCN 79-12SO GS-3.0 Securi. Call List PCN 79-1'889. GS-30.0 Threatenin Phone Call or Bomb Threat Procedure PCN
PAGE 113 PORC ITEM ff PROCEDURE 79-1253 4-1.1C, Preciitical Technical S ci.fication Check Sheet PGV 79-1254 PC-l.l Pr Coolant Anal sis Schedule and Limits'CN 79-1864. PC-1.2, Non-Prima Coolant Anal sis Schedule and Limts PCN 79-1255 ePT-13.1.13; Star Co ration Heat Detector S item Test'CN 79-"1'256 ~-2.1'afe In'ection S stem Pum s PCN s 79-1846 and 79-1848. 79-1257 ~-2.8 Com onent Coolin Water S stem PCN 79-1856; 79-1258 %-23.2.2 Containment Pur e Procedure PCN 79-1891. 79-1259 %-30.3; Containment S ra S stem Valve Position Verification, PCN 79-1260 %C-1;8; Post Aces.dent Erivironmental Sam lin PCN 79-1893. 79-1261 KC-1.7C Monitorin Site Radiation Level b TLD PCN 79-1892. 79-1262 KC-1.15 Ins ection of Emer enc L ment PCN 79-1819. 79-1263 N-44.4, HVAC Lirieu for Standb Auxil'eedwater S stem PCN 79-1272 ES-7.1, Collects Environmental and Post Accident TLD s'CN
I PAGE 114. PORC iTEM y PROCEZRE ES-7;2, Readout of Environmental and Post Accident TLD's PCN RD-13.2, ln estion Doses from Li 'd Releases PCN 79-1854. RD-13.3 Dose Commitment from Gaseous Releases PCN 79-*1855. S-16:i6A iA Safe Injection Isolation Restoration'CN S-16.16B, 1B Safe Injection Isolation Restoration PCN S-16.16C 1C Safe Injection Isolation Restoration PCN 79-1273 EM-174, Emer en Maintenance Procedure - EN 174 - Check Valve Iso ation or ns et~on an amtenance EN-179 Re lacement of CVCS Letdown Vent Valve 2234 PCN 79-1916. EM- 8; R Dragon Va ve air o E W PCN ld o "" Char in Pum 'ar Lin to RYI-194, Re air of CVCS Han er CH54, ~i 79-1896. EM-197 Re air of Weld on "B" Char m Dz.schar e Line to Re ie ave EN-198 Re lacemerit of the Buchanan Terminal Blocks for Pressurizer Pressure an Leve Transmitters Termnatzons Lh.t a Western ouse S e No. TermLna B o PQV
PAGE 115 PORC iTEH* '/I PROCEDURE EH-202, Safe Injection Se ence Timin Rela Re lacement PCN EH-205, Turbine Runback Rela in RPI S stem Re lacement', PCN EH-232, Re aii of Feedwater Pi in Inside Containment P&i 79-1901. EH-234, Re air of Feedwater - Steam Generator llozzles'CN 79-1902. EH-237, Weld Re air - Connection at eedwater Line from MDAFWP EH-238; Weld Re air - Connection at 'A'eedwater Line from TDAFWP B&239; Containment S ra Rin Header Pi e Clam Replacement PQl 79-1274 %T-13.1.5 Flood Valve S stem Test S stem k3, 4 5 6; PCN 79-1913. 79-1275 "PZ-12;2, Emer en Diesel Generator 1B; PCN 79-1934. 79-1277 %~ -37.54, Isolation and tIaintenance of Letdown Orifice Valves A, B an PCN 79-1278 Wa -48.4, Isolation of Bus 16 PCiii 79-1921. 79-1281 +A-35 Pxime Mover Iioldi and Maiku Re rements PCN 79-1924. 79-1282 +A-53.1, E 'ent Ins ection Peiiod and Lubricant List,'CN
PAGE 116 PORC ITEM PROCEDURE 79-1283 A-301, Control of Station Hodi'fications PCN 79-1940. A-304, Pre aration, Review and A royal of Desi n Out ut Documents or d'or M x scat'.ons, 79-1284 A-1001'ns ectiori and Surveillance Activities PCN 79-1935. 79-1285 "GS-5.0, Securit Guard General Instructions'CN 79-1925. 79-1286 "GS-8.0 Detex Tours 8 Securit Guaids PCN 79-1949. 79-1287 "GS-9.0'alkie Talkie Procedure for the Securi Force PCN

-1 5 79-1288 '%S-18.1 Conduct of Qn-The-Job Trainin of Guards PCN 79-1951.

79-1289 "GS-19.0 Issuance of Electronic Card Ke s,'CN 79-1946. 79-1290 GS-21.2'noccu ied Vital Area Access Control PCN 79-1907. 79-1291 NS-26.0 Securi Ke and Lock Controls, PCN 79-1947. 79-1292 CS-32.0 Cia.l Disturbance Procedure'CN 79-1945. 79-1293 'CS-33.1, Use of Rifles and Shot s PCN 79-1942. 79-1294 KS-34.0'ital Areas PCN 79-1944. 79-1295 WS-35.0 Issuin and Destruction of Ginna Photo Identification ar s
PAGE 117 PORC ITEM ik PROCEXSRE 79-1296 WS-39.0; Protected/Vital Area Access PCN 79-1943. 79-1297 +1-11.5K Turbine Driven Auxili Feedwatei Pum Major or Mec ica ns ection, PCN 79-1298 %-48.2; Isolation of Bus 14, PCN 79-1922. 79-1299 O-l.l, Plant Heatu from Cold Shutdown to Hot Shutdown P& 7 -1 0-6.2; Main Control Board S stem Status Verification *PCN 79-1300 &C-1.3; Dail Chemical Anal sis Results PCN 79-1938. 79-1301 -"PT-2.5.2, Air 0 crated Valves Quarterl Surveillarice (Valves 112B an C PCN 79-1302 'PT-'5.'1'0, Process Instrumentation Reactor Protection Channel Tri Test C e , CN PT-5.20'rocess Instrumentation Reactor Protection Channel Tri Test C e , N PT-5.30 Process Instrumentation Reactor Protection Channel Tri

'lest ne 79-1303 %D-4 Vent Radio as Back round and Factor Determination PCN 79-1305 S-ll'atchin Tank'CN 79-1933'.

PAGE 118 PORC PROCEDURE S-ll.l, Boric Acid Stora e Tank Transfer to Batch Tank, PCN 7 -l 79-1306 "6-30.5, Standb Auxilia Feedwater Pum Valve Position Vera icatxon, PCN 79-1307 '%C-1.7B Determination of Iodine or Particulate, PCN 79-1926. 79-1308 SC-1.7D; Emir enc Radiation Monitorin~ Off-Site Surve Team t/9D Re , PCN SC-1.7E, Emer enc Radiation *Monitorin On-Site S~~e~ Team 69E B ue, PCN SC-1.7F, Emer enc Radiation tfonitorinp Off-Site Surve Team //9F Green, PCN SC-1.7G,'mer enc Radi.ation Monitorin On-Site Surve Team //9G Ye ow, PCVi SC-1.7H, Emer enc Radiation Monitorin Off-Site Surve Team /39H Oran e PC',Vi 79-1310 "-T-&.2'tandb Auxilia Feedwater (SAMAJ) S stem Ali nment for Viorma 0 eratxon P i 79-1319 E-l.l Safet Injection S stem Actuation, PQl 79-2014. E-1.2, Loss of Coolant Accident PCN 79-2013. E-1.3; Steam Line Break Accident, PCiV 79-2012.
PAGE 119 PORC ITB1 E-1.4, Steam Generator Tube Rupture Accident PCN 79-2011. E-l.5,'oid Formati.on in the Reactor Coolant S stem PCN 79-2015. 79-1322 "B-48.1, Isolation and Restorat'on of Bus //13 PCN 79-2017.

%f-48.3, Isolatiori and Restoration of Bus //15,'CN 79-2018.

79-1323 -A-52.1, Shift Or anization Relief and Turnover, PCN 79-2079. 79-1324 +AR-D-4, Pressurizer Hi h Level; PCN 79-2063. 79-1325 -A-502; Plant Procedure Content and Format Re uirements PCN -1 79-1326 -"P-1; Peactor Control and Protection S stem, PCN 79-2064. 79-1327 >A-1002, Qialification of Surveillance and Ins ection Personne, P 'N 79-1328 "%1 -76.1; Installation and Test Sam lin of Groutin PCiiJ 79-1329 aST-2 A .1 Cold/Refuelin Motor 0 grated Valve Surveillance RFR S stem - Va ves 79-1330 PZ-2.9; Check. Valve Eiercisino Quarterl Pe uirement, 79-1331 >PT-5.20'iocess Instrumentation Reactor Protection Channel rz. est, C e
PAGE 120 I~PORC

/f PROCEDURE 79-1332 "PZ-6.1; Source Ran~e nuclear Instrumentation S stem, PCiit /

79-1333 SC-1.7E, Emer enc Radiation Monitorin On-Site Su>we Team f/E Bue, P&i SC-1.7G, Emer,enc Radiation t fonitorin On-Site Surve Team I Ye ov P i SC-1.7D, Emer enc Radiation Honitoii Off-Site Surve Team 0 Re SC-1.7F, Emer enc Radiation Monitori Off-Site Surve Team I/ F Gxeen PQl SC-1.7H, Emer enc Radiation Monitoiin Off-Site Surve Team t H Oran e Peril 79-1334 "'SC-1.78, Detexnii.nation of Iodine or Particulate, P&i 79-1926. 79-1335 SC-3.15.16; Fire Protection S stem Ins ections PCN

%-16.16; Safet Injection Pump Isolation, PCi< 79-1860.

79-1337 PZ-24.1; S ent Fuel Pit Charcoal Filter 8 -Pass Flow', PCiil PT-5.10, Process Instxumentation Reactor Protection C nne Trz. Test C anne , PCiil PT-2.8,'om nent Coolino Uater Pum S stem PCiit 79-2075.
PAGE 121 PORC ITEM PROC')URE 79-1338 GS-45.0; Vital Area Securi Surveillance PCiN 79-1908. GS-46.0, Electronic Ke card S stem Testin Procedures, ISI-10; Ins ection of Sta ant 0 enated Borated S stems PCiN M-37.62, Check Valve 7226 Ins ection and Maintenance, PCN 0-6.13 Dail Surveillance Lo P&i 79-1817. 79-1346 Mf-249,'erlval of the Tem ora Shield Wall Around The Re e ~ Hater Stora e Ta , PCiit 79-1347 MI-250'WST Su orts - Sam le Removal'i 79-2128. 79-1348 %-6.14, iHonthl Surveillance Schedule, PCiN 79-2003. XC-3.l5.17; Technical S ecification Firevatch Postin PCiN 79-1929. 79-1349 -A-1105 Calibration Surveillance Pro ram for Instrumentation/E ui-ment o Sa et Re ate om onents C 79-1350 "-EH-250'UST Su orts -'am le Removal, PCN 79-2129. 79-1351 %P-7.8; Ala 'osimeter Accura Test, PCN 79-2076. 79-1352 ~-11.2 Iodine In Air - Charcoal Cartridpe Method PCNi 79-2082. 79-1353 "-K?-12.1; Usa e of Res irators PCN 79-2080.
PAGE 122 PORC ITAL i/ 79-1354 %P-12.7, Constant Flow Breathin Air S stem Set U, PCN 79-2081. 79-1355 "PT-2.7, Service Mater S stem, PCN 79-2130. 79-1356 -PT-13.1.12, Containment Post-Accident (Recirc.) and/or Auxilia Fz. ter RTD Teston , PCN 79-1357 'M-36, Standb Auxilia Feedvater Pum s Flow Test PCN 79-2127. 79-1358 99-8'i id Radwaste Com ositin and Anal sis PCN 79-2077. 79-1359 -S-4.4, S ent Resin Removal to Shi in Casks, PCN 79-2103. 79-1360 6-5 0 eratin Instruction S-5,'uclear S stem, PCN Sam le Room Sam li 79-1361 PCN's -'n

>8-30.4, Auxilia Feed~rater S stem Valve Position Verification, 79-1373 >%T-27.1; Tendon Ins ection and Lift Off Verification, PCN 79-1374 7'~4f-82.1," De reasin of Containment Tendon Canisters, PCN 79-1376 MP-428.9; Pressurizer Level Recorder LR-428; PCN 79-2176.

79-1377 -4; Vent Radio as Back round and Factor Determination PCN 79-l378 &-6.13 Dail Surveillance Lo ', PCN 79-2183.
PAGE 123 PORC ITEM PROCEDURE 79-1379 '6-6.2; Hain Control Board S stem Status Verification PCN 79-1380 HP-7.12; PIC-6A 0 eration and Calibration, PCN 79-1957. HP-7.13," RO-1 (Rad Owl) 0 eiation and Calibration PCN 79-1956. H-82.2'ontainment Tendon Greasin , PCN 79-2162. PR-10.1, ITE Circuit Shield Undervolta e Rela Acce tance Test PCN 79-1383 <<A-52.4, Control PCN of Limitin Conditions for 0 cretin E i ment 79-1384 <A-1601 Coirective Action Re ort'CN 79-2156. 79-1385 CP-128.0; Calibration and/or Maintenance of Char in Line Flow

,PL CP-420.4, Reactor Coolant Pressure Indicator PI-420 and Pecorder PR- , PCN 79-1386 CP-139.3, Uolu~ Control Tank Level Transmitter LT-139 PCN CP-172.3'oric Acid Tank Level Transmitter LT-172 PCN 79-1964.

79-1387 KP-128.3, Char in Line Flow Transmitter FZ-128 and Local Indicator FI A, PCN 79-1388 "CP-171 .3'oric Acid Tank Level Transmitter LT-171, PCN 79-1968.
PAGE 124 PORC ITEtf PROCEDURE 79-1389 ""CP-171.7, Boric Acid Tank Level Indicator LT-171A, PCN 79-1960. 79-1390 CP-171.9; Boric Acid Tank Level Nitrogen Bubbler Su 1 Pressure Sm.tc PS-, FCN CP-172.9, Boric Acid Tank Level Nitro en Bubbler Su 1 Pressure Swx.tc PS- , PCN 79-1391 CP-171.1, Defeat of Boric Acid Tank Level Channel "171" PCN CP-172.1; Defeat of Boric Acid Tank Level Channel "172" PCN CP-172.2'einstate of Boric Acid Tank Level Channel "172" PCN 79-1392 CP-171.5, Boric Acid Tank Level Bistable LC-171A/B PCN 79-1969. CP-171.6; Boric Acid Tank Level Bistable LC-171C, PCN 79-1970. CP-172.5; Boric Acid Tank Level Bistable LC-172A/B PCN 79-1965. CP-172.6, Boric Acid Tank Level Bistable LC-172C PCN 79-1961. CP-250.0; Calibration and/or Maintenance of Ginna Station Neteoro o ica Instrumentatxon, P i 79-1393 KP-250.6, Calibration and/or maintenance of Mind S eed Volta e Sz. na Con z.tioner PCN 79-1394 "CP-401.2, Reinstate T AVG Si nal for Channel "1", PCN 79-1975.
'I PAGE 125 PORC Imf // PROCEDURE 79-1395 KP-401.6; T AVG Bistable TC-401A Peril 79-1976. 79-1396 "CP-401.9, T AVG Indicator TI-401; PCN 79-1974. 79-1397 CP-171.0 Calibration arid/or Maintenance of Boric Acid Tank Level C el PCN 9-CP-172.0 Calibiation and/or Maintenance of Boric Acid Tank Leve C nne " ", PCN CP-420.0 Calibration andjor Maintenance of Reactor Coolant essure C e PCN 79-1398 XP-428.4 Pressurizer Level Pointer Su 1 LQ-428 PCN 5 79-1399 "CP-428.7; Pressurizer Level Re eater 1M-4288 PCN 79-1400 >'CP-428.9'iessuri.zer Level Recorder LR-428, PCN 79-1401 0-1.1, Plant Heatu From Cold Shutdown to Hot S ut own PCN 0-1.2; Plant From Hot Shutdown to Stead Load, PCN 0-2.1 Normal Shutdown to Hot Shutdown'CN 79-2186. 79-1402 %7-2.8; Com onent Coolin Water Pum S stem PCN
PAGE 126 PORC ITEM 79-1403 "S-12.2; 0 erator Action in the Event of Indication at Si nificant Increase m Le a e PCN 7

='SC-3.2.9'mmediate Action - Containment Vessel Fire -'9-1404 PCN 79-2154.

79-1416 ~6M 77-1850.1 Fire Barrier Penetration Seals Installation PCN 79-1417 "6-37.50; MOU-721 RHR to "B" Loo Maintenance and Ins ection, PCN 79-1418 "S-4.2.5," 0 eratin Instruction S-4.2.5, Release of Gas Deca Tank PCN 79-1419 HP-7.10; Area Monitor Calibration Ezergeri Center'CN 79-1959. HP-7.11 Teletectoi 0 eration and Calibration PCN 79-1958. HP-7.14; RD-2A 0 eration and Calibration, PCN 79-1955. HP-7.15; XETEX 302A Hi h Level Probe 0 eration and Calibration CN HP-7.16; XEZEX 302B Hi. h Level Probe 0 eration and Calibration, RD-13, Offsite Dose Calculation Manual PCN 79-2179. 79-1421 <A-l, Radiation Control Manual, PCN's 79-1804 and 79-1914. 79-1422 CP-5.0; Calibration Ali nment of T A . and Delta T at Zero Pover Channe Loo A, Un' PCN
PAGE 127 PORC ITEM CP-5.10; T A . and Delta T Ali nment at 70% Power or Greater Loo A Un'CN CP-6.0; Calibration Ali nment of T Av,. and Delta T at Zero Power C anne oo nz.t CP-6.10; T A . and Delta T Ali. nment at 70% Power or Greater Loo A, Unxt PCN CP-7.0'alibration Ali nment of T Av . and Delta T at Zero Power C anne Loo B, Unit PCN CP-7.10; T Av . and Delta T Ali,nment at 70/ Power or Greater Loo B nest P i CP-8.0," Calibration Ali nment of T Av . and Delta T at Zero Power C e P i CP-8.10, T Avp. arid Delta T B Un at PCN Ali nment it 70% Power or Greater Loo CP-31.3; Calibration of Source Ran e N-31 PCN 79-2029. 79-1423 CP-12.0, Rod Insertion Limit and Delta T Reactor Control Rack, PCN CP-12.19,'od Insertion Limit Medium Current Selector 1%-405X, PCN CP-12.22; Rod Insertion Limit Com uter Unit Ti~f-405J PCN 79-2027. CP-422.0, Calibration and/or tIaintenance of Pressurizer S ra Line Tem erature A Loo PCN
PAGE 128 PORC ITEM PROCEDURE CP-423.0; Calibration and/oi Maintenance of Pressurizer S ra Line Tem erature B Loo PCN CP-423.3; Calibration and/or Maintenance of Pressurizer S ra Line Tem rature In xcator PCN CP-424.0 Calibration and/or Maintenance of Piessurmer Li id Tem erature PCN CP-425.0 Calibiation and/or Maintenance of Pressurizer Va or Tem erature TE- , CN CP-429.1, General Defeat Procedure Pressurizer Channel 429 PCN CP-931.0 Calibiation and/or Maintenance of S ra Additive Tank Leve C e PCN CP-931A'alibration of RHR Refuelin Water Return Line Flow Transno.tters an ssocxate n icators CP-931B'alibration of RHR Refuelin Water Peturn Line Flow Trans'.tters an Assoc~ate In icators PM 79-1424 CP-31.1 Geneia1. Defeat Procedure for N-31'CN 79-2036. CP-32.1 General Defeat Procedure for N-32 PCN 79-2031. CP-421.1 Calibration and/or Maintenance Pressurizer S e Line Tem rature R I Converter TM- PCN CP-421.2, Pxessurizer Sur e Line Tem erature Bistable TC-421
I II'
PAGE 129 PORC ITEM PROCEDURE CP-423.1, Calibration and1or Maintenance of Pressurizex S ra Line Te erature R I Converter PCN CP-630.1; RHR Loo Reactor Coolant Inlet T erature R/I Converter TM- , PCN 79-1425 CP-31.4, Calibration of Source R e N-31 Bistable Rela Drivers CP-32.3,'alibration of Source Ran e N-32 PCN 79-2028. CP-32.4; Calibration of Source Ran e N-32 Bistable Rela Drivers FCN CP-424.2 Calibiation and)or Maintenance of Pressurizer Li id Tem erature Basta e TC- , s - an 79-1426 "CP-35.0; Iritermediate Ran e N-35 Calibration and/or Maintenance, K5 79-1427 CP-420.1; Reactor Coolant Pressure Poier Su 1 PQ-420 PCN CP-428.0; Calibration and/or Maintenance

" " of Pressurizer Level C nne CN CP-924.0'alibration and/or Maintenance of Safe Injection Flow Loo B P c CP-925.0 Calibration and/or Maintenance of Safet In'ection Plow Loo A P i 79-1428 WP-420.2; Reactor Coolant Piessure Tiansmitter PT-420 PCN 79-1998.

I PAGE 130 PORC iTEN I/ 79-1429 ~-42l.'3,'alibration and/or tfaintenance of Pressurizer Sur e Line Tem erature In locator TI- PCN 79-1430 CP-422.2; Calibration and/or Maintenance of Pressurizer S ra Line Tem erature Basta e TC- , PCN CP-422.3, Calibration'nd/or Maintenance of Pressurizer S ra Line Tem rature In z.cator TI- , PCN CP-423.2; Calibrati.on and/or Maintenance of Pressurizer S ra Line Tem erature Basta e TC- , PCN 79-1431 CP-426.0, Calibratio~ and/or Maintenance of "426" Pressuiizei Level Channe PCi$ CP-427.0, Calibration and/or 1"iaintenance of Pressurizer Level C e i CP-428.0; Calibration and/or Maintenance of Pressuxizer Level C e PCif 79-1432 CP-426.0; Calibration and/or Maintenance "426" Pressurizer Level C e , PCN CP-427.0 Calibration and/or Maintenance of Pressurizer-Level C e , PCN CP-428.0, Calibration and/or Maintenance of Pressurizer Level C e P i 79-1433 ~-429.2 Geneial Reinstate Procedure Pressurizer Channel 429'CN
I, PAGE 131 PORC ITEM 79-1434 CP-429.11'ressurizer Pressure Re eater PM-429C PCN 79-2053. 79-1435 CP-464.10 Steam Flow Indicator FI-464'i. 79-2049. CP-466.9, Feedwater Flow Indicator FI-466 PCN 79-2048. 79-1436 ~-467.10 Feedwater Flow Recorder FR-465 PCN 79-2047. 79-1437 CP-478.2, Reinstate of "8" Steam Generator Pressure Channel "478" PCN CP-482.2; General Reinstate of "A" Steam Generator Pressure Channel PCN 79-1438 CP-482.0, Calibiation and/or Maintenance of Steam Generator Pressure e CP-483.0 Calibration and /or Maintenance of Steam Generator Pressure e 79-1439 'CP-924.1 Calibratiori and/or Maintenance of Safet In'ection Flow Loo A Transao.tter FZ- P 79-1440 E-4.1, Safe d Buses Low Volta e Condition PCN 79-2191. E-4.2 RGK Low S stem Fre enc Condition, PCN 79-2192. E-6.1; Loss of ComDonent*Coolin Durin~ Power 0 eration PCN E-6.2; Loss of Com nent Coolin While Plant is Shutdown, PCN
PAGE 132 PORC ITEM PROCEDURE E-6.3, Loss of Com onent Cool Durin Recirculation Phase of Acct ent, PCN E-14 Hi h Reactor Coolant Activit PCN 79-2198. E-17.1 Reactor Coolant Drain Tank Pum 0 eration for Core Coolin E-38.1; 0 erator Actions to be Taken in the Event of a Loss of the Se~ce Water Return me tsar. e t e Aux'. z.a Bus xn PCN 79-1441 %P-4.3, Work Permit Use PQ1 79-2249. 79-1442 MSI-1.2.1; Qualit Grou A Insexvice Ins ection PCN 79-2195. 79-1443 ~<-40.8 Functional Testiri of H draulic Snubbers, PCN 79-2246. 79-1444 0-1.1C, Precritical Technical S cification Check Sheet PCN 79- 31. 0-1.1D Pre-heatu Plant Re uirement Check List'CN 79-2230. 79-1445 "6-6.7 Weekl Alarm Status Check P&l 79-2252. 79-1446 "-PZ 2.1 Safet Injection S stem s PCN 79-2181. 79-1448 ""S-3.6, AUX3.1i Buildin Heat Tiacin S stem 0 eiation PCN 79-1449 %-12.4 RCS Le@m e Surveillance Record Instructions PCN 79-2196.
PAGE 133 PORC ITEN PROCEDURE 79-1450 "T-41A, Ali. nment of Amrili Peedwater S stem Prior to Power 0 ration PCN 79-1461 ~-2Sl, Rock Anchor Cou lin Enclosure Broken Bolt Re air, PCiil 79-1464 "A-102.10, Health Ph sics Trainin and Res onsibili L~ts P 79-1465 NS-26.0'ecuri. Ke and Lock Controls, PCN 79-2285. 79-1466 -'ISI-2.1.6A;, Quali Grou B Inservice Ins ection PCS 79-1467 'S-3.4P Boron Rec cle Process Shutdown PCN 79-2304. 79-1468 CP-426.5; Pressurizei Level Bistable LC-426 A/B PCN CP-428.5; Pressurizer Levef Bistable LC-428 A/E'CN 79-2068. CP-427.5 Pressurizer Level Bistable LC-427 A/C'CN 79-2066. 79-1469 CP-406;2 Reinstate Delta T Si nal for Channel 2; PCiil 79-2106. CP-407.2; Reinstate Delta T Si nal for Channel 3'CN 79-Zi07. CP-408.2; Reinstate Delta T Si nal for Channel 4, ~ 79-2108. CP-134.1; Letdown Line Plow Transmitter FZ-134; PCN 79-2109.
PAGE 134 PORC ITEM PROCEXJRE CP-134.2, Letdown Line Flow Power Su 1 FQ-134 PCN 79-2110. CP-134.3, Letdown Line Flow S e Root Converter FH-134, CP-134.4, Letdown Line Flow Bistable FC-134 PWi 79-2112. CP-134.5 Letdown Line Flow Indicator FI-134 PCN 79-2113. CP-405.2 Reinstate Delta T Si nal for Channel 1,'CN 79-CP-405.20.1 Defeat of Delta T Set oint 2, Channel 1 PCN CP-408.20.1; Defeat of Delta T Set int 2, Channel 4 PCN CP-406.20.1 Defeat of Delta T Set int 2 Channel 2 PCN CP-408.10.1', Defeat of Delta T Set oint 1, Channel 4 PCN 79-1470 CP-42.1 General Defeat Procedure For N-2 PCN 79-2095. CP-43.1; General Defeat Piocedure for N-43 PCN 79-2096. CP-44.1 General Defeat Piocedure for N-44 PCN 79-2097. CP-41.1 General Defeat Procedure for N-41 PCN 79-2098.
PAGE 135 PORC ITEM CP-41.2 General Reinstate Procedure for N-41'CN 79-2099. CP-42.2; General Reinstate Procedure for N-42 PCN 79-2100. CP-43.2 General Reinstate Procedure for N-43, PCN 79-2101. CP-44.2 Genexal Reinstate Procedure for N-44 ~i 79-2102. CP-404.2, Reinstate T AVG Si nal for Channel "4", PCN 79-CP-403.2; Reinstate T AVG Si nal for Channel "3", PQ4 79-CP-402.2; Reinstate T AVG Si nal for Channel "2", FCN 79-CP-401.5, T AVG (3 SEC) La Unit Tiff - 401 BB; PCN 79-2115. 79-1471 "CP-401.5, T AVG (3 SEC) La Unit TM - 401 BB PCN 79-2115. 79-1472 ~-209.4, Nuclear Measurements Co oration Air Monitor, P 79-1473 CP-406.10 Calibration and/or Maintenance of Delta TSP1 C e P CP-405.10'alibration and/or Maintenance of Delta TSPl C e PCN 79-1474 MP-37.0 Calibration and/or Maintenance of Com arator Drawer
PAGE 136 PORC LITEM iI PROCEDURE 79-1475 CP-401.7 T AVG Re eater Tiff-401C; PCN 79-2116. CP-401.8, T AVG Re eater TH-40lQ; PVil 79-2117. CP-401.6' AVG Bistable TC-40]A PCN 79-2126. CP-406.20.6'elta T Set int 2 Re eater TH-402S, PCN 79-1476 WP-406.ip.'i. Defeat of Delta T Set oint 1; Channel 2, P 79-1477 CP-405.10.1 Defeat of Delta T Set int 1'hannel 1 CP-37.1, Low Volta e Power Su 1 hQ-401 Adjustments'P-406.20.0'alibration and/or Maintenance of Delta 79-1480 ='K-29.3'tandb Auxilia Feedwater Pum 0 eiation, PCN 79-79-1490 'PZ-36; Standb Auxili Feedwater S stem Flow Check'CN 79-2419. 79-1491 -KH-252, Pi e Su port Rework for S stem (Without Anchor Bo t Rework PCN 79-1492 "4M-154, Steam Geneiator Handhole Cover Gasket Leak Re aiz Process, ~i Us'urmanxte
PAGE 137 PORC ITEN PROC EIXEE 79-1493 "'K1-253'e lace Reset Button for Containment Isolation and Ke 0 crate Swz.tc or Uenti ation Iso at>on wz.t a Ke 0 erator Pus Button, PCN 79-1494 ~OP-216.3; Re lacement of %45 Channel R-16 Detector PCN 79-2430. 79-1495 . VC-1.1, Pr'oolant Anal sis Schedule and Limits PCN 79-2416. 79-1499 'CP-113.0, Immediate Boration Flow Channel 113'alibration and/or i amtenance, KP-113.1, Iamedi.ate Boration Ha netic Flow Convertor Bf-113 PCN KP-113.2; Immediate Boration Flow Inte rator YM-113 PCiil 79-2086.

'CP-113.3, Immediate Boration Flow Counter YIC-113'CN 79-2087.

CP-113.4; Immediate Boiation Flow Indicator FI-113 PCN 79-2088.

""SC-3.15.9; Exterior H drant Freeze Protection', PCN 79-2326.

79-1500 'A-25.1'inna Station ~ ;nt Re ort PCN 79-2398. 79-1501 ~A-54.6,'ealth Ph sic's "'" .", PVil 79-2399. 79-1502 , A-1702; Record Stroa e Facilities and E ui ment PCN 79-2382. 79-1503 "~P-10.1, Defeat of Delta Flux Si al Channel 1, PCN 79-2307. 79-1504 "CP-410.1 Reactor Coolant Tem erature, COld Le ," R/I TH-410 ~i
PAGE 138 PORC ITEN /I 79-1505 "-%&246, Furmanite Re air.Pressurizer S ra Valve 431A and B PCN 79-1506 "-HP-1.1; Issnin Personnel Dosimerers'CN 79-2625. 79-1507 -HP-1.6 Nuetron E osure PWi 79-2420. 79-1508 %P-7.9,'000B Gamma Calibratoi 0 eration', PCN 79-2323. 79-1509 -XSI-1.1.9'ualit Grou A Inservice Ins ection PCN 79-2282. 79-1510 ~1-38.l, Diesel Fire Pum Enoine Haintenance and Ins ection PCN 79-1511 &-1.2, Plant from Hot Shutdown to Stead Load PCN 79-2432. 79-1512 '6-2.1'ormal Shutdown to Hot Shutdown'CN 79-2426. 79-1513 -PZ-2.8, Com nent Coolin Mater Pum S stem PCN 79-2400. 79-1514 ~-27.1, Tendon Ins ection arid Lift-offVerification PCN 79-2418. 79-1515 %D-7'i uid Maste Release, PCN 79-2322. 79-1516 %SSP-1.4; Valve Interlock Verifi.cation - Reactor Coolant S stem PCN 79-1517 "-SC-1.3B Emer enc Coordinator Check Li.st, PCN 79-2324. 79-1518 WC-1.4'eneral Radiation Emer en 'CN 79-2391.
PAGE 139 PORC ITEN PROCEDURE 79-1519 "SC-ls13'stimatin Off-Site Doses PCi4 79-2390. 79-1520 "-WC-1, A list of Sam le Chemical Parasmtets aiid S liu Schedule, PCN 79-1529 ~-13.1s14; Fire Barrier Penetration Seals PCN 79-2460. 79-1530 CP-4084.0 "C" Standb Auxili Feedwater Flow PCN 79-2267. CP-4084.'1, Tiansmitter W-4084, PCN 79-2268. CP-4084.2' e Root Extractor IY-4084A PWi 79-2269. CP-4084.3 Re eater FY-4084B and Indicator FI-4084A PCN 79-2270. CP-4084.4, Re eater FY-4084C and Indicator FI-4084B, ~i 79-2271. CP-4084.5'istable FB-4084A and B PCN 79-2272. CP-4084.6'istable FB-4084C PCiN 79-2273. CP-4085.0'D" Standb Auxilia Feedwater Flow PCiN 79-2277. CP-4085.1; Transmitter FZ-4085 PCN 79-2278. CP-4085.2, S uare Root Extractor FY-4085A PCN 79-2279. CP-4085.3 Re eater FY-4085B and Indicator FI-4085A PCN 79-2280. CP-4085.4; Re eater FY-4085C and Indicator FI-4085B PCiN 79-2274.
PAGE 140 PORC ITEYi // PROCEDURE CP-4085.5; Bi.stable PB-4085A and B,'CN 79-2276. CP-4085.6; Bistable FB-4085C'CN 79-2275. 79-1532 +A-1102, lification of Test Personnel'CN 79-2462. 79-1533 +A-1105, Calibration Suxveillance Pro ram ment o Sa e Re ate Com onents PCN for Instrumentation/E i-79-1534 CP-405.0; Calibiation and/oi Maintenance of Delta T Channel 1, PCN CP-406.0; Calibrati.on and/or Maintenance of Delta T Channel 2, CP-407.0; Calibration and/or maintenance of Delta T Channel 3 PCN CP-408.0, Calibiati.on and/or Maintenance of Delta T Channel 4'9-1535

~-2.2,'hole Bod Counter 0 eration PCS 79-2435.

79-1536 "-8P-4.3 Work Permit Use PWi 79-2417. 79-1537 <PZ-31; Safe rd Bearin Tem erature Check PCN 79-2437. 79-1538 %-14.1, Radiation Monitoiin and Related S stems Dail Plot Re cerements PCN 79-1546 :"A-301, Control of Station Modifications PCN 79-2480.
I PAGE 141 PORC ITEM PROCEDURE 79-1547 <HP-4.l, Controlled Area Ent POi 79-2484. 79-1548 %T-2.1; Safet Injection S stem* s, PCN s 79-2466 and 79-2467. 79-1550 CP-4086.0'C" Standb Auxili Feechiater Pum Dischar e Pressure Channel PCN 9-CP-4086.1; Transmitter PT-4086; ~i. 79-2310. CP-4086.2 Powei Su 1 PQ-4086 PVil 79-2311. CP-4086.3 Bistable PB-4086; PCiif 79-2312. CP-4086.4; Indicators PI-4086A and PX-40868 PCN 79-2313. CP-4087.0; Standb Amcili Feedwater Dischar e Pressure e, CP-4087.1, Transmi.ter PT-4087; PCN 79-2315. CP-4087.2 Power Su 1 PQ-4087, PCN 79-2316. CP-4087.3; Bistable PB-4087 PWi 79-2317. CP-4093.0 Standby Auxilia Feedwater s Condensate Tank Leve PC CP-4093.2; Power Su 1 Lg-4093 ~i, 79-2376. CP-4093.3; Bistable LB-4093A PCN 79-2377.
PAGE, 142 PORC ITEM // PROCEDURE CP-4093.4 Bistable LB-4093B,'C& 79-2378. CP-4093.5, Indicator LI-4093; PCN 79-2379. HP-7.17; Q1 E-530 Suive Meter 0 exation and Calibration PCN HP-7.18; Auto Di imaster 305A and B 0 eration and Calibration, PCN HP-7.19 Jordon Rad Gun 0 eration and Calibration PCN 79-2388. HP-7.20; Di imaster Surve Meter 0 eration and Calibration PCN HP-7.21'ordon Radector 7-III 0 eration and Calibration PCN HP-7.22 Hi h Range Surve Meter, CP-5-MJ 0 eration and Ca z rat>on, P HP-7.23; Xetex 501 A-2 Di ital Area Monitor 0 eration and Ca x rat>on, N HP-li.'5.1 NMC Constant Air Monitor AM-3D Calibration, PCN 79-1551 >A-102;4; Indoctrination and Trainin of Qualit Control Personnel 79-1552 <A-502 Plant Procedures and Format Re irements'CN 79-2474. 79-1553 +A-1001 Performance of Tests'CN 79-2470.
PAGE 143 PORC ITEM d PROCEDURE 79-1554 CP-409.0, Reactor Coolant Tem exature', Cold Le "409B" Calibiation an or Maintenance PCÃ - 1 CP-410.0 Reactoi Coolant Tem erature Cold Le "410B" Calibiation an or azntenance, 79-1555 CP-424.3'alibration and/or Ãairitenance of Pressurizer Li 'd em erature n z.cator CP-425.2; Calibration and/or Maintenance of Pressurizer Va or T erature Basta e TC- PCN 79-1556 WP-427.2 Reinstate "427'iessuiizei Level, PCN 79-2173. 79-1557 ~-428.2, Peinstate 428 Piessuiizei Level'CN 79-2174. 79-1558 CP-430.1'eneral Defeat Procedure 430 Pressurizer Piessure CP-430.2'eneial Reinstate Procedure 430 Pressurizer Pressure C e , P CP-431.1 General Defeat Procedure 431 Pressurizer Pressure C e , PCN CP-431.2; General Reinstate Procedure Pressurizer Piessure C e P CP-449.1, Geneial Defeat Procedure for Piessurizer Piessure e CP-449.2 Gerieral Reinstate Procedure foi Pressurizer Pressure C e P- PCN
PAGE 144 PORC nEM f/ PROCEDURE 79-1559 CP-450.0 Ove ressure Protection Loo 450 P&i. 79-2218. CP-452.0, Ove ressure Protection Loo 452 PCS 79-2213. 79-1560 'CP-451.0 Ove ressure Protection Loo 451 PCN 79-2219. 79-1561 CP-409.1 Reactor Coolant Tem erature Cold Le , R/I TH-409 CP-409.2; Reactor Coolant Tem erature Cold Le , Recorder TR-409 P i CP-409.3, Reactor Coolant Tem erature Cold Le Bistable TC-409A/B CP-410.2, Reactor Coolant Tem erature Cold Le , Recorder TR-410 PWi CP-410.3; Reactor Coolant Tem rature Cold Le , Bistable TC-410A/B PCS CP-410.3, Reactor Coolant Tem erature Cold Le , Bistable TC-410A/B PCN CP-424.1'alibiation and/or ~ifaintenance of Pressurizer Li id Tem erature onverter CP-425.1; Calibration and/or Maintenance of Pressurizer Va or Tem erature onverter CP-450.1; Ove ressure Protection Loo 450 Transmitter, PCN
PAGE 145 PORC ITEM PROCEDURE CP-450.2, Ove ressure Protection Loo 450 Power Su 1 and Bz.sta e PCN CP-451.1; Ove ressure Protection Loo 451 Transmitter, CP-451.2; Ove ressure Piotection Loo 451 Power Su 1 and Basta e, PCN CP452.1, Ove iessuie Piotection Loo 452 Transmittei, CP*-452.2; Ove ressuie Protection Loo 452 Powei Su 1 and B2.sta e, CP-455.1, N Accumulatoi Lo Loo 455 Tranmitter PCN 79-2209. CP-455.2 N Accumulator Pressure Low Bistable Power Su 1 and In locator Loo CP-456.1, N Accumulator Pressure Low Loo 456 Transmittei, P CP-456.2 N Accumulator Pressure Low Loo 456 Bistable Powex Su an In z.cator, 79-1562 CP-455.0, N Accumulator Pressure Low Loo 455 PCN 79-2212. CP-456.0, N Accumulator Pressure Low Loo 456 ~i 79-2211. 79-1563 CP-46i:O, Calibration andj'or Maintenance of Stean Generator Level

, P

PAGE 146 PORC ITEM /I PROCEDURE CP-462.0, Calibration and/or iifaintenance of Steam Generator Level C el , PCN CP-463.0; Calibration and/or Maintenance of Steam Generator Level C e 79-1564 CP-464.7; Steam Flow S re Root Extractoi FM-4649, PCN 79-2245. CP-465.7, Steam Flow S uare Root Extractor Fif-465B PCN 79-2244. 79-1565 CP-426.8; Pressuiizer Level Indicator LI-426 PCN 79-2170. CP-428.8; Piessurizer Level Indicator LI-428 PCN 79-2175. CP-461.8; Steam Generator Level Indicator LI-461'CN 79-2206. CP-462.8 Steam Generator Level Indicator LI-462 PQi 79-2204. CP-463.8, Steam Generator Levei Indicator LI-463, PCN 79-2202. CP-465.10 Steam Flow Indicator FI-465; PCN 79-2243. CP-468.10 Steam Generatoi Piessure Indicator PI-468, PCN 79-2239. CP-469.5, Steam Generatoi Piessuie Lead/La Unit PH-469A; CP-469.8; Steam Generator Pressure Indicator PI-469 PCN 79-2237. CP-471.8; Steam Generator Level Indicator LI-471 PCN 79-2236.
1

jt

'l
PAGE 147 PORC iTEM "1/ PROCEDURE CP-472.8 Steam Generator Level Indicator LI-472; PCN 79-2235. 79-1566 WP-46S.'ii Steam Flow Recorder N,-465; PCN 79-2242. 79-1567 CP-431.0, Calibration and)or Maintenance of Pressurizer Piessure C e CP-467.0; Calibration and/or Maintenance of Feedwater Flow C e PCN 79-1568 KP-472.0; Calibration and/or Maintenance of Steam Generator Level 79-1569 CP-473.3; Steam Generator Level Transmitter LT-473'CN 79-2233. 79-1570 WP-'6i7.0; Co onent Coolin Water s Dischar e Pressure PEC-617 PCN 79-1571 CP-1012 Caiibration arid/or Maintenance of "A" Waste Condensate T eve CP-1013 Calibiation and)or Maintenance of "B" Waste Condensate T eve 79-1572 ~-154; Steam Generator Handhole Cover Gasket Leak Re air Usm Furmanz.te Process, PCN 79-1573 ~-i3 Fire Pum 0 eration and S stem Ali nment', PCN 79-2482. 79-1574 %-4.1D Drumr~ Waste Eva rator Bottoms PCN 79-2472. 79-1575 %-30.4, Auxil Feedwater S stem Valve Position Verification
PAGE 148 PORC iTEN t'/ PROCEDURE 79-1576 -SC-1.15 Ins ection of E~r enc E i ment ~i 79-2477. 7e-ii77 "-T-41A; Ali nment of Auxili Feedwater S stem Prior to Power 0 erat>on PCN 79-1586 4Yf-255; Technical Su ort Center Intercom S stems Wirin nsta ate.on 79-1589 4f-38.10; Re air or Re lacement of U-2 Switches PCN 79-2473. 79-1590 +A-7.1, First Aid Su 1 Invento for Plant Stretcher Boxes PCN 79-1591 CP-474.7; Steam Flow S e Root Extractoi FM-47kB'CN 79-2262. CP-475.5 Steam Flow Bistable FC-475A PC8 79-2260. 79-1592 CP-473.8 Stean Generator Level Indicator LI-473; PCN 79-2263. CP-475.7 Steam Flow S e Root Extiactor FH-475B PCN 79-2259. CP-475:il 'te~ Flow Recorder FR-475 PCN 79-2254. CP-474.10 Steam Flow Indicator FI-474 PWi 79-2261. CP-477.9; Feedwater Flow Indicator FI-477; PCN 79-2257; 79-1593 KP-476.9, 'B Feedwater FloYi Indicatoi FI-476, PCN 79-2255. 79-1594 CP-477.5; Feedwater Flow S re Root Extractor FN-477A PCN
PAGE 149 PORC ITEN /I PROCEDURE CP-476.5' Feedwater Plow S ie Root Extractor Rf-476A PCN 79-1595 ~-1.6'uetron E sure PCN 79-2492. 79-1596 "-HP-7.5 Pocket Dosimeter/Accurac and Leak Test'CN 79-2496. 79-1597 CSI-10; Ins ection of Sta nent 0 enated Borated S stems'CN 79-1598 %-3.4D; Boron Rec cle Process Staitu, PCN 79-2488. 79-1599 KC-1.15'ns ection of Emer en E 'ent PCN 79-2493. 79-1608 +A-1104 Ginna Station Technical S ecification Surveillance Pro ram 79-1609 M-1; Schedule for Environmental Sam les and Parameters

-Ana ze PCN 79-1610 '%F-4.3, Mork Permit Use PCN 79-2504.

79-1611 S-5'uclear Sam le Room S lin S stem, PCN 79-2485. 79-1612 "GC-1.4 General Radiation Emer enc PCN 79-2502. 79-1613 :%i -38.11; OZ2 Switches Re air or Replacement for PCN 79-2490.'9-1614 HP-7.1 Calibration of Gamma Surve Instruments - Hi h Ran e PCN
PAGE 150 PORC ITEM PROCEDURE HP-7.2'alibration of Gamma Surve Instruments - Low Ran e PCN M-55.1 Re air or Re lacement of, e W-2 Breaker Control Swz.tc es, PCN 79-1616 "CP-473.0, Calibration and/or Maintenance of Steam Geneiator Level C e PCN 79-1617 WP-473.6; Steam Generatoi Level Bistable LC-473E, PCS 79-2290. 79-1618 "CP-474.5; Steam Flow Bistable FC-474A PCN 79-2288. 79-1619 CP-478.5, Steam Geneiatoi Pressure Lead/La Unit PH-478A CP-478.10; Steam Generator Pressuie Indicator PI-478; PCN 79-2302. CP-479.5, Steam Generatoi Pressure Lead/La Unit PH-479A CP-479.8'team Generatoi Pressure Indicator PI-479'CN 79-2300. CP-482.5, Steam Generator Pressure Lead/La Unit PH-482A CP-482.9 Steam Generatoi Pressure Indicator PI-482A arid Remote P- L CP-483.5; Steam Generatoi Pressure Lead/La Unit 7- PH-483A'CN
PAGE 151 PORC ITEM II PROCEDURE CP-483.9, Steam Generator Pressure Indicator PI-483A and PI-483Ba CP-486.6; Turbine First Sta e Pressure I ulse Unit PM-486B'CN 79-1620 ".CP-482.3 Steam Generator Pressure Transmitter PZ-482 PCN 79-1621 ".CP-2092.0'alibration and/or Maintenance of 2092 Atmos heric Re ze a ve A - Contro 79-1622 CP-2092.2 General Reinstate "2092" Atmos heric Relief Valve 1A CV- Contro, PCN CP-2093.1'eneral Defeat Procedure "2093" Atmos heric Relief Va ve B CV- Contro , PCN 79-1623 a09-2093.0; Calibation and1or Maintenance Re xe ave Contro of 2093 Atmos heric. 79-1'6N HP-7.3; Calibration of Al ha Surve Instruments PAC-4S P& HP-7.4; Calibration of Neutron Surve Instruments,'CN 79-2507. 79-1625 %P-7.6'a in of Instxuments Re irin Calibration or Maintenance PCN 79-1626 %P-7.7; Calibration of Heat Surve Instruments'CN 79-2505. 79-1627 "Q-5.1'oad Reductions PCN 79-2529.
PAGE 152 PORC iTEM d PRQCEXRE 79-1628 KC-1.12A, Immediate Call List PCN 79-2165. 79-1637 Mf-255; Technical Su ort Center Intercom S stems Wirin Insta ation PCN 79-1638 %-10; Malfunction Rod Position Indicatoi'CN 79-2522. 79-1639 "-E-12.1; Malfunctionin Rod Cluster Control Full Len th Rods PCN 79-1.640 N>> -42.2; Charcoal Filters RemovaljInstallation PCN 79-2514. 79-1641 Wi -37.56 Nuclear Sam le S stem Manual Valve Re lacement PCN

+f-43.1i " Steam Generatoi Tube Removal - Steam Generator PCN 0$ -43.23A Steam Generator Recirculation to the "B" Condensate Stora e 79-1643 %M-180'ani ulator Crane Gri er Maintenance, PCN 79-2551. -EM-184; Limitor e Valve 0 erator Removal and Re lacement for MOV- PCN &-43.32 Steam Generator Tubes ID Measurement'CN 79-2545.

79-1644 E-l.l, Immediate Action and Dia nostics for S urious Actuation o SI LOCA, Loss o Secon Coo ant, an Steam Generator Tu e Ru ture PCN
PAGE 153 PORC ITEM PROCEDURE E-l.2; Loss of Reactor Coolant PCN 79-2593. E-l.3'oss of Seconda Coolant PCN 79-2592. E-l.4; Steam Generator Tube Ru ture PCN 79-2591. 79-1645 %-8.1, Restoration of Pressurizer Heaters to Maintain Natural

~cu at>on at HS 79-1646 M-11:11 Crane Ch s Series G and GT Maintenance PCN 79-2553.

M-ll.13 'ns ction and Maintenance of Gould s'CN 79-2560. M-li:16 Durco-Dunrion Maintenance, PCN 79-2566. M-il:i7 Meinman Pum s, PW 79-2565. M-ll.18 Buffalo For e Pum s Maintenance'CN 79-2554. M-ll.19 Crane-Demin Pum s Maintenance, PCN 79-2564. M-11.20, Econo Pum s Vertical T e Maintenance'CN 79-2463. A-li.22 La -'Inte ace Pulsa Feeder Pum s PCN 79-2562. M-11.31; Condensate Polishin Sundstrand Air Blower Maintenance M-'11.33; Condensate Booster . Ins ection and Maintenance'
PAGE 154 PORC iTEM // PROCEDURE M-37.12 Aaintenance Isolati.on Proceduxe for V-392B Char in Line to Co dLe A PCN M-37.34'ain Steam Line Power 0 crated Relief Valves 3410 or 3411 axntenance M-43.23 Steam Generator Tubesheet Lancin PCN 79-2548. M-43.25; Installation of Steam Generator Handhole Cover PCN M-45.2; Non-Safe rd Motor for Ins ection, PCN 79-2556. M-61.2; Auxili Buildin S Tank Ins ection and PCN - 5 Cleanin~'-63.1, Fan Cooler Unit Maintenance PCN 79.-2557; 79-1647 +A-1602'reventive Action Re rt PCN 79-2544. 79-1649 ~-945.7'ontainment Pressure Indicatoi PI-945; PCN 79-2349.

~-496.7, Containment Pressure Indicator PI-946 PCN 79-2348.

KP-497.7 Containment Pressure Indicator PI-947 PCN 79-2347.

~-948.7 Containment Pressure Indicator PI-948 PCN 79-2346.

WP-949.7 Containment Pressure Indicator PI-949'Wi. 79-2345.

<P-950.7; Containment Pressure Indicator PI-950 PCN 79-2344.

PAGE 155 lePORC PROCEDURE 79-1651 CP-624.1; Residual Heat Removal Heat Exchan er Outlet Valve HCV-624 Isolation PCN CP-625.1, Residual Heat Removal Heat Exc er Valve HCV-625 Iso at~on, PCN CP-626.1, Defeat of Residual Heat Removal Floe Channel "626" P CP-934.2'ccumultor Level Bistable LC-934 PCS 79-2359. CP-934.3 Accumulator Level Local Indicator LI-934 PCN 79-2358. CP-945.1, Defeat of "A-1" Contairment Pressure Channel "945" CP-945.2, Reinstate of "A-1" Containment Pressure Channel "945", CP-947.1, Defeat of "A-3" Containment Pressure Channel "947"'P-947.2; Reinstate of "A-3" Containment Pressure Channel "947"'P-949.1; Defeat of "B-l" Contairment Pressure Channel "949" CP-949.2 Reinstate of "B-1" Contiinment Pressure Channel "949"'CN CP-1090.1, //1 Fan Cooler Condensate Level Transmitter LT-1090'CN
PAGE 156 PROCEDURE CP-1091.1; II2 Fan Coolei Condensate Level Transmitter LT-1091 PCN CP-1092."1, /f3 Fan Cooler Condensate Level Transroitter LT-1092 PCN CP-1093.i; t/4 Fan Coolei Condensate Level Txansmitter LT-1093 CP-2006.0; Turbine Driven Auxili Feedwater Flow to Steam Generator oo CP-2007.0'uibine Driven Auxilia Feedwater Flow to Steam Generator B oo CN 79-1652 KP-626.0, Calibration an*d/oi Maintenance of Residual Heat Removal FowC e PCN 79-1655 KP-629.0,'esidual Heat Removal Loo Pressure "629", PCN 79-2362. 79-1654 "CP-920.0 Calibration and/or Maintenance "920" Refuelin 'Pater Stora e T Leve C e , PCiiI 79-1655 KP-930.0, Calibration and)or Mai.ntenance of S ra Additive Tank n et F ow Transmit.tter oo , 79-1656 CP-937.0; Calibration and/or Maintenance of Accumulator Pressure C e , PCN CP-939.0, Calibration and/pi Maintenance of Accumulator Level C e
PAGE 157 PORC ITEM // PROCEDURE CP-940.0 Calibration and/or Maintenance of Accumulator Pressure C e , PCN CP-941.0, Calibration and/or Maintenance of Accumulator Pressure C e PCN 79-1657 CP-938.0, Calibration and/or Maintenance of Accumulator Level C e CP-2030.0 1B Motor Driven Auxili Feedwater Dischar e Pressure Loo 'N 79-1658 "CP-940.'1; Accumulator Pressure Transmitter PT-940 PCN 79-2353. 79-1659 KP-942.0; Check and/or Maintenance of Containment S gl Level Switches and In icatin Li ts PCN 7 - 5 79-1660 KP-943.0 Check and/or Maintenance of Containment Sum B //2 Level Sm.tc es an In xcatzn Lx ts PCN 79-1661 KP-1037, Calibration and/or Maintenance of f/2 Gas Deca Tank Pressure C e PCN 79-1663 CP-2092.1, General Defeat Procedure "2092" Atmos heric Relief Valve 1A CV-5 Control PCN 79- 3 1. CP-2093.2, General Reinstate "2093" Atmos heric Relief Valve B CV- Contro , PCN 79-1664 E-9'eakage into the Com onent Coolin Loo PCN 79-2523. E-ll, Continuous Rod Mithdrawl'Ql 79-2520.
PAGE 158 PORC ITEM' '// PROCEDURE E-15.1'malfunction of Piessurizer Power Relief or Safet Valves'CN E-15.2'alfunction of Pressurizer Heaters or S ra Valves'CN E-17 Loss of Residual Heat Removal, P& 79-2525. E-19, Contirnious Insertion of RCCA Control Bank'CN 79-2524. 79-1665 CS-39.0; Piotection Vital/Area Access PCN 79-2550. 79-1666 4P-2.1 Whole Bod Countin Guide'ViI 79-2559. 79-1667 %T-17.2'rocess Radiation ifonitois R-ll - R-21 and R-10A and B, PCN 79-l668 PT-22.8, Mechanical Manifold A Leakrate Test'CN 79-2538. PT-22.9; Mechanical Manifold 'B Leakrate Test'CN 79-2537. PT-22.10 Mechanical Manifold C Leakrate Test, PCN 79-2536. PT-22.1i, Mechanical Manifold 'E Leak@ate Test'CN 79-2535. PT-22.12 Mechanical Manifold 'F Leakrate Test PCN 79-2534. PT-22.13; Mechanical Manifold IG Leakrate Test PCN 79-2533; PT-22.14 Mechanical Manifold 'H Leakrate Test'Vl 79-2532.
PAGE 159 PORC ITBf PROCEDURE PZ-22.16 Mechanical Manifold "J" Leakrate Test, PCN 79-2531. PT-22.17 Mechanical Manifold 'k" Leakrate Test PCN 79-2530. 79-1669 ~IP-21, Shi in Packa e LL-50-100 Ins ection PCN 79-2570. 79-1670 S-16A; Safet Injection S stem Ali nment, PCN 79-2568. S-30.2 RHR S stem Valve Position Verification PCN 79-2569. 79-1683 "-SM 79-1837.2 Fiie Doors Installation', PCN 79-2589. 79-168+ "-M-57.2; Source Ran e and/oi Intermediate Ran e NIS Detector Re acement, PCN 79-1685 "-ISI-9.1; Inservice Ins ection of Shell T e Anchor Bolts PCN

~SP-15.12' of Class "B" Pi in 79-1686 Fee ater i indro Test PCN (A and B Steam Generator 79-1687 -EbR-2603'irect Indi.cation of Valve Position Pressurizer Safet a ve osxtion In ication.

79-1688 ~-2603A Direct Indication Valve Posi.tion Pressurizer Power crate Re ie a ve In ication. 79-1689 ~~1-43.16.2; Installation of Steam Generator Mechanical Tube Plu s 79-1690 %-51.5 Westin house BFD Rela Armature Overtiavel Measurement
PAGE 160 PORC ITEM f/ PROCEDURE 79-1693 "SM 79-2603.1'ressurizer Safet Valve Direct Position Indicator PCN 79-79-1694 "SH 79-2603A.1 'ressurizei PORV *Direct Position Indicator to Co uter CN 79-1695 %M 79-2604.1, RCS Subcoolin Mai in ifonitoiin S stem PCN 79-2630. 79-1697 "=A-l.l; Locked Radiation Areas'Wi 79-2596. 79-1699 T-36.2 Service Mater Redundant Return Line 0 eration PCN 79-2623. T-44.1, Condensate Su 1 Tank for Standb Auxili Feedh<ater sFi in, ~i 79-1700 H-73.4; Co onents to Stainless Steel Pi in. or Com onents PCN SM 79-01.1'eedwater Drain Lines Inside Containment'CN 79-2638. SM 77-06.2 Low* Pressure Purification S stem Modification H dro-static Test CN Pif 77-06.3; Low Pressure Purification S stem Modification, PCN 79-1701 SC-1.3D'annin the Technical Su it Center PQf 79-2500. SC-1.3E'annin the 0 erational Su ort Center'CN 79-2501. 79-1702 H-38 E lizin Char e Station Batte S stems PCN 79.-2605.
PAGE 161 PORC ITEM II PROCEDURE M-44.3 Isolation of 1C YCC and Restorin to Seivi.ce PCN 79-2609. N-44.4; Isolation of 1D YCC and Restor'o Service PCN 79-2610. M-44.5; Isolation and Restoration of Motor Control Center lE; PCN M-44.6, Isolation and Restoration of Motor Control Center 1F M-55.3'aintenance of Control Pod Drive Mechanism Coil Stack PCN 79-1703 -A-601, Plant Procedure Document Contiol PCN 79-2637. 79-1705 E-4, Station Blackout 0 eiation PCN 79-2579. E-26.1; Reactor Tri -Turbine Not Latched'Ql 79-2580. E-26.2 Reactoi Tii -'Turbine Latched PCN 79-2581. 79-17O6 ~-251, Rock Anchor Cou lin Enclosure Broken Bolt Re air'CN 79-17O7 %P-1.4, Noble Gas E osure PCN 79-2636. 79-1708 %P-2.3 TLD Readei Calibration PCN 79-2618. 79-1709 WSI-9.1; Inservice Ins ection of Shell e Anchor Bolts'CN
PAGE 162 PORC ITEM II PROCEDURE 79-1710 ~i&18el Drum Pre aration for Waste Eva rator Bottoms, PCN 79-2603. 79-1711 %-57.2, Source Ran e and/or Intermediate Ran e NIS Detector Re acement PCN 79-1712 %-6.10; Plant 0 eration With Steam Generator Tube Leak Indication PCN 79-1713 ~Q-8; Natural Circulation in the RCS, PCN 79-2578. 79-1714 %-25.4 Processin Water from Either Steam Generator PCS's 79-2599 79-1715 %M 77-1836.2, Relocation of Halon S stem, PCN s 79-2611 and 79-1723 >8-43.31.1; Steam Generator Handhole Gasket Surface Weld Re air PCN 79-1724 ~-256'e ai.r of the Safe Erid for the Pressurizer Power 0 crated Re xe a ve one, 79-1728 "K&257; Furmanite Re air - Valve 427 CVCS Letdown Isolation Peril 79-1729 "SP-4.3, Work Permi.t Use PCN 79-2612. 79-1732 A-53.3, Valve Pieventive Maintenance Pro ram PCN 79-2595. CP-430.11 Pressurizer Pressure Re eater PM-430A.1 PCN 79-2633. CP-4086.0 "C" Standb Auxil'eedwater Pum Dischar e Pressure C e PCN
PAGE 163 PROCEDURE CP-4086.1; "C" Standb Auxili Feedwatei Pum Dischar e Pressure Transmitter PT-, PCN 7 - 1 CP-4086.2 "C" Standb Auxili Feedwater Pum Dischar e Pressure Power Su , PCN CP-4086.3'C" Standb Auxili Feedwater Pum Pressure Bistable B- CN CP-4086.'4, "C" Standb Auxili Feedwater Dischar e Pressure In xcators PI- A an PI- B PCN CP 4087 0 j 'D Standb AUxilia Feedwater Pum Dischar e Pressure C e CN CP-4087.1'D" Standb Auxili Feedwater Dischar e Pressure Transmitter, CP-4087.2 '5" Standb Auxilia Feedwater Dischar e Pressure Power Su PCN CP-4087.3; "D" Standb Auxilia Feedwater Pum Dischar e Pressure Basta e PB- P i CP-4087.4'D" Standb Auxili Feedwater Pum Dischar e Pressure n zcators P- an CP-4093.1; Standb Condensate Level Transmitter LT-4093 PCN M-83'ani ulator Crane Gri er and Inner bfast Maintenance PCN M-84'leanin of Feedwatei Flow Venturis', PCN 79-2628.
PAGE 164 PROCEDURE M-31; Statox Re lacement for Part Len*th Control Rod Drive S stem PCN HHE-'ioo-1 'aintenance and Ins ection of 40/5 Ton Shaw Box Crane t in e uxi i Bui in HHE-100-2; Maintenance and Ins ection of 100/20 Ton tahiti Crane in Containment Seria No. HHE-100-3'aintenance and Xns ection of 125/25 Ton Whitin Crane in t e ur ine Bui in Seria No. HHE-200-1; Ins ection of ers Hoist Seria No. Area PCN and Maintenance TWL in t e Auxi i 5 TonBuiRobbins and in Drummin M HHE-300-1; Xns ection and Maintenance of 10 Tons Robbins and ers Hoist Seria No. TU in ontainment CN ~USE-300-2; Ins ection and Maintenance of 3 Ton P and H Jib. Crane eria o. ontainment HHE-400-1 Ins ection and Maintenance of 18 Ton Grove Mobile H xau ic Crane P i HHE-500-1 Ins ection and Maintenance of 1 Ton P and H Electric 0 crate Hoists in .V. MHE-500-2; Xns ection and Maintenance of 1 Ton P and H Electric 0 crate Hoists in t e uxi i Bui HHE-600-1'ns ection and Haintenance of All Chishalm - Moore E ectric C in Hoists in t e to Room P
C S
PAGE 165 PORC ITBf // PROC EDUPJ". MHE-700-1; Ins ection and Maintenance of Hand 0 crated Chain Hoz.sts m t e Ran e o~ Ton to Ton Ca ace.t , PCN MHE-700-2, Ins ection and Maintenance of Hand 0 crated Chain Hoists in the Range o Ton to 1 Ton Ca acct PCN 79-2692. RK-900-1; Ins ection and Maintenance of Chi.'shalm - Moore Lever 0 crate C in Pu ers an Ton CN MHE-900-2 Ins ection .and Maintenance of Ratcliff Lever 0 crated C xn Ho>.sts, PCN MHE-900-3, Ins ection and Mainenance of L All Lever 0 crated Pu ers, PCN MHE-1000-1, Ins ection of Sli s, PCN 79-2696. S-19'ailed Level Monitor S stem PCN 79-2701.- S-28.2'ailed Fuel Detection Sam le Line Isolation/Restoration P 79-1734 M-5, Control Room Inaccessibili 'CN 79-2655.

"X-28'eactor Coolant Leak; PCN 79-2656. ~i-31 Automatic Turbine Load Runback; PCN 79-2674. -E-32', Loss of Instrument Air, PCN 79-2675. +l-55.2 Control Rod Drive Cables and Assemblies Mainte~i ce and/or Ins ection,

PAGE 166 PORC ITEM // PROCEDURE

8-55.4; Permissible Rod Movement for Troubleshootin Rod Control Far.lure, PCiN T-5C; Condensate Pum Isolation PCN 79-2626.

T-6.7 AVP Concentrated Acid Pum s - Isolatin 'lushin and Returns to Norma PCiN T-6.8,'VP Concentrated Caustic Pum s - Isolatin , Flushin and Returns.n to Norma PCil 79-1735 +A-7; Procedures for Handlin Illness or In'uries at Ginna Station'CN s 7 7 , and 79-nsibilities'CN N 79-1736 ""A-54.4; Du En ineer Res 79-2680. 79-1737 "CP-430.0, Calibration and/or Maintenance of Pressurizer Pressure C nne , N 79-1738 %-16.2; Hi h Iodine 131 in the Plant Vent,'CiN 79-2665. 79-1739 W-20; Immediate Boration'CN 79-2657. 79-1740 E-23.1, Malfunction of //1 Reactor Coolant Seal PCN 79-2673. E-23.2 Malfunction of >/2 Reactor Coolant Pum Seal PCN 79-2672. E-23.3, Malfunction of J/3 Reactor Coolant Pum Seal'CN 79-2671. E-23.4'oss of Reactor Coolant Pum Seal In'ection Su 1

'PAGE 167 PORC ITEM /I PROCEDURE E-23.5; Reactor Coolant Pum Seal No. 1 Seal Leak-off Flow on or 0 PCN E-25 Loss of Containment Inte rit PCN 79-2668.

E-30.1'artial Loss of Condenser Vacuum'CN 79-2663. E-30.2'o lete Loss of Condenser Vacuum PCN 79-2662. E-36, 0 erator Actions to be Taken in the Event of Alarm Conditions on t e Tur vive Vz rat>on Instruments, PCN E-37.1; New UO Fuel Assembl Dro in of Collision with Another 0 gect PCN E-37.3 S ent Fuel Assembl or Rod Control Cluster Drop in or Co as@on m.t Anot er 0 ject PCN 79-1741 WS-39.0; Protected Vital Area Access'CN 79-2659. 79-1742 %P-11.2* Iodirie in Air - Charcoal Cartrid e Method'CN 79-2642. 79-1743 %P-11.10; Aix Sam lin with Siersat*Low Volume Air Sam les, PCN 79-1744 ~-12.6; Issuance'ro i Use arid Return of Res irators 79-1745 MSI-1.2.1 Quali Grou A Inservice Ins ection PCN 79-2660. 79-1746 M-l.l, Plant Heatu from Cold Shutdown to Hot Shutdown PCN
PAGE 168 PORC ITEM PROCEDURE 79-1747 6-2.3.2; Fillin and Ventin the RCS PCN 79-2708. 79-1768 -PT-2.2 Residual Heat Removal S stem, PCN 79-2646. 79-1749 -PT-2.6 Cold/Refuelin Shutdown Air crated Valve Surveillance PCN 79-1750 %T-7' dro Test of RCS PCN s 79-2726 and 79-2728. 79-1751 sS-30.1'afe Injection S stem Valve Position Verification PCN 79-1752 "-S-30.6 Safe d Valve Position Verification (Inside CV) PCN 79-1753 "-Z-41C'urbine Driven Auxili Feedwater Pum Restoration to Senn.ce ter Maintenance 79-1761 +A-201 Shift Technical Advisor Accountable to Technical Assistant 0 eratzona Assessment En meer 79-1762 ~-235; Fummnitin MOV-700 RHR From Loo 'CN 79-2722. 79-1763 'AS-3.3Ae Coolant Chemist Addition Tank'CN 79-2713. 79-1764 -A-52.1 Shift Or animation and Res nsibilities'CN 79-2654. 79-1765 -A-52.1.1, Shift Relief Turnover PCN 79-2651. 79-1766 ~A-52.1.2'hift Relief Turnover - Parameter Check PCN 79-2652.
PORC ITBf

/i'AGE 169 PROCEDURE 79-1767 +A-52.1.3; Shift Relief Turnover - Auxilia 0 erato'CN 79-2667.

79-1768 %-1.5 Void Formation iri the R*CS PCN 79-2582. 79-1769 W-l.l; Plant Heatu From Cold Shutdown to Hot Shutdown, PCN 7 75 ~ 79-1770 "O-6;2 Main Control Board Verification PCN 79-2650. 79-1771 <A-102.2, R. E. Ginna Administrative Controls Train'ro ram PCN 79- 7 79-1772 ""'EN-257 Furmanite Pe air - Valve 427 CVCS Letdown Isolation P 79-1774 sS-9L, Batchin Bori.c Acid and Transferri o to S ent Fuel Pit P 79-1775 "=A-102.1'acilit Staff Trains Pro ram Ginna Station Personnel Tram+ Pro ram, PCN 79-1776 eA-403; Re isitionin Services from General Maintenance PCiil 79-1777 eA-604 Control of ConstmucLion Documents PCN 79-2749. 79-1778 +A-1502 Non-Conformance Re orts, PCN 79-2698. 79-1779 "%-1.6; CVCS Leak'CN 79-2761. 79-1780 <X-7, Dro of a Pull Le th Rod Cluster Control Assembl PCN
PAGE 170 PORC

// PROCEDURE 79-1781 ="ISI-9.1'njervice Ins ection of Shell e Anchor Bolts, PCN 79-1782 ~41-56.1'lacement of Ceramic Fiber Penetration Seals PCN 79-2754.

79-1783 %-6.13'ail Survei.llance Lo PCN 79-2767. 79-1784 KC-18.3,'etermination of Chloride b < ecific Ion Electrode P 79-1785 -PT-7 RCS H dro Test,'Ciif 79-2739. 79-1786 ~-13; Fire Pum 0 ration and S stem Ali nment PCN 79-2710. 79-1787 ~S-3.2D; Transferrin Water From CVCS HUT s to RWST or SFP PCN 79-1792 M-27.3 Fuel Oil Recei t Emer enc /Fire Diesel'CN 79-2765. 79-1793 M-32'ire Service Water S stem PCN 79-2714. 79-1794 %C-9.0'etexmi.nati.on of Chromate ~i 79-2705. 79-1802 +A-52;1.4; Health Ph sics and Chemist Shift Chan cover PCN 79-1803 "WC-23.1'mei en Sam lin of Piima Coolant PCN 79-2706. 79-1804 -PC-23.2 Containment Radio@as Sam lin~ and Anal sis Durin a Con-taument Iso ation PCN 79-1805 "TC-23.3 Estimate of Noble Gas Release Rate from the Plant Vent Durban Accident Conditions PCN 79- 7
PAGE 171 PORC ITB1 // PROCEDURE 79-1806 "6C-1 'adiation ~er en Plan PCN 79-2576. 79-1807 "SC-1.3A Si.te Radi.ation Emer enc (Shift Su ervisor and Control Room . PCN s 79- an
PAGE 172 PORC ITEM ff PROCEDUPZ 79-31 -SH 78-1890.2 'eedwater Line Drain Valves After the Containment C ec.c Va ves PCN - . is procedure is to prom. e a pro-ce e or per orming mo ification. The Committee recommended approval of this new procedure. This item IS NOZ COMPLETE pending closeout review of the completed procedure. A Safety Evaluation was performed and it was detexmined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-32 -SM 78-1594 A-1 Installation of S ent Fuel Pit Suction Strainer FCN . This procedure is to describe the wo necessary to

~usta a new suction strainer for the upper section from the spent fuel pool. The Committee recommended approval of this new pro-cedure. This item IS hOT COMPLETE ending closeout review of the completed procedure.

A Safety Evaluation was perfoxmed and it was detexmined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessaxy. 79-78 WM 78-1845.1, Guide Stud Stora e Racks, PCN 79-41. R. Yeckel presented t is pxocedure change. It requested minor revisions be made to incorporate Revision 1 to Reference 1 and improve the procedure. The Committee recommended approval of this procedure change. This item IS COWLEZE. A Safety Evaluation was performed and it was detexmined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-90 SM 78-1594A.1'nstallation of SFP Suction Strainer PCN 79-83. This request to N/A Steps . . . p 9 and 6.9.1 as temporary strainer will not be required per field change to Drawing //10904-72. A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary.
PAGE 173 PORC ITEf~ t/ PROC

'Vi1 78-ED'9-92 ~58 77-1499.1,'od Insertion Limit Circuit R. Yec~e present t xs new proc ure to pro-instructions for rcodifying Pod Insertion 7.nsit pl~ ~cCa Circuitry as per Ki& 1499 Design Criteria. The Com-mittee recommended approval of this new procedure.

This item IS I1OT CGWLEZE pending closeout review of h A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-93 "SN 78-1872 1 ~ tfani ulator Crane Gri er S stem kfodi-z.cat>on, PC'ii1 - . R. Ye e presented the.s new proce ure to escrow. e the method to install a modified double acting gripper actuation system on the manipu-lator crane. The Committee recommended appxoval of this new procedure. This item IS i'OMPLETE pending closeout review of the complet proce.ure. A Safety Evaluation was pexformed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-130 SN 76-21.4 Batte Room Air Conditionin - Air Condi-tioner Dzsc ar e Duct Sout En o Batte Room, PCS A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in Lhe Plant Operating Technical Specifications is not necessary. Sil 76-21.6, Batte Room Air Conditionin Air Su 1 Duct to t e Axr Con ztioner PCii1 A Safety Evaluation was performed and it was deterttined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. Siif 76-21.5; Batte Room Air Conditionin - Service

%tater Px. xn Insta at~on A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Speci ications is not necessaxy.

PAGE 174 PORC iTEM /! 'ROCEDURE SM 76-21.7; Batte Room Air Conditionin - Miscellane-ous PCN 7-A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SH 74-28.1, Installation of Hake-U Lines to Condensate Stora e Tanks PCN 7 -1 1. A Safety Evaluation was performed and it was determined that the accident is not increased. A change in the Plant possibility of an Operating Technical Specifications is not necessary. SM 75-48.30, Rework of*the Auxili Feedwater Crossover Pz. zn H z. z.cation PCN A Safety Evaluation was performed and it was detemined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary. SM 77-1030.1'eutralizin~ Tank Lo ic Modification PCN 7 -1 3. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 81 77-2110.1; Chen. Lab DI Storage Tanlc Cable Routing, PCN A Safety Evaluation was performed and of it was determined that the in the Plant possibility an accident is not increased. A change Operating Technical Specifications is not necessary. SM 77-1449.1'iesel Fiie Pum Heatei PCS 79-135. A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary.
PA% 175. PORC iTEM f/ PROCEDURE 79-159 78-1594A.'2; Standb S ent Fuel Pit Pum Cable Rout-PCN - . . Yec e present is new proce-ure to escri the steps necessary to install conduit and cable for the standby spent fuel pit pump. The Committee recommended approval of this new procedure. This item IS pending closeout review of

~q ~p NOT COYPLEZE A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

79-160 %M 78-1594A.3 Installation of S ent Fuel Pit Coolin Ba u S stem, PCN - . R. Ye .e present is new proce ure to escri e the steps necessary to iso-late the system and to install butterfly valves and other mechanical components to existing plant systems. The Committee recommended approval of this new pxoce-dure.'his P'd item IS

~p hOT GOMPLETE pending closeout A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change .in the Plant Operating Technical Specifications is not necessary.

79-166 %M 75-14.1 Batch Tank Recirculation Heat Trice Installation rown present ' t is temporary

' proce ure ange q q procedure as Field Change Request is no longer required. The-Committee reviewed this procedure change. This item IS COM-PLETE.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant

.Operating Technical Specifications is not necessary.

79-i72 WiN 77-1682.5 Penetration Testin Modification-Penetration , PCN

- . J. Brown presented , t is proce e c nge. It requested several minor revisions be made to the procedure to incorporate Revision 1 to Bell/Schneider procedure and improve procedure. The Committee recommended approval of this procedure change. This item IS CQ~jPLETE.

A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary.
PAGE 176 PORC ITH"1 lf PROCEDURE 79-184 @M-2714.1 "A" Steani Geneiator J-Tube Podification PCN 78-2693. J. Brown present t is new proc ure to escri e t e steps necessary to install J-Tubes on top of the eedwater distri-bution ring header'nd plug the existing hoes on the bottom of A il new procedure. Wl Pp~ this ring header. The Committee recomm nded approval of this This item IS NOT COMPLEIZ pending closeout Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-185 >51&2714.2 "B" Steam Generatoi J-Tube Ifodificat:ion PWi 78-2692. J. Broth presente t is new proce re ti escri e tne steps necessary to install J-Tubes on top of the feedwater distribution ring header and plug the existing bales on the bottom of this ring header . The Committee recommended approval of this new procedure. This item IS hOT CO%'LETE pending closeout i I * .pl A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-190 <SN 78-1657.1 Installation of 42" Duct for Control Room Ventil-ation PW - . J. Brim presented the following pxoc ure c ange. It requested that steps 6.2.1,'.3, 6.4, 6.4.1, and 6.5 be performed in any sequence to assure job completion in a timely manner because it is not realistic to do each part of the installation in strict chronological sequential order. The Committee recotm nded appxoval of the procedure change. This item IS CQ~fPLETE. A Safety Evaluation was performed and it was detexnined that the possibility of an accident is not increased. A change in the Plant Operating Technical Speci..ications is not necessaxy. 79-2W <SM 77-1623.1'har in Pum Honoiail,'W 79-,308. J. Brown pre-sent t is temporary proce ure c ange or review only. It re-quested Steps 6.5.1, 6.5.2; and 6.5.3 be N/A'd as the monorail was not installed. The Committee reviewed this temporary proce-dure change. This item IS CQ~PLETE. A Safety Evaluation was perfoxmed and it was detexmined that the possibility of an accident is not increased. A change in the Plant Opexating Technical Specifications is not necessaxy.
PAGE 177 PORC ITEM 8 79-216 SM 79-1880.1, Part Le th Control Rod Drive Shaft Retention or 0 eration Wit .out Part Len t R s PCN J. Larizza presente t is new proce ure toget er with the

>westinghouse Safety Evaluation, the RGB Design Review of the part length rod removal and system modification, SM 79-1880.1 for review. Item II of the safety evaluation performed by westinghouse addresses thimble plugs assembly mechanical devices. The plug assemblies to be installed at Ginna are of the flow mixer type and contain sixteen rather than twenty short rods. The Committee recommended approval of this new procedure and safety evaluation. This item IS NOT CO.PLEZE pending completion of the edification.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A charge in the Plant Operating Technical Specifications is not necessary. 79-215 "SH 78-2133.1, Valves 866A and 8668 Hodification for Testin ', PCiit - . J. Brown present t is new proce ure to escribe ll l. 866B and modify piping to install new valves for testing. 866 The Committee recommended approval of this new procedure. This item IS NOT COl&LETE pending closeout review of the completed 8 A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-216 <SN 79-1832A.1 Circuit Se aration ~use Installation PVif 79-333. J. Brut presented this new procedure to describe the steps necessary to install fuse disconnect bloc'.cs and wiring in Buses 14-16-17 4 18. The Co~i 'ttee reconrranded approval of this new procedure. This item IS 'KOT CO%'LETE pending closeout review of the completed procedure. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
PAGE 178 PORC ITEM 8 PROC EDUPZ 79-267 ~ 78-1845.1'uide present Stud Stora e Racks PCN 79-276. J. Brown thzs procedure ange. It request e following changes: Revise Step 2.1 to read:

"2.1 Bell/Schneider Work Procedure EK 1845, Revision 3."

Replace WP EWR 1845 Revision 1 with attached Revision 3. This is to update the procedure. The Committee recomrended approval of this procedure change. This item IS CQWLETE. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-260 "-SM 79-2428; RCP Lube Oil Level Indication. J. St. Martin presented Revision 0 o the Sa ety Analysis and Revision 0 of the Design Criteria for this modification. The Committee perforated a Safety Evaluation and determined there were no unreviewed safety questions or Technical Specification changes required. This item IS WZ CG'f-PLEZE pending completion of this modification. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant

'l Operating Technical Specifications is not necessary.

79-260 "SM 77-1431.1, AF4 Plow Control Valve - Mechancial Installation PQV - . J. St. Martxn presente this new procedure to e-p miscellaneous supports

~

for the AH< Plow h 'p'hh d d Control Valve Modifica-tion. The Committee recommended approval of this new procedure. This item IS lLT CGWLEZE pending closeout review of the com-p Kp A Safety Evaluation was performed and it was determined that the A change in the Plant possibility of an accident is not increased. Operating Technical Specifications is not necessary.
PAGE 179 PORC IT&i 0 PROCEDURE 79-288 ""SN 77-1682.10; H drostatic Testin of Penetration 1 sent Pi inp M i ication, PCiil - . J. Brown pre-t zs proce ure c ange. t requested minor revisions be made to make the procedure consistent and complete with respect to SH-1682.5. The Com-mittee recomzended approval of this procedure change. This item IS CIPMTE. A Safety Evaluation was perfoxmed and it was determined that the possibility of an accident is not increased. A change in the lant Operating Technica Specifications is not necessaxy. 79-290 "6N 79-1832A.2 Circuit Se aration Installation PCS 79-351. J. Brown present t xs new proc ure to escrow. e t e steps necessary to install fuse disconnect blodcs and wiring in Buses 13 and 15. The Cormnittee reco;noended approval of this new procedure. This item IS hOT COMPLETE pending closeout review of the completed procedure. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-308 "SH 77-1891.1 Electric Heat Tracin for Valve 825 A 6 B, PCN - . J. Brown presente t xs proce ure c ange. It requested several revisions be made to the procedure to conform with drawing change and to facilitate fabri-cation prior to installation activities. The Corznittee recommended approval of this procedure change. This item IS CG~PLETE. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
PAGE 180 PROCEOURE SM 1594A.4, Qualificatiori and Leak Testin of Standb SFP Coolin Co onents PCN - . is ange reques-t t e o owing c ange to Step .4.3: "Step 6.4.3 Service Mater Inlet and Outlet Tempera-tures not taken during test." This is because temperatures are not necessary for Engi-neering data. A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessaxy. SM 78-1872.1, Mani. ulator Ciane Gri er S stem Modi.fica-tion PCN - . This change requested minox revisions ma e to t e procedure to facilitate the change as re-quired without changing the intent. A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary. SM 79-2417.1'A" Steam Generator J-Tube Modification', PCN - . This c nge requeste a nge to Step 3 12 3 '3.23.1" '33.-3.1". This is to correct the incorrectly referenced procedure. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SM 79-2417.1 "A" Steam Generator J-Tube Modi.fication, PCN - . is change request minor revisions to 3.23. '1 sampling requirements were modified. A Safety Evaluation was performed and it was detexmined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary.
PAGE 181 PORC ITEM P PROCEDURE SM 79-2417.2'B'team Generator J-Tiibe hfodification PCN - . This ange requeste a change to Step

- 2 d 4 ld 4 3.24.1" '2143-23.2"'.

This is to correct the incorrectly referenced procedure. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SM 79-2417.2 "B" Steam Gendeiator J-Tube Modificationd

~3. zs c ange request 3.211.2 sampling requirements were modified.

manor rem.sz.ons to Tne Committee reviewed these temporary procedure changes. This item IS COWLE1T.. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-337 SM 78-1464.1 Re lacement of Volume *Control Tank Level Transmitters, PVi.l - . This requested minor changes ma e to t e proce ure to ensure proper hookup of the system. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SM 78-1464.2; Re lacement of Accumulator Level Trans-m.tters LT- LT- , LT- an LT- . PCS zs request moor c nges ma e to t e proce ure to ensure proper hook-up of the system. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
PAGE 182 PORC IT&i f7 PROCEDURE SM 77-1623.1 T ~s request Chir i'onoiails to ma "Step . N A" as Bra y PCN 79-470. letters will be applied after painting is completed after shutdown for "C" Charging Pump. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SH 78-1890.2 Feechiater Lirie Drain Valves After the Containment e a ves, i - . s requested t e delxneatxon o Step 4. to al ow contractor to drill as they see fit: pilot hole,'hen larger hole, using electric drill. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SM 78-*2133.1'alves 866A ind 866B Modification for Testm, PCN - . zs request t e o om.ng steps e a to Step 6.1. 6.1.4 Ensure V-868A open. V-868A Open 6.1.5 Ensure V-868B open. V-868B Open 6.1.6 Open Spray Header Drain. V-2825 Open 6.1.7 Open Spray Header Drain. V-2826 Open 6.6.2.1 Close Spray Header Drain.V-2825 CloseeC 6.6.2.2 Close Spray Header Drain.V-2826 Closed These were omitted frcm the procedure when last issued. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
PAGE 183 PORC ITEhl II PROCEDURE SM 79-2417.2' B'team Generatoi J-Tube

- l. t e e' meat>on Modi.fication'CN . zs requeste o Steps ~h 6.16.1.3, 6.16.1.4 p 6.16.13.1 delete words "after grinding". Add new Step 6.16.1 to read: "Placement of feedwater ring plugs at the feed-water ring to tee connections to be done as per Vesting-house field change Number 3." This is because supports in the area are located differently than shown on draw-ings ~

The Conunittee reviewed these temporary changes. This item IS OOMPLEZE. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-353 %M 77-1431.2' drostatic Test of Auxili Feechiater M i icatzon PCN - . J. St. Martin present thz.s new proce ure to per orm required tests of the modified piping for the 1A and 1B Auxiliary Feedwater Pumps. The Committee recommended approval of this new procedure. This item IS NOT CRPLEZE pending completion of this modification. A Safety Evaluation was performed and it was determined possibility of an accident is not increased. A change that the in the Plant Operating Technical Specifications is not necessary. 79-388 ~~M 77-1431.4, Installation of Electricai E Auxil Feedwater F ow Control B ass Valves PVif -631. i ment for J. St. Martxn present t zs new proc ure to escrow. e t e steps needed to install miscellaneous electric equipment for the Auxiliary Feedwater Flow Control Modification. Mechanical installation is in accordance with SM 77-1431.1. Electrical terminations and checkout are in accordance with SM 77-1431.3. The Committee recqnmended approval of this new procedure. This item IS NOT CCMPLEii pending closeout review of the completed 6 6 A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
PAGE 184 PORC ITEM /> PROCEDURE 79-396 "SM 78-1838.1 Containment Wall-Mounted Jib Crane, PCN J. St. Martm present xs new proc ure to

~ra~ere guidelines for installation of the BK-1838 Wall-Mounted Jib Crane in Containment. The Ccxnmittee recommended approval of this new procedure. This item IS NOT GRPLETE pending closeout review of the completed ~p A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

79-728 %H 75-9.24, RWST Jet Shieldin Installation Rework PCN 79-1020. J. Brown present t proce ure or eletzon cause wo s been completed and procedure is no longer needed. The Committee reccanmended approval of this deletion. This item IS COMPLETE. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-763 %M 75-6.23 Servi.ce Water Redundant Return Line Su ort Assemblies Xnsta ation PQl - . s proc ure xs eing e et as t ie wo s en completed and the procedure is no longer needed. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

%M 75-50.31 Jet Shi.eldin Rework, Hain Steam and Feedwater, PCN 7 - . Ttu.s proce ure is ezng e et as t e wo . s een ccxn- ~p ete and the procedure is no longer needed.

A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary.

%M 76-01.1'Safe d Buses DC Control Volta e Moni.tor'CN 79-1117 This proce ure is ezng elet as e work s een completed and the procedure is no longer needed.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
PAGE 185

/i'ROCEDURE PORC ITEM WM 76-21.8 Reroute of Service Miter Su 1 to Batte Room Air Con itioner PCN - . is proce ure is being e et as e t wo een comp et and the procedure is no longer needed.

A Safety Evaluation was pexfoxmed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. WM 77-i@4.i, Reactor Coolant Seal B ass Modification, PCN is proce ure is being e ete as t e wo s en can-preter and the procedure is no longer needed. A Safety Evaluation was perforated and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. NM 77-1499.1 Rod Insertion Limit Cixcuit PCN 79-11&. This proc ure is being deleted as the work s been completed and the procedure is no longer needed. A Safety Evaluation was perfonaed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. is i' WM 77-1623.1, is Char ete as no longer needed. in e work Monorails PVii 79-1113. s en complete and This procedure the procedure

'A Safety Evaluation was performed and it was detexmined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessaxy. %M 77-1623.2 lled e Mashei Installation - Chai in Monoiail PCN - . e proce ure is ing e et as t e wo s en A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessaxy.

PAGE 186 PORC ITEH 8 PROCEDURE

""SH 77-1891.1'lectri.c Heat Tracin for Valves 82SA and 825B PCN -1 . The.s proc ure is bear@ de et as t e wo z has een com-pCete2 and the procedure is no longer needed.

A Safety Evaluation was performed and it possi'oility of an accident is not increased. A cnange was determined that the in the Plant Operating Technical Specifications is not necessaxy.

"-SH 78-1464.1'e lacement of Volume Control Tanlc Level Transmitters LT- an LT- , PM - . zs proce ure is ing e ete as t e wo z s een comp et and the procedure is no longer needed.

A Safety Evaluation was performed and it was detexmined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifica'tions is not necessary.

~SH 78-1464.2 Re lacement of Accumulatoi Level Transmitters LT-935 LT-9 , LT-9 , and LT- 9 PCN 7 -11 7. Thxs proce ure z.s bexng e et as t e wo s een comp et and the procedure is no long needed.

A Safety Evaluation was performed and it was detexmined that the possibility o an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.

%H 78-1890.2 Feedwater Line Drain Valves after the Containment C ec Ua ves, PCN - . xs proc ure xs ing eleted as t e wo s een comp eted and the procedure is no longer needed.

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessaxy.

~SH 78-2133.1,'alves 866A and 866B Modification for Testin PCN -1 . Thxs proce ure xs kg e et as e wor~ een com-Mp etecPand the procedure is no longer needed.

A Safety Evaluation was performed and it was detexmined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
PAGE 187 PORC ITEM ff PROCEDURE

%H 78-2273.1 Armor Plate on the East Mall of the Control Room.

This procedure is being deleted as the wo ~ has been completed and the procedure is no longer needed. A Safety Evaluation was perforated and it was determined that the possibility of an accident is not increased.' change in the Plant Operating Technical Specifications is not necessary. 79-839 "-SM 77-1431.3, Auxili Feedwater Plow Contiol B ass Modification Termination an C eckout PCN 7 -1 1 . J. Brown presented this proce ure c ange. It rquest ao.nor changes be made to agree with field change request.'he Committee recommended that the Peril Reason should read "to agree witn revised drawing" not "to agree m.t~ield change request". This is due to the fact that Engineering is taking cre of the draw'ng revision. The Coramittee reviewed and recommended approval of this procedure change with modifications. This item IS COtfPLETE. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-882 WN 77-1431.3'uxili Feedwater Flow Control B ass Modification Termination an Che <out PVil 7 -1 . J. Brown presented this proce ure c ange. It request t t minor changes be made to the procedure to agree with Buffalo Electric drawings t/12676-2R LX and 12676-3R D; Revision VIII. The Committee reviewed D,'evision and recommended approval of this procedure change. This item IS COt4'LKTE. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
I t I I.
PAGE 188 PORC ITEM i/ PPOCEDURE 79-893 WM 79-2449.1, Safe In ection Lo ic Modification, PCN 79-1278. C. Rioch present t s new proce ure to remve t e pressurizer low level coincident with pressurizer low pressure signal for automatic safety injection initiation and install a edified design which will initiate safety injection when any two out of three pressurizer low pressure signals are received. The Commit-tee determined that this procedure as written meets the test requirements of the design criteria. The Committee recommended approval of this new procedure. This item IS NOT COMPLETE pend-ing completion of this modification. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-924 %M 77-1431.3 Termination an Auxilia procedure change. C ec out It

. i - ..

Feedwater Flow Control B ass Modification Brown present requested that minor cbees be made to conform the procedure with the wiring diagrams. The Committee t s reviewed and recommended approval of this procedure c'nange. This item IS COMPLETE. A Safety Evaluation was performed, and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79 953 4M 77-1431.3 Auxili Feedwater Flow Control B ass ifodification Termination an C ec out PCN - . J. Brown present this proce ure change. It request t. t minor changes be made to correct wording and to correct typographical errors. The Committee reviewed and recommended approval of this procedure change. This item IS COMPLETE. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating TechnicalvSpecifications is not necessary.
PAGE 189 PROCEDURE %M 79-01.1 Feedwater Drain Liries Inside Containment PCN 79-1359. J. Brown presente t s new proce ure. It xs to esca. e t e steps necessary to install a drain line with end cap on each feedwater li at the low point inside of containment. The Committee reviewed and recommended approval of this new procedure. This item IS NOT COM-PU.TE pending closeout review of the completed procedure. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. ='SM 77-1660.50 RCS Ove ressurization Protection S stem Annuncxatzon PCN - . . Brown presente t s new procedure to t e Cortmn.ttee or review. The purpose of this new procedure is to provide instruction for the installation of the alarm circuit to monitor the alignment of the PORV's isolation valves (HOV-515 and tQV-516). The Committee reviewed and recommended approval of this new procedure. This item IS blOT COMPLETE pending closeout review of the completed modificator.on. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. ='SM 79-1662.1, Installation of Snubber Platform PCN 79-1510. J. Brown presented thzs new procedure to the Committee or review. The purpose of this procedure is to provide the guidelines ,necessary for installing Snubber Maintenance Platforms. The Committee reviewed and recerrended approval of this new procedure. item IS NOT COMPLEZE pending completion of the rxdification. 'his A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. -SM 79-2449.2,'i.stable PC-449B, Control Channel Chan e Fxe C an e Re uest t/ PCN - . J. St. Hartm presented t zs new procedure to provide the steps necessary for inter-changing the PC-449B bistable to actuate on Channel 431 which will interlock PCV-431C independently from W9; the normalof this controlling channel. The Committee recommended approval new procedure. This item IS NOT COMPLEZE pending closeout review of the completed procedure. A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary.
1 PAGE 190 PORC ITEM I/ PROCEDURE 79-1093 JGlf 77-1660.50, RCS Ove ressurization Protection S stem c1.a ion ~

- . . pew presen s procedure c ge. reques t Step 5.10 be N/A'd for 0-7 as after discussion with the Operations Section it 0-7: The Committee reviewed and recommended approval of this shows no need to revise procedure change. This item IS COMPLEZE.

A Safety Evaluation was performed and ssibility of an accident is no't increased. A change

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it was determined that the in the Plant rating Technical Specifications is not necessary.

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79-1141 "SM 79-1837.1 Com uter Room Ceilin 'CN 79-i7i2. J. St. Martin presen e s new proce ure. z.s o prom. e guidelines for installing a fire-rated ceiling in the computer room. The Committee reviewed and recomended approval of this new procedure. This item IS hOT COMPLETE pending closeout review of the completed procedure. A Safety Evaluation was performed and ssibility of an accident is not increased. A change it was determined that the in the Plant crating Technical Specifications is not necessary. 79-1145 "SM

'dl' %

78-1875,2; "A" Feedwater Venturi Monorail Installation of Hoist pew presen e the "A" Feedwater Venturi Monorail. The Committee reviewed and xs new proce ure. 1 I is

' pro-recommended approval of this new procedure.'his item IS NOT CQMI?LheE pendrng closeout review of the completed proceoure.

A Safety Evaluation was performed and ossibility of

~

an accident

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it was determined that the is not increased. A change in the Plant crating Technical Specifications is not necessary.

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79-1148 -L. Depew presented the following procedures for deletion as the proce ure has been completed: SM 75-.5.38'tandb Auxili Feedwater S stem 0 erational Testin A Safety Evaluation was performed and possibility of an accident is not increased. A change it was determined that the in the Plant Operating Technical Specifications is not necessary. SM*75-5.39 Standb Auxili Feedwater S stem Rewod'CN 79-1729. A Safety Evaluation was performed and it was determined that the ssibility of an accident is not increased. A change in the Plant

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crating Technical Specifications is not necessary.

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PAGE 191 PORC ITEM e SH 75-5.41 Standb Aiixili Feedwater Cable and Conduit Instal-latzon Rewor PCN A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SM 75-5.42 'lectrical Installation and Cable Termination Rework or Air Han zn Units PCN A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. Shf 75-5.43; Rework of Standb Auxili Feedwater S stem PCN A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SM 75-5.44, Rework of SAHP Seal Pi in PCN 79-1725. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SM 75-10.28 Service Water Pi Aux>.lx i to Ai.r Handlin Units Bm in A dition Rework, PCN -17 for A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SM 75-34.23, Pi. e Restraints and Jet Shields Rework for Steam Generator B ow own xnes PCN A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
PAGE 192 PORC ITEN ff PROCEDURE SH 77-1660.50, RCS Ove ressurization Piotection S stem Annunciation PCN The Committee reviewed and recommended approval of these procedures for deletion. This item IS COI~IPLEZE. A Safety Evaluation was'performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-1416 <SM 77-1850.1', Fire Barrier Penetration Seals Installation PCN 7 - . C. Roc present thxs new procedure to pro~ e t e Bzrectzons necessary to install and properly document fire barrier penetration seals and to upgrade existing fire barriers to meet present Technical Specification requirem nts. The Committee reviewed and recommended approval of this new procedure. This item IS NVT COIPLEIK pending closeout review of the completed

;-.a %

A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-1683 'ISM 79-1837.2; Fiie Doors Installation, ?CN 79-2589. J. St. Hartin presented t is new proc ure to the Cotimn.ttee r review. The purpose of this procedure is to provide the guidelines for removing existing plant doors and replacing them with fire-rated frames, doors and associated hardware. The Committee reviewed and recommended approval of this new procedure. This item IS NOT COHPIZIE pending closeout review of the ccmpleted modification. A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary. 79-1693 'ASM 79-2603.1 Pressurizer Safe Valve Direct Position Indicator PCN . I' . St. Martxn present t s new proce ure. e

~p* install LVDT and 8 g'dl'o associated equipment for monitoring and alarm-ing pressurizer safety valve position. The Committee reviewed and recommended approval of this new procedure. This item IS NOT CO~PIZfE pending closeout review of the completed procedure A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary.

PAGE 193 PORC ITEM i! PROCEDURE 79-1694 'SH 79-2603A.1, Pressuri.zer POPU Direct Position Indicator to Cora uter, PVl 7 - . J. St. Hartin presente thxs new procedure. e purpose o t xs new procedure is to provide the instructions necessary for installation of the equipinent for detecting PORV valve position and monitoring and alarming via the plant ccmputer. The Committee reviewed and recommended approval of this new procedure. This item IS NOT CO!O'LETE pending closeout review of the completed procedure. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-1695 ~9M 79-2604.1 RCS Subcoolin Nar in Monitor' stem PCN 79-2630. J. St. Nartm presente the.s new proc ure. The purpose o xs new procedure is to provide the guidelines necessary to install the RCS Subcooling ifargin Monitoring System. The Committee reviewed and recommended approval of this new procedure. This item IS bVZ COMPLETE pending closeout review of the completed procedure. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. 79-1700 SN 79-01.1, Feedwater Drain Lines Inside Containment, PQ1 79-2638. As t e m z xcatzon as comp ete an c os out. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary. SM 77-06.2, Low Pressure Purification S stem Yodification - H dro-stats.c Test PCS - . As tne proc ure ~s comp ete. A Safety Evaluation was performed and it was determined that the possibility of an accident is not increased. A change in the Plant Operating Technical Specifications is not necessary.
PAGE 19~ PORC ITEM P PROCEDURE Stt 77-06.3'ow Pressure Purification S stem i4fodification, PQl 7 - ~ As t e procedure is ccmplete. The Committee reviewed and recommended approval of these procedures for deletion. This item IS COMPLETE. A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary. 79-1715 '6M 77-1836.2'elocation of Halon S stem PCi'1's 79-2611 and 79-2616 L. Depew present t ese proce ure c anges. ney requested t at minor changes be made as relocation of the Halon System will be administered by RGK instead of Bell/Schnieder as originally planned and to update the procedure. The Cpu.ttee reviewed and recommended approval of these procedure changes. This item IS CEETE. A Safety Evaluation was performed and it was determined that the in the Plant possibility of an accident is not increased. A change Operating Technical Specifications is not necessary.}}

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