ML19030A324

Submit Monthly Operating Report for the Month of August 1978 for Salem No. 1

ML19030A324
Person / Time
Site:	Salem
Issue date:	09/12/1978
From:	Midura H Public Service Electric & Gas Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML19030A324 (15)

Text

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PS~G e RESUl.ATORY DOCKH n!I !IY Public Service Electric and Gas Company P.O. Box 168 Hancocks Bridge, New Jersey 08038 Salem Nuclear Generating Station September 12, 1978 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir:

MONTHLY OPERATING REPORT

\.:.-**,

SALEM NO. 1 DOCKET NO. 50-272 In compliance with section 6.9, Reporting Requirements for the Salem Technical Specifications 1 10 copies of the following monthly operating reports for the month of August, 1978 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Summary of Safety Related Maintenance Operating Summary Refueling Information Sincerely yours, 11fr'~,

H. J. Midura Manager - Salem Generating Station LKM: jcm cc: Mr. Boyce H. Grier Director of U. s. NRC Off ice of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pa. 19406 Director, Office of Management Information and Program Control moa-T:P:srs-:f Nuclear Regulatory Ccrmnission

~ington, D.C. 20555 Enc W1mn*1rn Page l of 8-l-7.R4 95-2189 (4M) 3-78

AVERA.GE DAILY lI'ffT PC'iE~ LEVEL

• DJCKET i\0.50-2 72

~~-'---~~~~~

UNIT Salem No. 1 DATE.September 12, 1978 CG*lPLETED BYL. K. Miller TELEPHON.t 609-365-7000, X507 MONTH August 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL a.iwe-NET) (Mlvc-NET) 1 743 17 1073 2 1069 18 1092 3 1053 19 1076 4 1062 20 11 2 5 1038 21 _:373 6 948 22 7 925 23 313 8 496' 24 783 9 1022 25 9 10 1066 26 1002 11 1053 27 535 12 1092 28 0 13 1077 29 117 14 1071 30 968 15' 1045 31 1060 16 959 Pg. 2 of 15 8.1-7.Rl

.e IXX::XEr ro. :_5_0....-......

2....1...2_ _ _ _ __

~: Seotern.be.r 12:,_ 19}8 a::M?LEm) BY: L.. K. Mi lier TEU:PB:m:: 609-365-7000, X507

i. Onit Nana:.* Salem* No. 1 .

Notes *. -

2. Repc:rrt:i.nq* Peric:d:_A_u ....g.._u.-.s~t....;;;;1~9-.7.-8__.;._ _ _ _ __

3. Licensed 'lllema.l Pc7.er* (mt) : _ _ _ _3_3_3_8 _ _ __

4. Ncmep.late Ratinq (Gross. !fie): _ _ _ _'!:"'1~1~3~5_ _ __

s. Design Electrical. Ratinq (Net !fie): _ _1_0_9_0_ _ __

6 *. Maximum Dependable capac:ity (Gz:css:,~): 112 4

7. Maxilllllm: lJet'endable capacity* (Net~): _1_0_7_9_ _ __

---

a. If. Changes Occur in capacity Ratings. (Items Nul!Cer 3 Thl:co;h 7) S.ince Last P.eport, Give Reason:.

None 9.

.

lO.**

J?ower I.eveJ. To Which* PSstricted, If Reasons For P.estrictions ;. I f Arr:!~

_ _______________________

Arr:f* (Net .i.tiel :.*_._N

__.;.;.;;..;;.

None

....n;.;..;;.e_ _ _ _ _ _~-----------

....o

~-

. '!bis M:lnth Year to Date Cumulative 744 5,831 10,272 lL. - Hours' In P.e!;Crtinq Peric:d

12. Nlll!i::er. Of HCtJrs . .Reactor Was Critic:al 656.3 3,257.8 5, 801. 0

u. Reactor Reser.le Shuteewn Hours . 0 0 0 l4. Hou.rs. Generator On-Line, 648.8 3,069.0 5,499.6

15. Oriit P.eserve Shutdown Hours 0 0 0 l6. GJ:CSs. 'Ibmnal. Ene?:gy* Generated (Mora) 1,989,124.8 9,157,994.2 15,853,214.2 l7 *. GJ:CSs El.ectr.i.cal. . Ecergy Generated(Kola) . .657,860 3,084;350. 5,270,660 lS. Net Elect:rical. Energy Generated (Mta)

...

626,775 2.,919 ,291 4,977,509 l9. Unit Service Factor 87.2 52.6 53.5 20., Unit AvaiJahility_Factcr . 87.2 52.6. 53. 5 2l. Unit capacity Factcr (Us.inq *MOC Net) 78.l 46.4 44.9 22~ Unit capacity Factor. (Using DER Net)_. 77.3 45.9 44.5 23 *. Unit Forced Ol.It:age Rate 12.8 47.4 36.2

• 24.

• ShiltdcwriS Scheduled over Next 6 ~ *(Type, Date, and Duration o£ Each.> :

. .

25. If Shut. Down At End of Report Peri.Odr Estimated Dii.te of* Startup: ._ _ _ ___.;._ _ _ _ _ _ _ _ _ __

26. Onits* In Test Status (Prior**tc camerc:ial <:peraticn): *

• • Forecast. Achieved 9/30/76 *12/11/76 11/01/76 12/25/76 8-l-7.R2 Pg. 3 of 15 12/20/76 6/30/77

UNIT SI IU'l'IU'INS mID 1'F.R REOOCfIONS DOCK~~T NO. : 50-272 REPORT MJ1'm1 August, 19 7 8 UNIT:Ni\ME: Salem #1 D/\TE: September 12,' 1~78 COMPJ,ETED DY: L. K. Miller TELEPHONE: 609-365-7000 X507 MlITIDD OF OOFJ\TION SHlJITING LICENSE SYSTEM cx:t1I'CWENT CJ\USE J\ND rnrmocrIVE NO. D/\TE TIP El (HOURS) RE1\9'.JN2 IXMN EVEN!' rnoE'1 CODES J\CTIOO TO RFJ\CTOR REPOin' I PREVENI' RFilJRP.ENCE 78-100 8-1-78 F 0 B 4 --- HH FILTER Clean Steam Generator Feed Pump and Condensate Pump Suction Strainers.78-108 8:::5....:78 F 0 A 4 --- ;

HH FILTER Clean Condensate Pump Suction Strainers.

78-115 8-7-78 F 0 A 4 --- HH FILTER Clean Steam Generator Feed Pump Suction Strainers and repair,

1. 11 Recirc. Valve.

'78-116 8-8-78 F 0 A 4 --- HH TURBIN Turbine vibration caused by Governor Valve going open (due to blown 0-ring on EH,Oil Line) .78-129 8-15-78 F 0 A 4 --- HC HTEXCH 12A Condenser leak.

l 2 3 4 5 F: Forced Peason: M3thod: Exhibit G - Instructions F.x.hibi t 1-Sane Si Scheduled 1\-Equiprent Failure (Explain)  !-Manual for Preparation of Data Source B-Maintenance or Test 2-Manuai Scram. Entry Sheets for Licensee C-Refueling 3-Autanatic Scram. Event lleport (LER) File D-Regulatory nestriction 4-0ther (Explain) (NIJREX}-0161)

E--operator Training & License Examination F-1\dmlnistrative 8-l-7.R2 ~rational Error(Explain) Load Reduction II-Other (P..xplain)

Pg. 4 - 15

l UNIT smmx:mNS 1\ND PCMER IlEOUCTIONS DOCKET NO.: 50-272

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REPORI' IDHI'H August' 19 7 8 UNIT NAME: Salem #1 DATE: S*eptember 12, 1978 COMPLETED BY: L.K. Miller TEIJEPllONE: 609-365-7000 X507 METHOD OF DURATION SHUITING LICENSE SYSTEM COMPONENT CAUSE AND CORRECTIVE DATE 1 2

<XlDE4 NO. TYPE (HOURS) IlEASON IXMN EVEN!' CODES ACfION 'ID REI\C'IDR REPORT II PRE\IENI' REOJRRENCE 78-137 8-21-78 F 45.75 G 1 --- IA PUMP XX Reactor trip due to loss of Reactor Coolant Pump.

1. 12 Reactor Coolant Pump breaker was manually opened.78-138 8-23-78 F 0 A 4 --- HH FILTER Clean #11 and #13 Condensate Pump Suction Strainers.78-141 8-24-78 F 0 A 4 --- HC HTEXCH #llA Condenser leak.78-142 8-24-78 F 0 A 4 --- HC HTEXCH #llA Condenser leak.78-145 8-25-78 F 0 A 4 --- HC HTEXCH #12A Condenser leak.78-154 8-27-78 F 49.43 H 3 --- HA TURBIN Reactor trip due to a Maintenance error on the part o*f outside contractor causing turbine trip Page 5 of 15 ll'-1-'7.Rl

• DOCKET NO.: 5Q-2:Z2

. MAJOR

'

PLANT MODIFICA'9Ns UNIT -~1E: Salem I REPORT MONTH August 1978 Septei:nber 12, 1978 DATE:

COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000, X507

• DCR NO. PRINCIPLE SYSTEM SUBJECT l-ED-0364 Service Water Install Modified No. 14 s .w.

Pump l-ET-0400 4 kv Bus u.v. Relays Install Temporary D. c. Feed l-EX-0402 Circulating Water Determine Reduced c.w. Flow by Throttling Discharge V~lve l-OD-0048 Waste Liquid Replace Saunders Valves with Full Flow Plug Valves I,

'

• DESIGN CHANGE REQUEST Page 6 of 15 l_ 8-1-7.Rl

DOCKET NO.: 50-272

.=.,:._....-...-....~~~~~~-

MAJOR PLANT MODIFICAT~S Salem I UNIT,~:

IU:'PoRT MONTH August 1"'8 ATE: *September. 12, 1978 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000, X507

• DCR NO. 10CFRSO. 59. SAFETY EVALUATION l-ED-0364 Setpoint change required to comply with new s.w. Pump performance curves. The change does not degrade system performance.

l-ET-0400 Addition of noise suppressor will not affect safety function of the relay. Safety analysis are not affected.

l-EX-0402 The implementation of this experiment does not affect any presently performed safety analysis nor does it create any new hazards. The basis of the Technical Specifications are not affected.

l-OD-0048 This DCR requests the substitution of plug-type valves for diaphragm-type valves. This change does not increase the probability or consequences of an accident, create a possibility for an accident or malfunction or reduce the margin of safety as previously defined.

• ---. ... ~

• nESIGN CRAJ.'1GE .RF.QUEST Pa e 7 of ls

DOCKET NO.: 50-272

~~~~~~~~~~~~-

SUMMARY

OF SAFETY RELATED 'INTENANCE UN IT N~:~_s_a_l_e_m~#_l~~~~~~~-

Maintenance DATE: September 12, 1978 COMPLETED BY: L.K. Miller REPORT MONTH August, 1978 TELEPHONE: 609-365-7000 ( X507)

WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

MD-2939 11RC17 Valve Packing leak. Tightened packing.

1. 14 Service MD-2918 Water Auto Breaking shear keys. Replaced bottom wear Strainer shears and keys.

OD-10033 #12 Service Broken shear keys. Replaced shear keys.

Water Strainer MD-2781 Cask Handling Worn cable. Replaced cable.

Crane OD-8878 lDDC #27 Check for ground. Replaced limit switch.

Breaker

,

- - -- - - -- - - *-

MD-2916 Containment Failed leak test. Adjusted locking device.

Air Lock Inner Door -- - --

"

OD-9481 Service Water Pipe leak. Installed temporary Piping patch.

c OP-9431 Service Water Pipe leak. Installed temporary Piping patch.

-

OD-9527 #16 Service Broken shear key. Replaced distributor barrel Water Pump 0-ring and shear key.

Strainer --

OD-9909 13MS168 Valve Packing leak. Packing tightened.

OD-9474 #11 Chiller Leak. Replaced tubing reducer to Unit condenser.

OP-9885 12SW23 Valve Valve leak. Applied temporary patch and clamp.

--

-- -

OD-9535 #11 Service Housing leak. Temporary patch installed.

Water Pump

~ -- - Strainer 8-1-7.Rl Page 8 of 15

DOCKET NO.: 50-272

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UNIT N~: Salem #1 sriMMA.RY. OF SAFETY RELATED .lrNTENANCE DATE: September 12, 1978 Performance COMPLETED BY: L. K. Miller REPORT MONTH August, 1978 TELEPHONE: 609-3£5-7000 (X507)

WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

PD-4930 13RC431C Verify setpoint. Adjusted calibration of Tavg.

PD-4934 1PM505B Summa tor failed low. Replaced summator.

PD-4937 1PC526C Verify setpoints. Adjusted trip and reset points.

PD-4939 1PT536A/B Trips 8rnv high. Adjusted output #2 setpoint, PD-4944 1LC461A/B Verify setpoints. Adjusted setpoints.

PD-4902 11 Steam Stearn flow failed low. Repaired faulty Generator Steam connections on-the PCB Flow Channel II - - - ---* - - *-- - --Elco connector.

PD-4904 1TM441E High trip point. Adjusted trip points. - -

PD-4917 1FC511A/B Low setpoint. Adjusted setpoint.

PD-4920 14 Steam Out of calibration. Installed and calibrated Generator -* -* new PCB transmitter.

1LT549 11 Boric Acid PD-4926 Low setpoint. Calibrated.

Tank level 1LT106~

PD-4927 12 Batt. Level High transmitter Calibrated.

1LT102. output.

OD-9388 A.F.D. Recorder Out of calibration. Recalibrated recorder.

XA-8740 .

OD-9384 #13 Steam Verify stable operation .Recalibrated transmitter.

Generator Level .. *- --.

Page 10 of rt:;

8-1-7.Rl

DOCKET NO.: 50-272 SU~Y OF SAFETY RELATED IINTENANCE UNIT N~:~~-S-a_l_e_m~#-1~~~~~~

DEPARTMENT Maintenance DATE: SEi.ptember 12, 1978

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REPORT MONTH August, 1978 C0 MP LET ED BY: L.K. Miller

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TELEPHONE: 609-365-7000(X507)

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WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

OD-10051 #16 Service Strainer trips. Replaced moter, seals, Water Pump and fittings.

Strainer MD-8956 1CC190 Motor malfunctioning. Replaced motor.

'

OD-10124 13RC26 Valve Packing leak. Tightened packing nut.

MD-2951 Airlock Door Door leaks repacking Replaced two cam followers needed. and two inner door gaskets

-

MD-2851 4kV Group UF Relays causing trips. Replaced relays.

Relays lH and lF OD-10077 11MS169 Valve Valve leaks through. Replaced stem and seat disc.

-**

..

MD-2892 lA Diesel Spike on D.C. feed. Replaced power supply.

Controls" OD-9569  :#.T2 RHR Room ..

• Service Water leak. Repaired plugs in coil.

Cooler MD-2846 13CV78 Valve Bonnet leak. Furmanited valve.

OD-10099 13MS168 Valve Packing leak. Furmari+/-ted*~ackirig *gland.

• . - ..

...

.

..

OP-0311 #14 Service Replace pump. Removed and installed Water Pump rebuilt pump.

MD-2944 1CC190 Valve motor operator Replaced operator.

malfunctioning.

OD-10068 #13 Service Inch pushbutton not Cleaned threads and hole Water Screen working. on shaft.

• Page 9 of is* _,...

8-1-7.Rl

DOCKET NO.: 50-272 SUMMA'RY OF SAFETY RELATED IINTENANCE UNIT N~: Salem #1 DATE: September 12, 1978 DEPARTMENT Performance COMPLETED BY: L.K. Miller REPORT MONTH August, 1978 TELEPHONE: 609-365-7000 (X507)

WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

OD-9377 # 11 Steam Gen. Verify stable Replaced comparator and Low Low Level operation. calibrated 1LC518A/B.

OD-9337 #12 Boric Acid Hi-Low Temp. Alarm is Inserted fuse.

Tank, illuminated.

OD-9117 Safety Inject. Calibrate 11 and 12 Recalibrated-LT-934A, Accumulator Accumulator level. :Gf.r.,...9 35A ,_LT-9 35B, LT-9 34B.

OD-9260 Safety Inj-ectior Channel A shows Repaired sticking 11 .. Accum.Ch.A increase while Channel indicatoL~eplaced strain B is constant. gauge.

OD-9291 Safety Injection Channel A erratic. Repaired and -recalibrated

1. 11 Accum. indicator.

Page 11 of 15 8-1-7. Rl

SALEM I OPERATING

SUMMARY

• AUGUST 1978 8-1 Unit load was reduced to 50% to clean feed pump suction strainers. At 0900 a load increase was started and the unit reached full output at 2200. The unit remained at full load until 8-5.

8-5 At 2124 a load reduction to 70% was initiated in order to clean condensate pump suction strainers.

8-6 The unit returned to full load at 1200 and operated there the remainder of the day.

8-7 At 1455 a load reduction was initiated in order to clean feed pump suction strainers. At 2400 the unit was at 45%

load.

8-8 At 0030 the unit was at 40% load. At 0400 unit load reached 52%. This level was held while repairs were made to a feed pump recirculation valve. A load increase was started at 1200 but was terminated at 1448 due to turbine vibration.

Load was decreased from 62%-to 55% while the problem was analyzed. The vibration was caused by the failure of a turbine governor valve to open. The cause was a blown 0-ring in the E-H oil line. Repairs were made and a load increase was started at 1900.

8-9 The unit reached full load at 0642. The unit remained at full power until 8-15.

8-15 At 2045 a load reduction at 15%/HR. was initiated because of condenser tube leaks. Load was stabilized at 70%.

Page 12 of 15 i_

8-16

• At 0330 a load increase was initiated at 5%/HR. The unit reached £ull load at 1000. The unit remained at £ull load until 8-21.

8-21 At 0312 load was decreased to 97% due to condenser tube leaks. At 0915 a Reactor/Turbine Trip occurred £rom £ull load. The trip was caused by a loss 0£ reactor coolant flow when a reactor coolant pump breaker opened.

8-23 The unit was taken critical at 0355. The delay in going critical was caused by repairs that had to be made to an inoperable £an coil unit. The unit was synchronized at 0700. A load increase was initiated and the unit reached 70% at 2000. The unit was held at this level while condensate suction strainers were cleaned. The load increase was continued at 2230.

8-24 The unit reached £ull load at 0600. At 0713 a load decrease was initiated due to high condenser backpressure.

Load was reduced to 78%. At 1155 load was £urther reduced to 70% when a circulator was removed from service. A load increase was initiated 2040.

8-25 The unit reached full load at 0300. At 0424 load was reduced to 90% due to condenser tube leaks. At 1022 power was increased to £ull load. At 1648 load was reduced to 91% in .order to remove a circulator from service.

8-26 At 1050 power was increased to full load and the unit operated at this level all day.

8-27 At 1257 a reactor/turbine trip occurred £rom £ull load when an outside contractor dropped an air horn on the turbine trip block.

Page 13 of 15

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8-29 The unit was taken critical at 1000.

• The delay in going critical was due to repairs to a containment fan coil unit, contai~ment air lock door, lA Vital Bus Instrument Inverter and the rod control system. The unit was synchronized at 1425 and at 2400 load had increased to 63%.

8-30 The unit reached full load at 0800 and remained at full load for the day.

8-31 The unit was at full load for the day.

Page 14 of 15

• REFUELING INFORMATION .

• DOCKET NO.: 50-272 UNIT: Salem No. 1 DATE: Septeinl5er 12 ~.1978 COMPLETED. BY: L.K. Miller TELEPHONE: 609-365-7000 X507

-

MONTH: August, 1978

l. Refueling information has cha."'lged from last month:

YES X NO

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2. Scheduled date of next refueling: March 31, 1979

3. Scheduled date for restart following refueling: May 26, 1979

~---------~

4 .. A. Will Technical Specification changes or other license

• amendments be required? YES NO _ __

NOT DETERMINED TO-DATE August, 1978 B. Has the reload fuel design. been reviewed by the Station Operating Review Cammi ttee'? YES NO X If no, when is i t scheduled?

5. Scheduled date(s) for submitting proposed licensing action:

February. 1979 if reg:ujred, 6.*

• Importan.t licensing considerations .associated with refueling:

None

7. Number of Fuel Assemblies:

A. In-Core 193 B. In Spent Ftiel Storage

• 0

8. Present licen~ed spent fuel storage capacity: 264

~-----------~

Future spent fuel storage capacity: 1 170

--~-=-:~------~

9. Da.te *of last refueling that can* be discharged to the spent. fuel pool assuming the present licensed capacity:. i:\pril, 1982

• ~....._. .

Page 15 of 15 8-l-7.R4