ML20202G803
| ML20202G803 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1985 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8604150013 | |
| Download: ML20202G803 (23) | |
Text
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. ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT UNIT 1 - ANNUAL REPORT REQUIRED BY 10CFR50.59 (1985)
Section 50.59 of Part 50, Licensing of Production and Utilization Facilities, of the regulations of the United States Nuclear Regulatory Commission, states that the holder of a license authorizing operation of a production or utilization facility may (1) make changes in the facility as described in the safety analysis report, (2) make changes in the procedures as described in the safety analysis report, and (3) conduct tests or experiments not described in the safety analysis report, without prior commission approval, unless the proposed change, test or experiment involves a change in the technical specifications incorporated in the license or an unreviewed safety question (as defined in 10CFR50.59).
The licensee is required to maintain records of such changes, tests or experiments, and these records are required to include written safety evaluations which provide the basis for the determination that the change, test or experiment does not involve an unreviewed safety question.
Brief descriptions and a summary of the safety evaluations of the changes, tests or experiments as described above which were completed in 1985 for the Joseph M. Farley Nuclear Plant Unit 1, are provided in the following pages.
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Subject:
Cycle 7 Reload Safety Evaluation
Description:
h e Unit 1 Cycle 7 fuel reload consisted of 2 Region 4A, 2 Region 7, 77 Region 8, and 76 fresh -
Region 9 fuel assenblies. 'Ihe 2 Region 4A bundles are two OpHmimi Fuel Denonstration Assenblies (OFDAs) which are being reinserted in Cycle 7 fran the spent fuel pool for further irradiation. A total of 672 fresh standard burnable poisen rodlets were utilized in clusters of 4,12, and 16 rodlets. All of the asserblies used in Cycle 7 have antianag grid designs except for the two OEDAs.
Eblicwing return to power, it was discovered that a misload had occurred involving one of the OFDAs and another spent fuel assenbly.
Safety Evaluation: A Reload Safety Evaluation was conducted by Westinghouse. The reload design was found to be in cmpliance with current Technical Specificaticms and to involve no unreviewed safety questions per 10CFR50.59. 'Ihis safety evaluation was later detennined to be inadequate (See ler 86-003-00 Ibcket No. 50-348).
Folloving determiration that a misload had occurred, this condition was evaluated and determined to have ro safety significance.
PORC Review: PORC Meeting 1368,3/21/85 '
PORC Meeting 1419,8/8/85 PORC Meeting 1431,9/10/85
Subject:
ENP-1-AOP-2.0, 'ICN SA Dascriptio'u The final Safety Analy99: Repnrt indicates that the stean generator blowdown isolation valves close autanatically cn a high radiation signal fran radiation monitor R-19 in adiition to signals from R-23A and R-23B. This is contrary to design drawings and actual tests which -indicate that these valves do not close on a signal fran R-19. This procedure was changed to reflect the actual design l
of the plant.
l Safety Evaluation: This change was made to reflect the existing design of the plant. '1he existing design was determined to be the proper design.
PORC Review: PORC Meeting 1450,11/7/85 l
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Subject:
FNP-0-AP-2, Revision 9
, ,- " Plant Operations Review Constittee"
Description:
Revised procedure to show new membership of the !
Plant Operations Review Committee (PORC) due to plant management changes and made minor changes in f the review requirements of the PORC.
Safety Evaluation: %ese changes increase the effectiveness of the PORC and plant management.
PORC Review: PORC Meeting 1370, 3/28/85 l
Subject:
FNP-0-AP-3, Revision 4
" Plant Organization"
Description:
Revised procedure to show the new plant management and changed the educational requirements of the Systems Performance Supervisor.
Safety Evaluation: Wese changes increase the effectiveness of the plant management.
PORO Review: PORC Meeting 1370, 3/28/85 l
Subject:
ENP-0-AP-45, Revision 5 l "Farley Nuclear Plant Training Plan" i
Description:
Revised procedure to not allow exempting operators from annual retraining base 1 on the previous year's examination performance.
Safety Evaluation: This change increases the effectiveness of the training program.
PORC Review: PORC Meeting 1371, 3/29/85 I
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Subject:
ENP-0-HIP-1.0, Revision 10
Description:
W is procedure provides the method used to retove the reactor vessel head during refueling. Wis method involves renoving the reactor vessel head and placing it cm the storage stand prior to flooding the refueling cavity. Wis is different frcan the procedure described in the Final Safety Analysis Report in which the head is raised while sinultaneously flooding the cavity.
Safety Evaluation: This method reduces the radiaticm exposure involved by slortening the duration of the job. We extranely difficult coordinaticn effort of raising the head and cavity level simultaneously is
' eliminated. We time the head is suspended from the polar crane is reduced.
i PORC Revies: PORC Meeting 1400, 6/18/85
Subject:
FNP-0-MiP-3.1, Revision 9, 'ICN OB
Description:
We Final Safety Analysis Report states that new fuel assenblies are moved in the new fuel area by use of the new fuel assa bly handling fixture suspended from the new fuel hoist. m is procedure change allowed for the use of slings to lift a dropped fuel assenbly from the horizcntal position since the handling fixture could not be used.
Safety Evaluation: We handling of a single damaged unburned assaibly
< is safe from a criticality standpoint. We undamaged assetbly is the nost reactive gecar.etry, i.e., the asseibly will not become significantly more reactive if it is further deformed when it is lifted and placed in the shipping container.
PORC Review: PORC Meeting 1458,11/26/85 3
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Subject:
INP-1-SOP-50.0, Revision 18
Description:
During a review of this procedure, it was found that the Waste Evaporator feed Pump and Floor Drain Tank recire valves were listed as " locked 1 throttled" which was contrary to system drawings and the Final Safety Analysis Report (FSAR). Upon investigation it was found that " locked throttled" was the desired condition and that the system drawings and FSAR should be changed. Further, this revision changed the normal required positions for
' the following valves from " locked open" to " locked throttled":
' Waste Evaporator Concentrate Tank pump recirc valve
' Chemical Drain Tank pump recirc valve Laundry and Hot Shower Tank pump recirc valve 1
! Safety Evaluation: The purpose of the recirc path is to provide mininum flow protection for the pumps and recirc mixing. According to startup test procedures, the recirc valves for all waste processing system pumps j should have been throttled to obtain a nominal recire flow sufficient for pump protection and recirc mixing.
PORC Review: PORC Meeting 1350 2/8/85 i
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Subject:
INP-1-SOP-50.0 Revision 18, EN 18C
Description:
Changed the normal required positions for the Reactor Coolant Drain Tank (RCDP) pump discharge manual isolation valves and the RCUT pump recirc orifice outlet isolation valve from " locked open" to " locked throttled". Having these valves in the locked open position has resulted in the RCUT pumps exceeding design flow. Also, having the recire valve wide open was causing insufficient head for transfering tank contents through the discharge path.
Safety Evaluation: W e valves have been throttled to conform with pump design and pre-operational testing results.
PORC Review: PORC Meeting 1389, 5/14/85
Subject:
PCR/PCN 78-209 (S78-1-209)
Description:
Installed two additional pressure gauges to measure Boron % ermal Regeneration System (BTRS) chiller pump suction pressure.
Safety Evaluation: The pressure range of the existing gauges was too high to accurately determine pump suction pressures.
PORC Review: PORC Meeting 1387, 5/7/85
Subject:
PCR/PCN 79-449 (B79-449)
Description:
Made several changes associated with the concentrated waste storage tank to reduce personnel exposure.
Safety Evaluation: Wese changes in no way adversely impact the safety of the plant since the system is not a safety system, nor does it impact a safety system.
PORC Review: PORC Meeting 826, 6/02/81 PORC Meeting 995, 6/15/82 PORC Meeting 1010, 7/27/82 1
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subject: PCR/PCN 79-566 (B79-566 & SE79-566)
Description:
Added P.A. speakers, amplifiers and new flashing I beacon lamps in the Auxiliary Building and the 4 Containment Building.
Safety Evaluation: 'Ihese additions improve plant emergency evacuation alarm coverage and satisfy a ccanitment made to the NRC in IE Bulletin 79-18.-
i PORC Review: PORC Meeting 590, 8/21/80 PORC Meeting 611, 9/23/80
PORC Meeting 987, 5/18/82
Subject:
PCR/PCN 81-975 (S81-975)
Description:
Added a service water standpipe with a surge tank to provide backpressure on the service water system and removed existing backpressure control valves Q1P16v559A and B.
Safety Evaluation: The standpipe and surge tank were seismically qualified to protect adjacent class IE electrical l
equipment; however, the standpipe and surge tank are in a non-seismic portion of the service water
] system. Operability of the service water system is i
not contingent upon the standpipe and surge tank i
since, by transferring to pond recirc mode and bypassing the non-seismic portion of the system, ,
adequate system backpressure is maintained. l
- PORC Review: PORC Meeting 1200, 1/10/84 PORC Meeting 1204, 11/24/84 j l
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Subject:
PCE/PCE 81-0-1037-1A-132 (SM81-0-1037-1A-132)
Description:
Installed pre-action sprinkler system 1A-132 in i
auxiliary building room 107 to facilitate use of l this room as an occasional combustible materials ;
' storage area. Also the room boundary was upgraded l to a 3-hour fire rating.
I Safety Evaluation: This design was evaluated for its effect on other systems and was found not to interfere with or degrade other installed systems.
PORC Meeting 1443, 10/10/85 l PORC Review:
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Subject:
PCR/PCN 81-0-1037-1A-134 (SM81-0-1037-1A-134)
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Description:
Installed pre-action sprinkler system 1A-134 to cover auxiliary building rooms 601, 602, 603, 2601, 2602, and 2603 to facilitate use of these rooms for
.t occasional combustible materials storage.
j Safety Evaluation: his design has been evaluated for its effect on other systems and has been found not to interfere 1
with or degrade other installed systems.
1 PORC Review: PORC Meeting 1443, 10/10/85 l
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Subject:
PCR/PCN 81-0-1037-603 (B81-0-1037-603)
Description:
Upgraded rooms 601, 602, 603, 2601, 2602, and 2603 to be a common three hour rated fire area for use i as a combustible materials storage area.
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Safety Evaluation: h is design has been evaluated for its effect on other systems and has been found not to interfere i
with or degrade other installed systems.
PORC Review: PORC Meeting 1415, 8/1/85 I
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Subject:
PCR/PCN 81-1167 (S81-0-1167)
Description:
Piping and associated valves were added in order to
' connect the Unit 2 Service W. tar standpipe inlet to
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the fire pump suction header.
Safety Evaluation: h is addition provides a supply of water to the fire pumps in case the fire protection storage tanks are depleted for any reason and has no l
adverse effect on service water system operation.
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PORC Review: PORC Meeting 1297, 10/9/84 1
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Subject:
PCR/PCN 82-1228 (882-1228)
Description:
Modified annunciation circuit for loss of voltage tripping busses 1F, 1G, 1H, IJ, and degraded grid voltage tripping busses IF and 1G to provide immediate targeted'information to aid in
' troubleshooting a tripped bus.
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- ' Safety Evaluation
- his modification in no way adversely affects the safe operation of the plant.
PORC Review: PORC Meeting 1299, 10/12/84 1
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Subject:
PCR/PCN 82-1-1250.1 (S82-1-1250.1)
Description:
Replaced the 3A, 3B, 4A, and 4B feedwater heaters. ,
Safety Evaluation: Copper in the original feedwater heaters is I
> suspected to be a major contributor to steam l generator tube denting. he new heaters utilize stainless steel tubes. Se new heaters are designed to meet or exceed the old heaters' performance with the operation being similar.
Replacement of the feedwater heaters improves the system's performance without degrading system l safety. %ese heater replacements are expected to assist in prolonging steam generator longevity. '
f PORC Review: PORC Meeting 1193 12/13/83
Subject:
PCR/PCN 82-1-1250.2 (S82-1-1250.2)
Description:
Replaced the 1A, 1B, 2A, 2B, 5A, 5B, 6A, and 6B j feedwater heaters. '
Safety Evaluation: Copper in the original feedwater heaters is i suspected to be a major contributor to steam generator tube denting. We new heaters are designed to meet or exceed the old heater's ,
performance with operation being similar.
Replacement of the feedwater heaters improves the i system's performance without degrading system
) satety. Wese heater replacements ate expected to 1
assist in prolonging steam generator longivity. '
PORC Review: PORC Meeting 1353, 2/14/85 i
Subject:
PCR/PCN 82-1328
Description:
Replaced sample pumps for the containment air sample monitor. Also, heat tracing was added to I the incoming sample lines from containment and a l valve modification was made to igrove blower performance. .
Safety Evaluation: ne new pumps have all metal internal parts which l should reduce maintenance requirements. In addition, system function will be igroved due to reduced condensation in the radiation monitor pugs and reduced back pressure on the sample pump.
PORC Review PORC Meeting 1126, 6/28/83 l
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Subject:
PCR/ Poi 83-1419 (S83-1-1419)
Description:
Replaced existing carbon steel service water supply and drain piping valves for Diesel Generators 1-2A, 1B, 1C and 2C air start system aftercoolers with stainless steel. j Safety Evaluation: his replacement will allow proper cooling water flow to the aftercoolers. his will reduce maintenance and operational problems associated with corrosion of existing carbon steel piping.
h is modification will not reduce the integrity of the system and does not constitute an unreviewed safety question.
PORC Review: PORC Meeting, 1402 6/25/85 PORC Meeting, 1418 8/8/85
Subject:
PCR/PCN 83-1465 (B83-1465)
Description:
Provided additional control capability, from the hot shutdown panel, for the following components, previously controlled from the main control board only.
Main Steam Isolation Valves SV-3369A, B, and C CCW Heat Exchanger Discharge MOV-3047-B Valve 1 RNST to Charging Pump Suction LCV-0115B and D valves
< Pressurizer Power Operated PCV-0444B, and Relief Valves (PORVs) 0445A Pressurizer PORV Block Valves MOV-8000A, and B Reactor Vessel Head Vent Valves SV-2213A, B, and SV-2214A, B Seal Water Injection Valve HCV-0186 Also, this design change provided an RCS Tcold indication and a condensate storage tank level indication on the hot shutdown panel.
Safety Evaluation: Wese modifications were in response to comunitments made to the NRC. Wey comply with the requirements of 10CFR50, Appendix R, and increase the safe operation of the plant.
PORC Review: PORC Meeting, 1346 1/29/25 4 I
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Subject:
PCR/P m 83-2489 (S83-1-2489) 1
Description:
Added vent valves to the turbine steam bypass line, :
downstream of the main steam bypass valves.
Safety Evaluation: his modification provides the capability to test the bypass valves individually for leakage. his modification already exists on Unit 2.
PORC Review: PORC Meeting 1307, 11/2/84 PORC Meeting 1348, 2/5/85
Subject:
PCR/PCN 84-2518 (B84-1-2518)
Description:
Add temperature monitoring system to detect check valve leakage in the auxiliary feedwater system.
Safety Evaluation: his change addresses the issue of auxiliary feedwater pump steam binding due to leakage of system check valves. his change has been evaluated for its effect on other installed systems.
PORC Review: PORC Meeting 1269, 8/7/84
Subject:
PCR/PCN 84-2644 (B84-1-2644)
Description:
Replaced existing flow sensing instrumentation in the battery room exhaust fan ducts.
Safety Evaluation: We previously existing instrumentation was in constant alarm. We ventilation system was determined to have no design deficiency. he purpose of the flow sensing instrumentation is to measure pressure drop across the system fans to ensure fan operation, but the actual pressure drop was too low to be sensed by the previously existing instrumentation.
PORC Review: PORC Meeting 1356, 2/21/85 l
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Subject:
PCR/PCN 84-2678 (S84-0-2678)
Description:
Assigned TPNS nanbers to eight thermostats which control the operation of the control room ventilation duct heating systems covering both units.
Safety Evaluation: h is change assigns TPNS numbers to existing thermostats and does not degrade th. safe shutdown capabilities of the plant. l PORC Review: PORC Meeting 1387, 5/7/85 l 10 l
Subject:
PCR/PCN 84-2721 (B84-0-2721)
Description:
Modified the existing HVAC system for the computer room to adequately cool the room upon installation cf Safety Parameter Display System (SPDS) equipment.
Safety Evaluation: his design supports the implementation of the SPDS which is required by NUREG-0737, Supplement 1.
PORC Review: PORC Meeting 1311, 11/13/84 PORC Meeting 1387, 5/7/85
Subject:
PCR/PCN 84-2726 (884-1-2726)
Description:
Installed a normally locked open valve downstream of normal charging containment penetration #24 test connection valves W407A and W407B. his is to facilitate the performance of the Local Leak Rate nst (LLRT) of this penetration without the need to use four separate boundary valves which are not part of the acceptance criteria for the LLRT, but experience has shown will leak--delaying the LLRT.
Safety Evaluation: Installation of this valve enhances the ability to perform a meaningful LLRT. Since the valve will be locked open at all times, except during the LLRT, there will be no adverse effect on plant operation or plant safety.
PORC Review: PORC Meeting 1346, 1/29/85 W
Subject:
PCR/PCN 84-1-2742 (B84-1-2742)
Description:
Modified the extended range containment pressure instruments PT0950Y and Z to provide adequate train separation.
Safety Evaluation: h is modification complies with regulatory guide 1.97. .
PORC Review: PORC Meeting 1394, 5/28/85 11
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Subject:
PCR/PCN 84-2773 (S84-1-2773)
Description:
Installed differential pressure gauges across each charging pump oil cooler to supplement existing pressure gauges in detecting developing oil cooler service water side plugging problems.
Safety Evaluation: he additional gauges will inform plant operators of developing oil cooler problems without degrading plant safety.
PORC Review: PORC Meeting 1297, 10/9/84
Subject:
PCR/PCN 84-2821 (B84-1-2821)
Description:
Routed the fuel transfer tube Local Leak Rate Test (LLRT) test connections outside of the concrete shielding. mis provided a means for performing the LLRT of the bellows fIce the auxiliary building hallway.
Safety Evaluation: Piping the test connection to the hallway is necessary to allow access to the test point without the major effort required to remove and replace shielding. Se piping design complies with the applicable codes and standards.
PORC Review: PORC Meeting 1306, 10/31/84 l
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Subject:
PCR/ poi 84-2824 (S84-0-2824)
Description:
Installed a vertical scale indicator to provide local level indication for the domineralized water storage tank.
Safety Evaluation: A local level indicator was installed in the tank level transmitter circuit of the domineralized water storage tank due to the existing mechanical level indicator being broken and beyond repair.
Since the domineralized water system is not required for any safety related functions, this change will not degrade the safe shutdown capabilities of the plant.
PORC Review: PORC Meeting 1387, 5/7/85 PORC Meeting 1452, 11/12/85 s
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Subject:
PCR/PCN 84-2883 (S84-1-2883)
Description:
Removed pressure controller QlP16PC667, high select relay N1P10V730, and the associated pressure control val 3 and tubing from the control logic for valve QlP16V560.
Safety Evaluation: Prior to installation of the service water surge tank, Q1P16PC667 existed to detect high service water system pressure and relieve it by opening OlP16VS60. With the installation of the service water surge tank, this function is no longer required.
PORC Review: PORC Meeting 1409, 7/23/85
Subject:
PCR/PCN 84-1-2960 (S84-1-2960)
Description:
Replaced the existing carbon steel moisture separator reheater (MSR) first stage extraction steam piping with stainless steel piping.
Safety Evaluation: ne carbon steel piping has been experiencing wall thinning due to erosion / corrosion by wet steam.
W is change affects only the MSR first stage extraction steam piping which has no safety function and is not safety-related.
PORC Review: PORC Meeting 1348, 2/5/85
Subject:
PCR/PCN 84-1-2961 (S84-1-2961)
Description:
Replaced existing carbon steel extraction steam piping to 6A and 68 feedwater heaters with stainless steel piping.
Safety Evaluation: n e carbon steel piping has been experiencing wall thinning due to erosion / corrosion by wet steam.
Bis change affects only the extraction steam piping to feedwater heaters 6A and 6B. his system has no safety function and is not safety-related.
POF.C Review: PORC Meeting 1348, 2/5/85 13
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Subject:
PCR/PCN 84-1-3003 (B84-1-3003)
Description:
To allow location of the Unit 1 Safety Parameter Display System (SPDS) computer hardware in the existing Unit 1 computer room, the Nuclear Data Link functions of the P2550 Data Link System were consolidated into the Unit 2 SPDS computer.
Safety Evaluation: his change has no impact on safety systems. Use of this system was deemed acceptable with no impact on plant safety as long as the appropriate procedures were updated.
PORC Review: PORC Meeting 1350, 2/8/85
Subject:
PCR/PCN 84-3020 (B84-0-3020)
Description:
Removed the interlock mechanism on Motor control Center (MCC) "F" cubicle door which tripped the MCC if the door was opened.
Safety Evaluation: This design change was accomplished within the applicable electrical codes and standards. his change prevents the loss o'f safety-related loads if the cubicle door is inadvertently opened.
PORC Review: PORC Meeting 1408, 7/19/85
Subject:
PCR/PCN 84-3021 (B84-0-3021)
Description:
Removed the interlock mechanism on Motor Control Center (MCC) "G" cubicle door which tripped the MCC if the door was opened.
Safety Evaluation: This design change was accomplished within the applicable electrical codes and standards. This change prevents the loss of safety-related loads if the cubicle door is inadvertently opened.
PORC Review: PORC Meeting 1408, 7/19/85 PORC Meeting 1434, 9/19/85 14
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Subject:
PClyPCN 84-3044 (S84-1-3044)
Description:
The pipe downstream of component cooling water system drain valve QlP17V113A was cut, threaded, and a pipe cap was installed.
Safety Evaluation: We pipe downstream of this drain valve was previously shown on the Final Safety Analysis Report figure as being open ended. his change in no way adversely affects safe system operation.
PORC Review: ICRC Meeting 1395, 5/30/85
Subject:
PCR/PCN 85-3072 (S85-1-3072)
Description:
Changed component cooling water system heat exchanger 1B pressure sensing line from 3/4" carbon steel piping and valves to 3/4" stainless steel piping and valves.
Safety Evaluation: 2 e carbon steel pressure sensing lines and valves were becoming clogged. This change in no way adversely affects, safe system operation.
PORC Review: PORC Meeting 1387, 5/7/85
Subject:
PCR/PCN 85-3073 (BES-1-3073)
Description:
Replaced two elbows in pipe HCD-412 between the plant vent stack sample nozzle and the Sping-4 inlet with pipe bends having a minimum radius of 5 times the pipe diameter.
Safety Evaluation: h is modification is in accordance with ANSI N13.1-1969 and, based on engineering judgement, this modification will not have adverse effects on existing design.
PORC Review: PORC Meeting 1343, (1/22/85)
Subject:
PCR/PCN 85-3075 (B85-1-3075)
Description:
Replaced the existing overcurrent trip unit on breaker LB02 with a unit having a lower trip setting.
Safety Evaluation: his modification protects power cable from overheating inside Kaowool wrap. The new trip setting is still far in excess of normal full load current.
PORC Review: PORC Meeting 1351, 2/12/85 15 1
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Subject:
PCR/PCN 85-3094 (S85-1-3094)
Description:
Updated drawing D-175042, sheets 1, 2, 3, and 4 for processing vaste water via the Disposable Demineralizer System as the primary method of waste treatment.
Safety Evaluation: his change in no way adversely affects safe plant operation.
PORC Review: PORC Meeting 1400, 6/18/85
Subject:
PCR/PCN 85-3154 (S85-1-3154)
Description:
Revised drawings to document the removal of the centrol and all but the final driver cards in the instrument loops for valves OlP16fv3009A, B, C.
Safety Evaluation: he removal of the control cards from cabinets QlHilNGB2504J and 2504K (Process Control Cabinets) will have no effect on the operation of the other devices located in these cabinets. Since the plant always operates with these service water valves in the manual control mode, there will be no impact on safe plant operation.
PORC Review: PORC Meeting 1405, 7/9/85
Subject:
PCR/PCN 85-3161 (S85-1-3161)
Description:
Realigned containment venting system manual isolation valve from "normally closed" to "normally open".
Safety Evaluation: his change does not impact the design of the system with respect to any of the system design bases including containment isolation. This change eliminates the need to make a " reentry" during postulated accident conditions to manually open this valve to allow containrcent venting for hydrogen concentration control.
PORC Review: PORC Meeting 1402, 6/25/85 16 1
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Subject:
PCrvPCN 85-3175 (S85-1-3175)
Description:
Changed the drawing designation from " locked open" to " locked throttled" for the recirculation valves for the waste evaporator feed pump, the waste evaporator concentiate pump, the che.ical drain tank pump, the laundry and hot shower tank puq and the floor drain tank pump.
Safety Evaluation: ne purpose of the recirculation lines is to r provide minimma flow protection for the pumps and to allow for recirculation mixing of the tank contents. It is not desirable from a pump design '
standpoint to have the recirculation valves wide open. With the valve throttled, there is still sufficient flow for tank mixing.
PORC Review: PORC Meeting 1400, 6/18/85
Subject:
PCR/PCN 85-3233 (B85-1-3233)
Description:
Re-routed the residual heat removal system heat exchanger room sump cover vent to the waste holdup tank room as on Unit 2.
Safoty Evaluation: We vent previously extended into the component cooling water system heat exchanger room creating a pathway for radioactive gases to enter the non-rad side of the Unit 1 auxiliary building.
PORC Review: PORC Meeting 1403, 6/27/85
Subject:
PCR/PCN 85-3234 (B85-1-3234)
Description:
Plugged the Unit 1 non-rad side elevator shaft drain.
Safety Evaluation: We existing drain was tied into the rad-side waste gas processing sump. Wis created a pathway for radioactive gases to enter the non-rad side of the auxiliary building.
PORC Review: PORC Meeting 1408, 7/19/85 17
Subject:
PCR/PCN 85-3238 (B85-1-3238)
Description:
Revised drawing D-175002 sheet 2 to show the actual, correct, arrangement of component cooling water system low air pressure switches QlP17PSL3184D and QlPl7PSL3045, for solenoid valves QlP175Sv3184 and QlP175Sv3045.
Safety Evaluation: 'Ihis change corrected a drawing error only and in no way adversely affects safe system operations.
PORC Review: PORC Meeting 1447, 10/24/85 subject: PCR/PCN 85-3265 (S85-1--3265)
PCB/PCN 85-3266 (S85-1-3266)
Description:
Replaced the small diameter (less than two inch) carbon steel service water piping and valves in the atxiliary and turbine buildings with stainless steel piping and valves.
Safety Evaluation: The carbon steel piping has been a continually worsening maintenance problem. Corrosion of the piping and the accumulation of crud in the piping have caused reduced flows and, in some cases, flow blockages. 'Ihis change is expected to eliminate the corrosion problem and minimize the crud accumulation problem.
PORC Review: PORC Meeting 1444, 10/15/85 18
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Subj ect: GO-NG-1, Rev. 6 l Procedure DevelopTent
Description:
This procedure provides guidance for writing a i general office procedure. j e 1 Safety Evaluation: W is revision to the procedure reflects management changes made to the offsite support organization.
I PORC Review: N/A l
Subject:
GO-NG, Rev. 4 ,
Organization and Responsibilities 1
Description:
Wis procedure decribes the general organization l and responsibilities of the offsite support organization.
I Safety Evaluaticn: his revisicn to the procedure reflects management changes made to the offsite support organization.
PORC Review: N/A
Subject:
GC)-NG, Rev. 2 I Master Bid List Input
Description:
h is procedure provides guidance for adding vendors to the Master Bid List.
Safety Evaluation: This revision to the procedure reflects ,
managenent changes made to the offsite support I organization. !
IORC Review: N/A
Subject:
GO-NG-4, Rev. 3 Specification Review
Description:
This procsiure provides guidance for reviewing equipnent specifications.
Safety Evaluation: Bis revision to the procedure reflects managenent changes made to the offsite support organization.
PORC Review: N/A 19
. - . ~ . ..
/
Subject:
GO-tG-5, Rev. 2 !
- Environmental Pbnitoring
Description:
This procedure provides guidance for conducting an environmental monitoring program.
Safety Evaluaticn: This revision to the procedure -reflects management changes made to the offsite support organization.
ICRC Review: N/A .
Subject:
GO-NG-9, Rev. 3 Plant Services Approved Suppliers List
Description:
This procedure provides guidance for develcping and
- naintaining a Plant Services Approved Suppliers List.
Safety Evaluation: This revisicn to the procedure reflects nanagenent changes made to the offsite support organization.
PORC Review: N/A
Subject:
GO-NG-12, Rev. 9 Procurment Document Control
Description:
'Ihis procedure provides guidance for maintaining centrol of equipment procurment documentation.
Safety Evaluation: This revisicn to the procedure reflects unnagenent charges nade to the offsite support orgmization.
PORC Review: N/A
Subject:
GO-NG-22, Rev. 3 Maintenance Support Conduct of Operation
Description:
This procedure describes the respcmsibilities of the maintenance support organization.
Safety Evaluation: This revisicn to the procedure reflects nanagement changes made to the offsite support organizaticn.
PORC Review: N/A 20 g w - -- ,-
w
. l s ..
Subject:
GO-NG-33, Rev. 5
- Operational Procurerent Interfaces
Description:
This procedure describes the interfaces between Nuclear Support, Safety Audit and Engineering Review and the Purchasing Department required for procurement related activities.
Safety Evaluaticn: 'Ihis revision to the procedure reflects management charges made to the offsite support organization.
PORC Review: N/A f
CD-NG-44, Rev. 2 )
Subject:
Inservice Inspection
Description:
This procedure provides guidance for conducting an !
inservice inspection program. l l
Safety Evaluaticn: 'Ihis revision to the procedure reflects management changes made to the offsite support organization. f mRC Review: N/A :
l Subj ect: G0-1G-45, Rev. O Technical Support Conduct of Operations Dascription: This procedure describes the responsibilities of the technical support organization.
Safety Evaluation: This procedure reflects Iranagement changes made to ,
the offsite support organi7ation. l PORC Review: N/A 21
t' ' Mailing Ad.fr*ss Alabama Power Company 600 North 18th Street Post Office Box 2641
. Birmingham. Alabaina 35291 Telephone 205 783-6090 R. P. Mcdonald ,
Senior Vice President Flintnage Buildirg AlabamaPower e 3- y. 9;: :, ye. -
March 31, 1986 Docket No. 50-348 I Dr. J. N. Grace, Administrator U. S. Nuclear Regulatory Comission Region II, Suite 3100 101 Marietta Street, N.W.
Atlanta, Georgia 30303
Dear Dr. Grace:
Attached for your review is the annual report required by 10CFR50.59 for 1985. This report summarizes changes to the plant performed in accordance with the provisions of 10CFR50.59 for Joseph M. Farley Nuclear Plant Unit 1. Also, in accordance with 10CFR50.59(b), 39 additional copies are provided for your use.
If you have any questions, please advise.
Respectfully submittatd, T
v.
T tw, R. P. McDonal d RPM /JLO:ddb-D6 Attachment cc: Mr. L. B. Long Mr. E. A. Reeves Mr. W. H. Bradford Director, Office of Inspection and Enforcement, Washington, D.C. 20555 Document Control Desk Washington, D.C. 20555 .
1 J
' i l- i
.