ML20205R675
| ML20205R675 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1986 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8704060410 | |
| Download: ML20205R675 (26) | |
Text
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - .
ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT UNIT 2 - ANNUAL REPORT REQUIRED BY 10CFRSO.59 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 des:ribed in the safety analysis report, and (2) make changes in the procedures as described in the safety analysis report, and (3) conduct i,
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 those records are required to include written safety evaluations which provide the basis for the determination that the changes, tests or experiments do not involve any unreviewed safety questions.
Brief descriptions and a summary of the safety evaluations of the changes, tests or experiments as described above, for the Joseph M. Farley Nuclear Plant Unit 2 which were completed in 1986, are provided in the following.
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I subject: PCR/PCN80-796(S8b-0-796)
Description:
Added a back-up battery / charger set to each train of the service water DC distribution system.
- Safety Evaluation
- This addition enhances plant safety by increasing the reliability and availability of the service
- water DC power system. ,
PORC Review: PORC Meeting 1292, 10/2/84 ,
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Subject:
Description:
Revised drawings to delete cable.2WL5089D which was to provide annunciation in Unit 2 for the fire
] protection systems in the shared areas (Diesel 3
Generator Buildirg, Fire Pump House,. Service Water Building, River Water Building, and Water Treatment Building). As a result, these shared areas will alarm only in Unit 1. he FSAR was revised to reflect this condition.
. Safety Evaluation: his revision does not affect any of the fire
! protection systems.
PORC Review: PORC Meeting 1546, 7/24/86
Subject:
PCR/PCN 81-1058 (S81-1058) 1
Description:
Relocated a fan from the exhaust ducts to the j supply ducts of switchgear rooms A and B in the
- Diesel Building and the Service Water Intake Structure.
j Safety Evaluation: his change will resolve the negative pressure
- problem without reducing the ventilation capacity or affecting the structural integrity of the j buildings.
PORC Review: PORC Meeting 1028, 9/21/82 4
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Subjict: PCR/PCN 81-2156 (B81-2156)
Description:
Converted clean storage room 2403 and transformer 1 cubicle 2410B to a respirator storage and issue facility. l his change will provide a suitable respirator Safety Evaluation: !
storage and issue facility in compliance with l NUREG-0041.
PORC Review: PORC Meeting 1055, 12/7/82 l 1 l
Subject:
PCR/PCN 82-2216 (S82-2-2216)
Description:
Installed two wet-pipe sprinkler systems in the ,
Unit 2 Turbine Building to increase fire protection coverage in the Turbine Building. '
Safety Evaluation: he installation of these additional sprinkler systems will minimize the impact of a fire fueled by a major spill of turbine lubricating oil. his design has been evaluated for its effect on other systems and has been found not to intarfere with ,
or degrade other installed systems.
PORC Review: PORC. Meeting 1310, 11/8/84
Subject:
PCR/PCN 82-2256 (S82-2-2256) i
Description:
Provided a means for handling hydrazine drums outside the Auxiliary and Turbine Buildings.
Safety Evaluation: his modification will reduce personnel exposure to the hydrazine fumes, which are a suspected carcinogen, by relocating the hydrazine drums outside the Auxiliary and Turbine Buildings. %e hydrazine piping that was added in the Auxiliary Building was seismically supported to prevent the 3
failure of this line from adversely affecting any
- safety related equipment in the event of an earthquake. his modification will not affect the integrity or reliability of this system or any safety related system and thus the consequences or probability of an accident will not be increased.
PORC Review: PORC Meeting 1402, 6/25/85 1 i
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Subjact: PCR/PCN 82-2259.2 (S82-2-2259.2)
Description:
Replaced the 1A, IB, 2A, 2B, 5A, and 58 feedwater heaters.
Safety Evaluation: Copper in the original feedwater heaters is l suspected to be a major contributor to steam generator tube denting. he new heaters utilize stainless steel tubes. h e new heaters are designed to meet or exceed the old heaters' performance. Operation is similar. Replacement of the feedwater heaters improves the system's performance without degrading system safety.
%ese heater replacements are expected to assist i
in prolonging steam generator life.
PORC Review: PORC Meeting 1459, 12/3/85 Subjeet: PCR/PCN 82-2299 (B82-2-2299)
Description:
Installed suction and discharge pressure gauges for both residual heat removal (RHR) pumps.
Safety Evaluation: %ese gauges are used only during RHR pump surveillance testing. Two normally closed instrument valves isolate each pressure gauge at all times except when surveillance tests are in progress. nese gauges will increase the accuracy of the measurements taken during surveillance testing.
PORC Review: PORC Meeting 1417, 8/6/85 l
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s Subj::ct: PCR/PCN 83-2467 (B83-2-2467)
Description:
Provided environmentally qualified intake -
temperature sensors for the. containment air cooler.
1 Safety Evaluation: his change was evaluated for its effect on other systems and it was determined that it does not degrade other installed systems.
PORC Review: PORC Meeting 1262, 7/10/84
Subject:
PCR/PCN 84-2527 (S84-2-2527) l
Description:
Revised the Total Plant Numbering System (TPNS) numbers for the isolation and check valves in the air start system of the 2B diesel generator.
Safety Evaluation: Drawing change only.
PORC Review: PORC Meeting 1559, 8/21/86
Subject:
PCR/PCN 84-2544 (B84-2-2544) 1
Description:
Installed a new steam sample panel and modified the existing sample control panel.
i Safety Evaluation: his modification will enhance the ability to a monitor the water chemistry of the plant secondary 1 system and will not impact the safe operation of
) the unit.
PORC Review: PORC Meeting 1474, 1/8/86
Subject:
PCR/PCN 84-2618 (B84-2-2618)
Description:
Replaced extended range containment pressure transmitters PT-950Y and PT-950Z to meet the requirements of 10CFR50.49 and Reg. Guide 1.97.
Safety Evaluation: The extended range containment pressure transmitters perform no safety function and cannot, due to failure, affect any other equipment which is required to perform a safety function.
PORC Review: PORC Meeting 1303, 10/23/84 i
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Subj::ct: PCR/PCN 84-2632 (B84-2-2632)
Description:
Provided a display for the new Gama-Metrics neutron monitor on the main control board.
Safety Evaluation: he display of the new Gama-Metrics neutron-monitor in the main control room will satisfy Reg.
Guide 1.97 and APCo comitments in the Reg. Guide 1.97 compliance report.
PORC Review: PORC Meeting 1438, 10/1/85
Subject:
PCR/PCN 84-2634 (B84-2-2634)
Description:
Replaced the existing eler:tronic indicator for the component cooling water (CCW) heat exchanger flow with a differential pressure flow indicator for local indication. Also, added displays in the main control room.
Safety Evaluation: his design change will replace the existing indicators with a qualified indicator and provide a display in the main control room. This will satisfy Reg. Guide 1.97 and the APCo comitments in the Reg. Guide 1.97 compliance report.
PORC Review: PORC Meeting 1445, 10/22/85
Subject:
PCR/PCN 84-2637 (B84-2-2637)
Description:
Provided remote indication in the control room of radioactive liquid waste tank levels and waste gas decay tank pressures.
Safety Evaluation: his design change satisfies the provisions of Reg. Guide 1.97 and the APCo commitments in the Reg. Guide 1.97 compliance report by providing remote indication in the control room.
PORC Review: PORC Meeting 1441, 10/8/85 5
Subject:
PCR/ poi 84-2707 (B84-2-2707)
Description:
Replaced the tubing downstream of the steam dump j warming line isolation valves with stainless steel piping, i
Safety Evaluation: The steam' dump system is nr:t required for safe shutdown of the plant. However, failure of this tubing could render portions of the steam dump
, . system inoperable, which could affect plant startups or shutdowns when the steam dumps are in operation. By utilizing stainless steel piping, this design makes such a failure less likely.
PORC Review: PORC Meeting 1432, 9/12/85 i
Subject:
PCR/PCN 84-2732 (N84-2-2732)
Description:
Installed two additional breakers in the switchyard to provide breaker-and-a-half protection for startup transformers 2A and 2B.
Mis design change also provides for separation of the autobank transformer from startup transformer 2A which provides for greater reliability of the autobank transformer. ,
Safety Evaluation: his modification will increase plant safety and meet design requirements as stated in General Design Criteria 17.
PORC Review: PORC Meeting 1459, 12/3/85 PORC Meeting 1474, 1/8/86 i
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Subject:
PCR/PCN 85-3121 (B85-0-3121)
Description:
Upgraded the Service Water Intake Structure
- microwave intrusion detection system.
Safety Evaluation: his upgrade will increase the effectiveness of the system and improve the ability of the system to detect unauthorized entry to the Service Water Intake Structure..
PORC Review: PORC Meeting 1452, 11/12/85
Subject:
PCR/PCN 85-3151 (S85-0-3151) i
Description:
Provided a new tie-in to the existing potable
! water system to supply potable water to the new Computer Building. Also provided a new fire main j that ties into the existing fire protection system to supply water to the new Computer Building ,
i sprinkler system.
Safety Evaluation: We potable water system provides drinking water throughout the plant. Wis system is not safety i related and has no effect on plant safety. he fire prot.ection system provided for the new Computer Building meets NFPA 24.
PORC Review: PORC Meeting 1423, 8/20/85 4
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Subjret: PCR/PCN 85-3195 (B85-2-3195)
Description:
Installed a Combustion Engineering (CE) heated junction thermocouple system as a reactor vessel level measuring system. his installation required modifications in the upper internals assembly, on the reactor vessel head, and above the reactor vessel head.
Safety Evaluation: his design meets APCO's comunitment under NUREG-0737.
PORC Review: PORC Meeting 1505, 4/4/86
Subject:
PCR/PCN 85-3220 (S85-2-3220)
Description:
Upgraded the existing post-accident radiation zone maps to reflect plant conditions.
Safety Evaluation: his upgrade satisfies a commitment made to the NRC in June 1984. Additionally, this will allow
! accurate decision-making in the event of a radiological emergency.
PORC Review: PORC Meeting 1531, 6/5/86 1
Subject:
PCR/PCN 85-3221 (B85-2-3221)
Description:
Modified the filter and gas collection cylinder i
arrangement on radiation monitors RE-21 and 22.
his keeps the gas collection cylinder upstream of the particulate / iodine filter in order to avoid absorption of gas on the filter which results in a nonrepresentative gas sample. Also, this design change replaced the 90' elbows in the inlet lines with tubing bends.
Safety Evaluation: his change is needed to reduce particulate impaction losses in the sample piping and to increase the sample collection efficiency.
PORC Review: PORC Meeting 1445, 10/22/85 a
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Subj2ct: PCR/PCN 85-3232 (B85-2-3232) l
Description:
Upgraded the containment atmosphere sampling system (RE-067) for post-accident sampling capability.
Safety Evaluation: h e upgraded RE-067 system is designed to provide containment sampling capabilities to satisfy NUREG-0737 requirements. his system provides for containment atmosphere sampling capabilities during normal and post-accident conditions. his system also provides gaseous grab samples and particulate / iodine filter collection.
PORC Review: PORC Meeting 1500, 3/20/86
Subject:
PCR/PCN 85-3270 (S85-2-3270) 2
Description:
Assigned new TPNS Numbers to the feedwater flow local indicators. W ese indicators were assigned TPNS numbers by Bechtel which duplicated TPNS numbers already assigned to indicators on the main control board.
Safety Evaluation: Drawing change only.
PORC Review: PORC Meeting 1491, 2/20/86
Subject:
PCR/PCN 85-3298 (S85-2-3298)
Description:
Installed permanent main condenser basket tip connections.
Safety Evaluation: his facilitates local readings of condenser vacuum for daily calorimetrics and routine testing.
PORC Review: PORC Meeting 1491, 2/20/86 9
Subjrct: PCR/PCN 85-3299 (B85-2-3299)
Description:
Revised drawings to show existing WAC sleeves and penetrations and to correct labelling deficiencies.
Safety Evaluation: Wese changes were evaluated to ensure continued proper operation of the system. Penetrations were labelled appropriately to ensure that they would not be closed in the future.
PORC Review: PORC Meeting 1491, 2/20/86
Subject:
PCR/PCN 85-3302 (B85-2-3302)
Description:
Modified one anchor as a result of a Bechtel engineering evaluation on fire protection system 2A-25. A total of 16 supports (15 hangers and 1 anchor) were found not to meet the requirement of NFPA-13 as required by Section 9.5.1.2.2 of the FSAR and Section.4.24.1.10 of the FPPR. With the exception of this anchor, all the stresses were well within the AISC code allowables.
Safety Evaluation: his modification will improve the responsiveness of sprinkler system 2A-25.
PORC Review: PORC Meeting 1490, 2/18/86 .
Subject:
PCR/PCN 85-3313 (B85-2-3313)
Description:
Modified the particulate and gas collection arrangement for containment purge exhaust. The sample flow path has been modified to place the particulate and gas sample points in parallel.
Safety Evaluation: his modification will eliminate any particulate from being collected in the filter when a gas sample is being taken, thereby ensuring an accurate particulate sample. ,
PORC Review: PORC Meeting 1474, 1/8/86 l
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Subject:
PCR/PCN 85-3369 '(B85-2-3369)
Description:
Deleted the Steam Generator Blowdown automatic trip from the blowdown sampling system radiation monitor (R-19).
Safety Evaluation: Steam Generator Blowdown is not required to isolate automatically on an R-19 signal since blowdown isolates on an R-23A signal and the blowdown effluent isolation valve closes.
automatically on an R-23B signal.
PORC Review: PORC Meeting 1493,2/25/86
Subject:
PCR/PCN 85-3374 (S85-2-3374)
Description:
Revised drawing D-205071 (sheet 2) 'to add inline conductivity cells upstream of the cation columns in the steam generator blowdown demineralizer sample lines, which reflects the as-built condition of the plant.
Safety Evaluation: Drawing change only.
PORC Review: PORC Meeting 1595,11/11/86
Subject:
PCR/PCN 85-3380 (B85-2-3380)
Description:
Modified the solid state protection system (SSPS) output relay test panel to ensure detection of a previously potentially undetectable test circuit failure.
Safety Evaluation: This change assures that plant operators and technicians will be aware of SSPS relay test switch failures which could affect system operation.
PORC Review: PORC Meeting 1483,2/4/86 11 l
Subjsct: PCR/PCN 85-3384 (B85-2-3384)
Description:
Modified the design of main steam isolation valve (MSIV) Q2N11V002A. h is design change augmented a design change which had been made during the third refueling outage. m is current change removed the "O" ring packing which had been installed previously and replaced the original type of packing because the "O" ring packing had developed l steam leaks.
l_ Safety Evaluation: %e MSIV's are required to close to mitigate the consequences of a main steam line break. his change will not affect the valve weight, center of gravity, seismic calculations or operability of the valves.
PORC Review: PORC Meeting 1474, 1/8/86
Subject:
PCR/PCN 85-3385 (B85-2-3385)
Description:
Modified MSIV's Q2N11V002B & C and Q2NilV001A,B and C in order to reduce the amount of friction imposed on the valve by the valve packing i material. In the previous design, excessive friction was exerted upon the valves when the i packing was tight enough to stop steam from j escaping through the packing. ,
Safety Evaluation: %e MSIV's are required to close to mitigate the consequences of a main steam line break. his
- change will minimize the force on the MSIV shaft-t that could prevent valve closure. %e change will not affect the valve weight, center of gravity, seismic calculations or operability of the valves.
I PORC Review: PORC Meeting 1474, 1/8/86 i
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Subject:
PCR/PCN 85-3474 (S85-2-3474)
Description:
Revised drawings to show that the reactor coolant drain tank (RCDT) recirculation orifice outlet isolation valve and the RCDP pump discharge valves are in a " locked throttled" position instead of in the "open" position.
Safety Evaluation: his change will prevent pump run-out and allow sufficient pump discharge head for flow through the demineralizer and filter to the recycle holdup tank.
PORC Review: PORC Meeting 1499, 3/18/86
Subject:
PCR/PCN 85-3482 (S85-0-3482)
Description:
Revised drawings to reflect the correct valve line-up for operation of the waste gas processing system and the main steam system.
Safety Evaluation: Drawing change only.
PORC Review: PORC Meeting 1520, 5/6/86 r
Subject:
PCR/PCN 86-3648 (S86-0-3648)
Description:
Rerouted the 1-2A diesel generator control and starting air piping to provide positive venting of the rack boost cylinder. We rack boost cylinder ensures that fuel is supplied to the diesel engine during the early stages of engine starting.
Safety Evaluation: Positively venting the rack boost cylinder will improve plant operation and reliability.
PORC Review: PORC Meeting 1595, 11/11/86 I
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Subjcct: PCR/PCN 86-3649 (S86-2-3649)
Description:
Rerouted the 2B diesel generator control and starting air piping to provide positive venting of
-the rack boost cylinder. %e rack boost cylinder ensures that fuel is supplied to the diesel engine during the early stages of engine starting.
Safety Evaluation: Positively venting the rack boost cylinder will improve plant operation and reliability.
PORC Review: PORC Meeting 1595, 11/11/86
Subject:
ENP-2-AOP-33.0 Revision 0, KN OB
Description:
Corrected the FSAR discussion concerning the isolation of the steam generator blowdown (SGBD) system upon receipt of a high radiation signal.
Contrary to information currently shown in the FSAR, SGBD isolation valves 7614A, B and C do not close upon receipt of a high radiation signal from radiation monitor R-19. R-19 isolates only the SGBD sampling system.
Safety Evaluation: SGBD is isolated upon receipt of a high radiation signal for R-23A and the SGBD discharge to the environment is isolated upon receipt of a high radiation signal from R-23B. ,
PORC Review: PORC Meeting 1490, 2/18/86 i
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- Subject'
- FNP-0-AP-3 Ravision 7
Description:
Revised procedure FNP-0-AP-3 to show the current plant' organization. This revision affected two items shown in the FSAR:
- 1) 'The requirement for the Assistant General Manager - Plant Support .to have a senior reactor operator's license or the experience.-
and training required for this license was deleted.
- 2) The qualification requirements for the Health Physics Supervisor.were changed to be consistent with Regulatory Guide 1.8.
Safety Evaluation: Changing the qualification requirements for these individuals constitutes an administrative change only.
PORC Review: PORC Meeting 1525, 5/22/86
Subject:
FNP-0-AP-31 Revision 8
Description:
Clarified requirements for qualification of inspection, examination and testing personnel.
This improved compliance with commitments and allows management enhanced flexibility in establishing requirements.
Safety Evaluation: This change is for clarification purposes, and is administrative -in nature.
PORC Review: PORC Meeting 1536, 6/20/86 15
Subj;ct: INP-2-CCP-301 Revicion 0
Description:
Provided for the increase and control of the circulating water cycles of concentration by reducing the blowdown rate and periodically closing blowdown. D e FSAR states that the circulating water system will have a continuous blowdown in order to keep the solids content in the circulating water within acceptable limits.
Safety Evaluation: he solids content of the circulating water would still be maintained within acceptable limits.
Supporting data have shown that the corrosion rate of the water boxes and cooling tower piping should decrease with higher cycles of concentration.
PORC Review: PORC Meeting 1533, 6/12/86
Subject:
FNP-0-EIP-26 Revision 18
Description:
Revised the ENP Emergency Plan to require notification to state officials within fifteen minutes of declaration of any emergency class.
Previous evaluations had concluded that notification within one hour of the declaration of a Notification of Unusual Event was sufficient.
Safety Evaluation: he fifteen minute notification will allow additional response time for the state agencies and provide for consistency of the Emergency Plan with 10CFR50, Appendix E.
PORC Review: PORC Meeting 1615, 12/17/86 16
Subj2ct: FNP-2-ETP-1013 R:; vision 0
Description:
Provided a means of_ cooling down steam generator 2A. %is method is not described in the FSAR.
We procedure was written for testing in Mode 5 when the safety related systems utilized in the test are not required to be operable.
Safety Evaluation: he procedure is sufficient to provide adequate guidance to prevent or mitigate any malfunctions that could occur to overpressurize a steam generator.
PORC Review: PORC Meeting 1504, 4/1/86
Subject:
ENP-0-ETP-1014 Revision 0
Description:
Provided for flushing the steam generator tube support plates. We tube support plate flushing process is a series of depressurization cycles used to optimize removal of chemicals from areas of restricted flow such as the region between the tube support plate and the tubes.
Safety Evaluation: We use of the tube support plate flushing procedure will not adversely affect the safe operation of the plant in general, and the steam generator tube bundle integrity in particular, and ,
does not represent an unreviewed safety question with one, two or three steam generators being flushed at one ti:ne.
PORC Review: PORC Meeting 1520, 5/6/86 17
SubjLct: ENP-2-ETP-4195 Revision 0 MD 86-1380
Description:
Provided for the temporary hookup of a water treatment trailer to the condensate storage tank (CST). The purpose of this is to reduce the oxygen concentration in the CST water.
Safety Evaluation: The water in the CST will be monitored to ensure that all chemistry parameters remain within the applicable specifications. Several means were employed to ensure that the water level in the CST did not drop below the minimum value allowed by Technical Specifications. These means included stationing an individual at the CST with instructions to close isolation valves at the CST should the integrity of the treatment system be broken.
PORC Review: PORC Meeting 1501, 3/21/86
Subject:
ENP-2-SOP-7.0 Revision 15, TCN 15A
Description:
Changed the miniflow setpoint for Unit 2 RHR miniflow valves FCV602A and B by changing the orifice size to increase the miniflow flowrate.
Safety Evaluation: This change minimizes excessive vibration which .
was found to exist during startup testing.
PORC Review: PORC Meeting 1502, 3/25/86 18
Subj;ct FNP-2-STP-64.1 Revision 12, 'KN 12B
Description:
Changed the position of the feedwater heater bypass valve (N2N21v528) to locked closed.
Safety Evaluation: Locking the bypass valve in the closed position provides increased assurance that cold water will not be fed inadvertently to the Steam Generators.
PORC Review: PORC Meeting 1558, 8/19/86
Subject:
MD 85-1035 Revision 1 MD 86-1411 Revision 2
Description:
Added an isolation valve and a Chicago fitting to each of the condensate pump suction drain lines to faciliate the initial boric acid soak of the steam generators. Sufficient boric acid is added by vacuum drag to bring the steam generator concentration to about 50 ppm. These valves and fittings are removed at the conclusion of the boric acid soak. During normal operation boric acid is maintained via the auxiliary feed chemical addition pumps.
Safety Evaluation: W e condensate system is not necessary for the safe shutdown of the plant.
PORC Review: PORC Meeting 1613, 12/16/86
Subject:
MD 86-1397
Description:
Modified the existing Stock Equipment Compactor to provide the option of compacting 50-52 gallon drums with a 10-30 ton compaction or of compacting 55-gallon drums at a 15 ton compaction force.
Safety Evaluation: his modification will facilitate the use of super compaction.
I PORC Review: PORC Meeting 1503, 3/28/86 i
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Subjrct: MD 86-1433
Description:
Installed a grab sample valve assembly on the cation conductivity colum effluent.
Safety Evaluation: %e grab sample valve assembly was installed in existing lines on which only cation conductivity is measured.
PORC Review: PORC Meeting 1521, 5/7/86
Subject:
Cycle 5 Reload Safety Evaluation
Description:
The Unit 2 Cycle 5 fuel reload consisted of 1 Region 4, 16 Region 5, 72 Region 6, and 68 fresh Region 7 fuel assemblies. A total of 1120 fresh standard burnable poison rodlets are used in clusters of 4, 12, 16, 20, and 24 rodlets. %e Region 7 assemblies differ from the previous design in that they include chamfered fuel pellets, a modified fuel rod bottom end plug design, a reduced fuel rod helium backfill pressure and grid sleeves made from 304L stainless steel. All of the assemblies used in Cycle-5 have anti-snag grid designs.
Safety Evaluation: he fuel design changes will decrease the probability of cladding failure, grid snagging or ,
hydriding corrosion.
PORC Review: PORC Meeting 1512, 4/18/86 PORC Meeting 1518, 4/29/86 20
Subj;ct: Safsty Evaluation: Reduction of River Wat'ar Level
Description:
Approved the lowering of the elevation of Jim Woodruff reservoir to 74 feet MSL. his was due to drought conditions which existed in the Chattahoochee River Basin.
Safety Evaluation: Allowing river level to fall to 74 feet MSL will not adversely affect river water pump operation nor environmental concerns as previously evaluated in the FSAR.
PORC Review: PORC Meeting 1565, 9/5/86
Subject:
Safety Evaluation: Containment Calculated Peak Accident Pressure, Pa (ES-85-495)
Description:
Provided revised values of containment peak calculated post-accident pressure and temperature.
his re-analysis included reduced amounts of heat input from the zirconium-water reaction. Previous calculations had used overly conservative values for the zirconium-water heat input. We peak containment pressure was reduced from 48.4 to 48 psig and the peak temperature was reduced from 316 to 313'F.
Safety Evaluation: his calculation provides more realistic values.
No accident analysis is adversely affected.
PORC Review: PORC Meeting 1555, 8/12/86
Subject:
Safety Evaluation: Transfer of Control Rod Guide Tubes from Type A Cask to Type B Cask
Description:
Approved the transfer of control rod guide tubes to a different type of cask. During the Unit 2 fourth refueling outage, two irradiated control rod guide tubes were removed from the upper internals and placed inside a canister which was then placed in a Type A storage cask. Before these guide tubes could be shipped offsite for burial, they had to be transferred to a Type B shipping cask.
Safety Evaluation: The transfer of the control rod guide tubes from the Type A cask to the Type B cask is performed under vendor procedures.
PORC Review: PORC Meeting 1547, 7/28/86 21
Subject:
Safety Evaluation: R38C46 Partial Tuba Removal Condition
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Description:==
Approved continued operation with a steam generator _ tube having been partially removed.
During the Unit 2 fourth refueling outage, actions were taken to remove steam generator tube R38C46 on the hot leg side of steam generator C. This was done to investigate the significance of eddy current indications at_the tube support plate elevations. However, the tube could be only partially removed.
Safety Evaluation: Based on Westinghouse's evaluation, the operation of FNP Unit 2 with the presence of the remaining tube section located at R38C46 fixed within the tubesheet on the hot leg side of steam generator C does not involve an unreviewed safety questions.
PORC Review: PORC lieeting 1516,4/26/86
Subject:
Safety Evaluation: R34C44 Partial Tube Remove Condition
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Description:==
Approved continued operation with a steam generator tube having been partially removed.
During the third refueling outage in January 1985, actions were taken to remove steam generator tube R34C44 on the hot-leg side of steam generator A.
This was done to investigate the significance of eddy current indications. However, the tube could be only partially removed. The remaining portion of the tube and the adjacent tubes were plugged.
Westinghouse performed an analysis of this partial tube removal condition that demonstrated the tube bundle integrity for operation until the next scheduled refueling outage at which time an assessment of the condition of the adjacent tubes will be made.
Safety Evaluation: An assessment of the condition of the adjacent tubes was made during the fourth refueling outage and it was determined to leave the adjacent tubes plugged. An evaluation was conducted and it was determined that no further action is necessary as long as (1) the tubes closest to the partial tube remain plugged, and (2) eddy current testing of the active tubes nearest the partial tube are conducted during scheduled steam generator eddy current testing and the results do not indicate degradation of these tubes that could be attributed to interaction with the partial tube.
PORC Review: PORC Meeting 1511, 4/17/86 22
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Subject:
FNP Emerg:ncy Plan
Description:
Changed the Emergency Plan to require notification of state and local agencies within one hour of the declaration of a Notification of Unusual Event and within 15 minutes of the declaration of an Alert, Site Area Emergency or General rmergency.
Safety Evaluation: This change included no changes which would increase the probability or consequences of an accident previously evaluated, no changes which would create the possibility of a new or different.
kind of accident from any accident previously evaluated and no changes which would involve an unreviewed safety question. Also, these changes do not decrease the effectiveness of the Emergency Plan.
PORC Review: PORC Meeting 1492,2/21/86 PORC Meeting 1522, S/13/86
Subject:
GO-EIP-111, Rev. 13
Description:
This procedure provides guidance for the activation of the Nuclear Generation Department emergency organization.
Safety Evaluation: This revision to the procedure revises the phone numbers listed for notification.
PORC Review: N/A
Subject:
G0-NG-38, Rev. O
Description:
This procedure provides guidance for the steps required to ensure receipt inspections for General Of fice consigned services are properly performed and documented.
Safety Evaluation: This procedure provides guidance for receipt inspection of General Office consigned servicas by the General Of fice Nuclear Generation Department Staff.
i PORC Review: N/A 23
Subject:
Nuclear Operations Review Board (140RB) Manual
Description:
This manual provides operating guidelines for all NORB activities.
Safety Evaluation: This manual provides guidance for the NORB to conduct independent reviews of safety-related matters.
PORC Review: N/A
Subject:
Operation Quality Assurance Policy (0QAP)
Implementation List, Rev. 13
Description:
The OQAP Implementation List is a composite listing of administrative. procedures responsible for assigning responsibilities in the Operation Quality Assurance Policy Manual.
Safety Evaluation: This revision to the 0QAP Implementation List is the result of changes in the Technical Support organization.
PORC Review: N/A
Subject:
Operation Quality Assurance Pclicy Manual, Rev. 24
Description:
This manual establishes the Quality Assurance Policy for the Farley Nuclear Plant.
Safety Evaluation: This revision incorporates organizational changes made to the offsite nuclear support group.
PORC Review: N/A
Subject:
Safety Audit and Engineering Review (SAER) - AP Manual - Rev. 11
Description:
This manual provides administrative guidance for performing the duties of the SAER.
Safety Evaluation: This revision to the manual addresses changes made to the offsite support organization.
PORC Review: N/A 24 l
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Al bdma Power Company i
600 North 18th Street ;
Post Office Box 2641.
Birmingham. Alabama 352914400
- Telephone 205 250-1835 hnd?!e'%sioe,, Nabama w e the southern electic system 10CFR50.59 March 31, 1987 Docket No. 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
Attached for your review is the annual report required by 10CFR50.59 for 1986. This report summarizes changes to the plant performed in accordance with the provisions of 10CFR50.59 for Joseph M. Farley Nuclear Plant Unit 2.
If there are any questions, please advise.
Respectfully submitted, ALABAMA POWER C PAN R. P. Mcdonald-RPM / REM: dst Attachments cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford -
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