ML19309B159
| ML19309B159 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/26/1980 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML19309B158 | List: |
| References | |
| NUDOCS 8004030214 | |
| Download: ML19309B159 (13) | |
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ALABAMA POWER COMPANY-JOSEPH M. FARLEY NUCLEAR PLANT ',
ANNUAL REPORT REQUIRED BY 10CFR50.59 (1979)
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 those records are required to include written safety evaluations which provide the bases for the determination that the change, test or experiment does not involve any unreviewed safety questions.
Brief descriptions of the changes, tests or experiments as described above, for the Joseph M. Farley Nuclear Plant - Unit 1, including a summary of the safety eealuations which were reviewed by the Plant Operations Review Committee in 1979, are listed below:
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- 1.
SUBJECT:
Unit 1 Cycle 2 Reload (with demonstration assemblies).
DESCRIPTION: The Joseph M. Farley Unit 1 Cycle 2 reload fuel assembly consists of 50 Region 4 standard assemblies and 2 demonstration assemblies designated as Region 4A. The Region 4 assembly design is unchanged from the previous fuel design with
._ respect to the Nuclear, Mechanical and Thermal Hydraulics. The Region 4A fuel assemblies involve several minor design changes aimed at improving uranium utilization principally by .
reduction in fuel rod diameter and the replacement l of Inconel grids with zircalloy in the active I region of the core. Nuclear, Mechanical and Thermal Hydraulics compatibility with respect to standard fuel design has been fully evaluated.
SAFETY EVALUATION: The insertion of 50 Region 4 and 2 Region 4A fuel assemblies into Farley Unit 1 and the operation throughout Cycle 2 is within the l bounds of the currently approved safety analysis '
and meets an established core design criteria on
! the use of the Region 4A assemblies.
PORC REVIEW: PORC Meeting 333, 1/3/79.
PAGE 1
- 2.
SUBJECT:
PCR/PCN 78-187 (BM78-187). ,
DESCRIPTION: Upgraded the Containment Purge E'%haust Filter System to Seismic Category I. .
SAFETY EVALUATION: Upgrading the Containment Purge Exhaust Filter System to Seismic Category I up- to the filter discharge increases the safety margin in the event of a fuel handling accident.
PORC REVIEW: PORC Meeting 336, 1/12/79.
- 3.
SUBJECT:
PCR/PCN 78-042 (B78-042).
DESCRIPTION: Installation of a feedwater bypass control valve
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as part of a system to provide automatic Steam Generator level control at low reactor power levels.
SAFETY EVALUATION: The addition of a Q, Seismic Category I, ASME Code Class 3 feedwater bypass valve falls within the scope of, and meets all applicable accident analyses in the FSAR. The additional piping has been restrained for high energy pipe breaks consistent with FSAR Appendix 3K.
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PORC REVIEW: PORC Meeting 325, 12/12/78.
PORC Meeting 342, 2/2/79.
- 4.
SUBJECT:
PCR/PCN 78-234 (B78-234).
DESCRIPTION: Changed drainage alignment from the decontamination room to the Floor Drain Tank and added a drain to the Chemical Drain Tank.
SAFETY EVALUATION: This modification reduc es waste processing and increases plant efficiency without degrading safe operation.
PORC REVIEW: PORC Meeting 338, 1/19/79.
PORC Meeting 343, 2/5/79.
- 5.
SUBJECT:
PCR/PCN 78-251 (B78-251).
DESCRIPTION: Deleted a Reactor Trip following a Turbine Trip below 50% power.
SAFETY EVALUATION: Westinghouse has evaluated the impact of deleting !
a Reactor Trip following a Turbine Trip below 50% power. The re-analysis had acceptable results. Technical Specification revisions were ;
approved by NRC. '
PORC REVIEW: PORC MEETING 352, 2/26/79. ,
PAGE 2
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- 6.
SUBJECT:
PCR/PCN 78-271 (B78-271). .
DESCRIPTION: Modified the auto-closure interl'ock on the RHR inlet line isolation valves to provide RCS
- overpressurization mitigation capability required by the NRC. -
SAFETY EVALUATION: Westinghouse has stated that this modification does not degrade the protection systems required to keep the plant in a safe condition. The modified auto-closure capability, with regard to the RER System, meets the single failure analysis requirements.
PORC REVIEW: PORC Meeting 354, 3/7/79.
- 7.
SUBJECT:
PCR/PCN 78-295 (W78-295).
DESCRIPTION: Replaced the Part Length Rod Cluster Control Assemblies (PLRCCA's) with thimble plug assemblies.
SAFETY EVALUATION: The probability of occurrence of events has not increased and the consequences of these events remain within those reported in previous analyses.
The possibility of other types of accidents or malfunctions has not increased. Operation of
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, _ _ . the plant with the thimble plug assemblies
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instead'of the PLRCCA's does not present any danger to the health and safety of the public.
PORC REVIEW: PORC Meeting 356, 3/12/79.
- 8.
SUBJECT:
PCR/PCN 78-165 (B78-165).
DESCRIPTION: Piping change to allow boron concentration
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monitoring system sampling upstream of the Boron Thermal Regeneration System outlet.
SAFETY EVALUATION: Added a boron meter sampling point upstream of the BTRS outlet to the CVCS. This is a minor deviation from FSAR P & ID's which provides for a more accurate RCS boron concentration measurement.
PORC REVIEW: PORC Meeting 280, 8/8/78.
PORC Meeting 325, 12/12/78.
PORC Meeting 356, 3/12/79. !
- 9.
SUBJECT:
PCR/PCN 79-345 (B79-345).
DESCRIPTION: Replaced 3/4" line (HCD-206) running from the Chemical Reagent Tank to the Chemical Drain Tank with 3/4" high pressure stainless steel wire l braided hose having flange connections at both l ends. ,
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SAFETY EVALUATION: This modification corrects the problem of chemical corrosion in this line and allows for a reasonable means of replacing the leaking line. This is a design improvement compatible with the chemical
- environment of this system.
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PORC REVIEW: PORC Meeting 357, 3/13/79.
- 10.
SUBJECT:
PCR/PCN 78-281 (B78-281).
DESCRIPTION: Each existing valve on the inlet and outlet side of the Seal Injection Filters was replaced with 2 valves. This double valving provides increased
. personnel safety during filter changing activity.
- SAFETY EVALUATION: This design results in increased personnel safety and does not adversely affect installed systems.
PORC REVIEW: PORC Meeting 358, 3/14/79.
- 11.
SUBJECT:
PCR/PCN 78-246 (B78-246, SE78-246).
l DESCRIPTION: Revised the interlocking circuitry among the l diesel sequencers, modified load sequencing, I
modified interlocks between several Load Center and MCC supply breakers, and added another
,- service water wet pit stop log.
SAFETY EVALUATION: The modifications covered in the PCR and agreed to in the PCN are in accordance with the corrective actions reported to the NRC.
These modifications result in increasing the availability and reliability of the on-site emergency power system and do not adversely
__ affect plant safety.
PORC REVIEW: PORC Meeting 326, 12/15/78.
PORC Meeting 340, 1/26/79.
PORC Meeting 361, 3/20/79.
- 12.
SUBJECT:
PCR/PCN 79-346 (B79-346).
l l DESCRIPTION: Installed a contact pyrometer type temperature l element on each steam generator to provide indication of secondary side water temperature.
SAFETY EVALUATION: This change is required in order to satisfy an NRC RCS overpressure mitigating system surveillance l requirement and will enhance safe plant operation.
PORC REVIEW: PORC Meeting 365, 3/23/79.
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- 13.
SUBJECT:
PCR/PCN 78-143 (B78-143).
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DESCRIPTION: Provided an alternate on-line power supply for Process Instrument Cabinets 5 through 8. ,
SAFETY EVALUATION: This modification results in increasing the safety and reliability of the plant and will in no way interefere with or degrade other installed systems.
PORC REVIEW: PORC Meeting 369, 4/2/79.
- 14.
SUBJECT:
PCR/PCN 78-144 (B78-144).
DESCRIPTION: Provided an alternate on-line power supply for 7300 Process Protection Cabinets 1 through 4.
SAFETY EVALUATION: This modification results in increasing the safety and reliability of the plant and will in no way interefere with or degrade other installed systems.
PORC REVIEW: PORC Meeting 369, 4/2/79.
- 15.
SUBJECT:
PCR/PCN 78-356 (APC078-356).
DESCRIPTION: Provided additional access for RCP seal maintenance i -
by installing spool pieces to connect existing piping to seal housing connections.
SAFETY EVALUATION: These spools are seismic category II and perform no safety function. No additional unsupported length was added.
PORC REVIEW: PORC Meeting 375, 4/13/79.
._ 16.
SUBJECT:
Revised Fuel Loading Pattern for Unit 1, Cycle 2.
DESCRIPTION: The fuel loading pattern for J. M. Farley -
Unit 1, Cycle 2, was revised to include two Cycle 1, Region 1 assemblies in place of a Cycle 2, Region 2 assembly.
SAFETY EVALUATION: An evaluation of the design parameter based on the Westinghouse Reload Safety Evaluation Methodology, which resulted from the new loading pattern, demonstrates that the new reload pattern will not adversely affect the safety of the plant or change the conclusions of the original reload safety evaluation.
PORC REVIEV: PORC Meeting 376, 4/19/79.
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- 17.
SUBJECT:
PCR/PCN 78-317 (B78-317). , l DESCRIPTION: Provided waste discharge manifolds to facilitate bulk disposal operations. .
SAFETY EVALUATION: This modification improves the system operation without degrading safe operation.
PORC REVIEW: PORC Meeting 378, 4/24/79.
- 18.
SUBJECT:
PCR/PCN 78-358 (B78-358).
DESCRIPTION: The existing protection system logic was modified by deleting the low pressurizer pressure coincident with low pressurizer level actuation logic and replacing it with safety injection actuation on two-ous -of-three low pressurizer pressure signals only.
SAFETY EVALUATION: All current ECCS analyses are valid and appropriate for safety injection initiation as a function of pressurizer pressure signals only. The effect of changing to a pressure only signal results in either an earlier initiation of safety injection, or no change in the time of safety injection initiation for all break locations.
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PORC REVIEW: PORC Meeting 385, 5/7/79.
- 19.
SUBJECT:
PCR/PCN 78-056 A & B (B78-056).
DESCRIPTION: Changed the power source for the Reactor Coolant Pump breaker position trip logic from Class IE inverters to Class IE so,la regulated power supplies with key interlocks to permit switching the logic power back to the inverter in the event of a Sola failure.
SAFETY EVALUATION: This modification improved the reliability and safety of the plant and does not interfere with or adversely affect other installed systems.
PORC REVIEW: PORC Meeting 380, 4/26/79.
PORC Meeting 386, 5/9/79.
- 20.
SUBJECT:
PCR/PCN 78-149 (SE 78-149).
- DESCRIPTION: Installed a "first out" annunciator for the steam generator feed pumps.
l SAFETY EVALUATION: The Steam Generator Feed Pump first out annunciator l circuits are isolated from the SI Steam Generator i Feed Pump Trip circuits by an interposing relay.
PAGE 6
Testability of the trip circuity is not altered.
The addition of the annunciator does not compromise
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the safety of the plant. -
PORC REVIEW: PORC Meeting 387, 5/11/79.
- 21.
SUBJECT:
PCR/PCN 78-262 (B78-262).
DESCRIPTION: Installed undervoltage relays to detect degraded grid voltage on safeguard buses IF and 1G in accordance with NRC requirements, and added channel trip switches to the loss of voltage relay circuits associated with 4.16 KV buses IF, IG, 1H and IJ to facilitate circuit testing.
SAFETY EVALUATION: These changes increase the safety and reliability of the plant and will not adversely affect the safe operation of the plant.
PORC REVIEW: PORC Meeting 341, 1/31/79.
PORC Meeting 353, 3/5/79.
PORC Meeting 399, 6/12/79.
PORC Meeting 404, 7/6/79.
- 22.
SUBJECT:
PCR/ECN 78-305 (B78-305).
DESCRIPTION: Installed a flow orifice downstream of the waste
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concentrates pump to limit flow and ensure pump NPSH requirements are met.
SAFETY EVALUATION: This change improves the concentrates pump operation without degrading safety.
PORC REVIEW: PORC Meeting 411, 7/18/7,9.
- 23.
SUBJECT:
PCR/PCN 79-344 (SE79-344, B79-344).
DESCRIPTION: Replaced all river water pump HC6 handswitches (Units 1 and 2) with switches capable of starting or stopping the pumps during a LOSP condition in the event of a diesel sequencer failure. In addition, river water pump No. 10 circuitry was modified to allow this pump to automatically sequence onto Bus IH in the event of Loss of Off-site Power or low-low pond level.
SAFETY EVALUATION: These modifications enhance pump availability and the ability to balance river water and service water flows in the event of a pond dam failure.
PORC REVIEW: PORC Meeting 387, 5/11/79.
PORC Meeting 397, 6/5/79.
PORC Meeting 414, 7/25/79. .
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- 24.
SUBJECT:
PCR/PCN 78-278 (B78-278). ,
DESCRIPTION: Replaced the BIT recirculation flow transmitter with a Clampitron ultrasonic flow detector. ,
SAFETY EVALUATION: The Clampitron installation does no.t affect seismic qualification of the BIT recirculation piping nor interfere with or adversely affect other installed systems.
PORC REVIEW: PORC Meeting 415, 7/30/79.
- 25.
SUBJECT:
PCR/PCN 79-430 (B79-430).
PESCRIPTION: Installed insulation on the steam generator water level instrumentation reference legs.
SAFETY EVALUATION: This change provides for reducing the impact of increased uncertainties in steam generator water level instrumentation under post-accident conditions.
PORC REVIEW: PORC Meeting 426, 8/16/79.
- 26.
SUBJECT:
PCR/PCN 79-378 (B79-378).
DESCRIPTION: Removed the two diesel generator auto-synchronizers from the Emergency Power Board.
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SAFETY EVALUATION: The auto-synchronir i were to be used for testing purposes coif, therefore, their removal in no way adversely affects the safe operation of the plant.
PORC REVIEW: PORC Meeting 430, 8/29/7,9.
PORC Meeting 438, 9/20/79.
- 27.
SUBJECT:
PCR/PCN 78-078 (B78-078).
DESCRIPTION: Revised steam generator blowdown isclation circuitry to allow continued blowdown when Auxiliary Feedwater pumps are manually started, added a seal-in feature to ensure that the i blowdown valves remain shut when a MDAFWP auto start signal is reset and deleted the closure signals from the TDAFWP to the blowdown isolation valves.
SAFETY EVALUATION: These changes are consistent with system requirements and guarantee that the blowdown system remains isolated under accident conditions. Deletion of blowdown isolation upon TDAFWP start simplifies l the system design. The system will still meet I
the accident analyses contained in the FSAR.
PAGE 8
PORC REVIEW: PORC Meeting 342, 2/2/79.
PORC Meeting 438, 9/20/79. *
- 28.
SUBJECT:
PCR/PCN 79-441 (B79-441). .
DESCRIPTION: Provided foc installation of an off-site telephone in the Bulk Radwaste Loading facility.
SAFETY EVALUATION: This change provides communications between the Chem-Nuclear operator and his supervisor. This change improves communications.
PORC REVIEW: PORC Meeting 468, 12/12/79.
- 29.
SUBJECT:
OCR 1590 (BM-3027).
. DESCRIPTION: Installed differential pressure indicators across various filters in the liquid waste system.
SAFETY EVALUATION: This change is consistent with the original system design and will provide additional capability without degrading safe operation.
PORC REVIEW: PORC Meeting 415, 7/30/79.
- 30.
SUBJECT:
OCR 1699 (Various Change Notices for Fire Protection)
DESCRIPTION: (SM-1389): Preaction Sprinkler System in the Auxiliary Building.
(BE-2600): Termination Cabinet Water Protection.
(Containment Hose Stations)
(PCR/PCN 78-227 (B78-227)): Reactor Coolant
__ Pump Oil Collection.
(SM-1394): Core Drill in the Diesel Building.
(SM-1395): Core Drill in the Service Water Intake Structure.
(SM-1396, 1397): Preaction Sprinkler Systems in the Auxiliary Building.
(BE-4502): Reworked Auxiliary Building ventillation dampers.
(BE-4503): Rerouted Auxiliary Building electrical circuits.
(SM-1463): Preaction Sprinkler System in the Auxiliary Building.
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(BC-1224): Core Drill in the Auxiliary Building.
(BE-4505): Drawing changes for ' replacement of Emergency Lighting Battery Packs. *
(BM-3088): Auxiliary Building HVAC' drawing changes.
(2BC-642): Fire rated ceiling over the Control Room kitchen.
(BC-1225, 1226): Core Drills in the Auxiliary
. Building.
._ (SM-1466): Preaction Sprinkler System in the Auriliary Building.
(BC-1222): Core Drill in the Auxiliary Building.
(SM-1467 through 1470): Preaction Sprinkler Systems in the Auxiliary Building.
(BM-3087): Reactor Coolant Pump Oil Collection.
(BC-1228, 1229): Core Drills in the Auxiliary Building.
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(SM-1471 through 1474): Preaction Sprinkler Systems in the Auxiliary Building.
(SM-1475 through 1491): Smoke and Fire Detection Systems in the Auxiliary Building.
(SE-2393): Conduit added fcr Diesel Building cable tunnel Sprinkler System.
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(SE-2395): Freeze Protection circuits at the Service Water Intake Structure.
(SM-1492 through 1498): Smoke and Fire Detection Systems in the Auxiliary Building.
(SM-1499, SM-1503 through 1527): Smoke and Fire Detection Systems in the Diesel and Auxiliary Buildings.
(SM-1500 through 1502): Preaction Sprinkler Systems in the Auxiliary Building.
(SM-1530): Smoke Removal Equipment.
(BC-1231): Core Drill in the Auxiliary Building.
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(SM-1534 through 1539): Smoke and Fire Detection Systems in the Auxiliary Building.
(BE-4513): Smoke and Fire Detection Systems in a the Auxiliary Building.
(SE-2396 and 2398): Smoke and Fire Detection Systems in the Auxiliary Building.
(BE-4506): Raceway installation in the Auxiliary Building.
(BC-1232): Core Drill in the Auxiliary Building.
(BE-4508): Raceway installation in the Auxiliary Building.
(SM-1542): Hanger modifications in the Auxiliary Building.
(BC-1230): Core Drill in the Auxiliary Building.
(BC-1233, 1234): Core Drills in the Auxiliary Building.
(BE-4515,4516): Raceway installation in the
, __ Auxiliary Building.
(BC-1235): Core Drill in the Auxiliary Building.
(SM-1554): Hanger modification in the Auxiliary Building.
(SM-1556): Hanger modification in the Auxiliary Building.
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(SM-1566): Hanger modification in the Auxiliary Building.
SAFETY EVALUATION: These changes enhance plant safety and satisfy commitments made to and accepted by the NRC in the Fire Protection Program Re-evaluation Report.
These designs have been evaluated for their effect on other systems and have been found not j to interfere with or degrade other installed systems. These designs are in accordance with applicable codes, standards, FSAR and licensing l commitments.
PORC REVIEW: (SM-1389): PORC Meeting 334, 1/4/79.
(BE-2600): PORC Meeting 341, 1/31/79.
PAGE 11
(Containment Hose' Stations): P,0RC Meeting 341, 1/31/79. ,
(PCR/PCN 78-227 (B78-227)): PORC Meeting 341, .
1/31/79.
(SM-1394): PORC Meeting 342, 2/2/79.
(SM-1395): PORC Meeting 342, 2/2/79.
(SM-1396, 1397): PORC Meeting 342, 2/2/79.
(BE-4502): PORC Meeting 348, 2/16/79.
(BE-4503): PORC Meeting 348, 2/16/79.
(SM-1463): PORC Meeting 353, 3/5/79.
(BC-1224): PORC Meeting 353, 3/5/79.
(BE-4505): PORC Meeting 355, 3/8/79.
(BM-3088): PORC Meeting 355, 3/8/79.
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(2BC-642): PORC Meeting 355, 3/8/79.
,_ (BC-1225, 1226): PORC Meeting 355, 3/8/79.
(SM-1466): PORC Meeting 356, 3/12/79.
(BC-1222): PORC Meeting 351, 2/23/79.
PORC Meeting 362, 3/20/79.
(SM-1467 through 1470): ,PORC Meeting 365, 3/23/79.
(BM-3087): PORC Meeting 365, 3/23/79.
(BC-1228, 1229): PORC Meeting 366, 3/26/79.
(SM-1471 through 1474): PORC Meeting 369, 4/2/79.
(SM-1475 through 1491): PORC Meeting 369, 4/2/79.
(SE-2393): PORC Meeting 371, 4/5/79.
(SE-2395): PORC Heeting 375, 4/13/79.
(SM-1492 through 1498): PORC Meeting 375, 4/13/79.
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9 (SM-1499, SM-1503 through 1527): PORC Meeting 378, 4/24/79. *
(SM-1500 through 1502): PORC Meeting 378, ,
4/24/79.
(SM-1530): PORC Meeting 378, 4/24/79.
(BC-1231): PORC Meeting 400, 6/18/79.
(SM-1534 through 1539): PORC Meeting 403, 6/29/79.
(BE-4513): PORC Meeting 427, 8/21/79.
(SE-2396 and 2398): PORC Meeting 427, 8/21/79.
(BE-4506): PORC Meeting 427, 8/21/79.
(BC-1232): PORC Meeting 403, 6/29/79.
PORC Meeting 427, 8/21/79.
(BE-4508): PORC Meeting 428, 8/23/79.
(SM-1542): PORC Meeting 428, 8/23/79.
(BC-1230): PORC Meeting 400, 6/18/79.
- ~ PORC Meeting 428, 8/23/79.
(BC-1233, 1234): PORC Meeting 434, 9/7/79.
(DE-4515, 4516): PORC Meeting 436, 9/13/79.
(BC-1235): PORC Meeting 447, 10/12/79..
(SM-1554): PORC Meeting 447, 10/12/79.
(SM-1556): PORC Meeting 452, 10/24/79.
(SM-1566): PORC Meeting 470, 12/14/79.
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