ML20071F962

Rept of Changes,Tests & Experiments Performed at Pilgrim Nuclear Power Station,In Accordance w/10CFR50.59(b)

ML20071F962
Person / Time
Site:	Pilgrim
Issue date:	12/31/1993
From:	Rothert W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-73, NUDOCS 9407110288
Download: ML20071F962 (7)

Text

. e 10CFR50.59 aosnw axscw Fhtgnm Nuclear Power Station Rocky Hal Road Plymouth, Massachusetts 02360 W. C. Rothert June 30, 1994 General Mar.ager Technical BECo Ltr. #9' 73 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No DPR-35 Report of Changes, Tests and Experiments Performed at Pilarim Nuclear Power Station in accordance with 10CFR50.59(b), Boston Edison is submitting this report of the changes, tests and experiments at Pilgrim Nuclear Power Station for the period of January 1 through December 31,1993.

A listing of reportable changes and tests completed in the reporting period is attached. Each listing contains a brief description, a reference to the relevant Final Safety Analysis Report (FSAR) section, and a reference to the supporting Safety Evaluation (s). ,

No experiments were performed during the report period.

W. C. Rothert WCR/MTL/nas/5059RPT Attachments cc: Mr. R. Eaton, Project Manager Division of Reactor Projects - lill Mail Stop: 14D1 U. S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region i 475 Allendale Road l King of Prussia, PA 19406 l Senior Resident inspector Pilgrim Nuclear Power Station i I 9407110298 931231 FDR ADOCK 05000293 l

R PDR

4 ATTACHMENT Page 1 of 6 Trash Rack Rake Addition PDC No: 85-080D SE No: 2111 FSAR

Reference:

11.6.3 This modification added a trash rack rake to the screenhouse to remove accumulating debris and marine life from the trash rack.

The change did not constitute an unreviewed safety question because the change did not affect any Class I structures or systems.

Relocaie Eauipment fot Hydrogen Water Chemistry Shieldwall PDC No: 85-083A SE No: 2661 FSAR

Reference:

10.9.3.4.3 This change removed Turbine Building Ventilation Fans (VSF 102A,B,C) to allow construction of a shield wall to reduce radiation exposure to station personnel during Hydrogen Water Chemistry System operation.

This change did not involve an unreviewed safety question because the f ans did not perform any safety related function.

Station Blackout Diesel Generator Operability and Modifications PDC No: 89-043 SE No: 2682 FSAR

Reference:

8.4.5.1, 8.10.3, F7.4-11, F7.4-13 This change modified an existing diesel to meet the Station Blackout Rule (10CFR50.63) requirements for use as an alternate AC power source, These changes were previously discussed in BECo letter 89-057 dated April 17,1989 and did not .

constitute an unreviewed safety question.

ATTACHMENT Fage 2 of 6 SPO Diese(Generator Testina Modifications at 23kv Substation PDC No: 89-044 l I

SE No: 2435 1

FSAR

Reference:

F8.2 1 This change involved modifications to the 23 KV substation to provide protection to the 23 kv line dJring load testing of the Station Blackout Diesel Generator. This change did not constitute an unreviewed safety question because it has no impact on and does not directly affect any safety related systems, subsystems or components.

Instrument Air System Uparate PDC No: 89-061 SE No: 2432 FSAR

Reference:

10.11.3.1,10.11,3.2 This modification installed new flow meters, filter differential pressure gauges, a dew point monitor, and replaced a filter is the instrument air system. These modifications were necessary to enable the system to meet tne requirements of Generic Letter 88-14 and did not constitute an unreviewed s 1fety question.

Helocation of the Recirc MG set AC Lube Oil Pump DC Motor Power Supply Control Circuits PDC No: 89-071 SE No: 2493 FSAR

Reference:

F8.6-1 This change relocated the DC control power supply of the recirculation MG sett AC Lube Oil pumps to increase the reliability of both recirculation MG sets.

This modification did not constitute an unreviewed safety question because the function of the recirculation MG set AC Lube Oil Pumps has not been altered.

ATTACHMENT Page 3 of 6 Control Room Liahtin.q Uparade PDC No: 90-040 SE No: 2649,2494 FSAR

Reference:

10.16.2 This change involved upgrading the lighting system in the control room to assure compliance with NUREG 0700 and did not affect 10CFR50 Appendix R compliance as it relat s to control room emergency lighting.

This modification did not involve an unreviewed safety question because the modified equipment is functionally similar and introduces no new failure modes, Salt Service Water Pipina Replacement PDC No: 91010A SE No: 2572,2575 and 2663 FSAR

Reference:

F10.7-1 This was the first in a series of plant changes to support the Salt Service Water (SSW)

Piping Replacement Project. This change relocated existing buried pipe and conduit in preparation for the construction of a concrete vault (separate change) adjacent to the south wall of the Intake Structure. This part of the project did not involve any safety related portion of the SSW system or plant structures, and aid not constitute an unreviewed safety question.

,R_ejlacement of Carbon Steel Pipe Between Water Box Scavenaina Puino and the ScavensLna Pump Seal Wate Pumps PDC No: 91-011 SE No: 2560 FSAR

Reference:

F 11.6-1 This change replaced carbon steel pipe with plastic pipe between the water box scavengir;g pumps (P-145A/B) and the scavenging pump seal water pumps (P-157A/B)'

in the circulating water system, This change did not involve an unreviewed safety question because the new pipe meets ANSI B31.10-1967 and has no safety related function.

4 ATTACHMENT Page 4 of G Heplacement of 125V c ; Battery Charaers PDC No: 92-038 SE No: 2712 FSAR

Reference:

8.6.3, F8.6- i The modification replaced the 125V DC battery chargers to improve die DC system's voltage response to AC input voltage transients.

This chango did not involve an unreviewed safety question because the new chargers are essenSally the same as the old chargers and the function remains unchanged.

Auamented Fuel Pool Coolina - Phas.e i Modifications PDC No: 92-041 SE No: 2697 FSAR

Reference:

4.8.5.6,10.4.3 This change implemented a modification to the Fuel Pool Cooling System to create a new operating mode (Mode 1) which uses the Residual Heat Removal / Fuel Pool Cooling intertie to divert a portion of shutdown cooling flow to the fuel pool to provide augmented fual pool cooling.

This modification did not constitute an unreviewed safety question. The Mode 1 of augmented fuel pool cooling enhances the cooling capability of the Fuel Pool Cooling System and all postulated accidents, transients and equipment failures are bounded by existing analysis.

Chance Various DC MOV Stroke Times l

SE No: 2776

FSAR

Reference:

4.7 5, 6.5.2.3. T7.3-1, TS.2-4, 7.4.3.2.5 l

l This change modified various DC motor stroke times. The systems affected by these changes are HPCI. RCIC, Main Steam Drains, RHR, and RWCU.

l These changes did not constitute an unreviewed safety question. Valve stroke times do not affect accident probabilities and all stroke times are bounded by existing analyses. No new types of accidents were postulated.

l

ATTACHMENT Page5 ofti Fire Protection Surveillance Freauencies in Locked Hiah Radiation Areas SE No: 2801 FSAR

Reference:

10.8.4.2.2,10.0 A.5.2 This change reduced the Fire Protection Surveillance frequencies in Locked High Radiation Areas during power operation. The affected components are valves and hose stations in Locked High Radia ion A;eas only. This change is consistent with Condition of License #3.F and no po%tial unreviewed safety questions have been identified.

Chanae RWCU Precoat Material SE No: 93-02 FSAR

Reference:

9.3.4.2.1 This change replaced the Reactor Water Cleanup Filter Demineralizer precoat material from *SOLKA floc" to a higher grade material to preclude sodium spikes when placing the filter demineralizer in service.

This change did not constitute an unreviewed safety question because the new precoat material performs the same function as the material it is replacing. No new failure modes have been introduced.

Surveillance Testina for PASS SE No: 93-06 FSAR Reference' 10.19.3,10.19.5 The change is to permit sample comparisons between Post Accident Sample System (PASS) samples and normal grab samples. These samples are compared to determine that the samples from the PASS are representative of the system being sampled within a factor of 2 as required by NUREG 0737 and INPO Good Practice CY-707. This change does not involve an unreviewed safety question.

ATTACHMENT Page 6 of 6 Annual Update to Emeraency Plan SE No: 93-22 FSAR

Reference:

App.N This evaluation was for the annual review and revision of the Pilgrim Station Emergency Plan and did not constitute an unreviewed safety question because no safety related structures, systems or components were affected, l-Revise the Initial Conditions for Performance of the Manual Openina of the ADS Valves SE No: 93-26 FSAR

Reference:

8.5 6.2 The initial conditions for manual opening of the ADS relief valves (RV203-A,B,C,D) were changed from reactor pressure at 375 psig (approximately 11% power) to 20%

reactor power to take advantage of increased plant stability (at higher power levels).

This change also reduces water fluctuation induced by cycling the relief valves.

This change does not involve an unreviewed safety question because opening the valve at a higher pressure does not increase the potential for equipment failure, intearity Testina of the Emeraency Diesel Generator Oil Storaae Tanks SE No: 93-29 FSAR

Reference:

8.5,14.3, G,5 A test of the Emergency Diesel Oil Storage Tanks (T126A/B) was performed to verify the integrity of these underground tanks. The test did not impair the ability of the Emergency Diesels to perform their safety function and the volume of diesel oil required by Technical Specifications was maintained.

This test did not involve an unreviewed safety question. The primary fuel sources for the diesels (Day Tanks T124A/B) were verified to have sufficient fuel for 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of diesel operation prior 'o the start of the test. This was sufficient time for onarators to abort the test and retum the storage tanks to normal service had the die' m tun required for plant operations.

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