BECO-LTR-96-063, Forwards Rept of Changes,Tests & Experiments at Plant for Period of Jan-Dec 1995

Forwards Rept of Changes,Tests & Experiments at Plant for Period of Jan-Dec 1995

ML20115A799
Person / Time
Site:	Pilgrim
Issue date:	06/28/1996
From:	Oheim H BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-96-063, BECO-LTR-96-63, NUDOCS 9607080455
Download: ML20115A799 (6)

Text

m p 10CFR50.59 Boston Edieon 4

Pdgrim Nuclear Power S'tation Rocky Hill Road Plymouth, Massachusetts 02360 Henry V. Oheim General Manager . Technical Section June 28, 1996 BECo Ltr #96-063 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 I License No. DPR-35 Report of Changes, Tests and Experiments Performed at Pilarim N_uclear Power Station i

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 31,1995. {

A listing of all changes affecting the Final Safety Analysis Report (FSAR) completed in the reporting ,

period is attached. Each listing contains a brief description, a reference to the relevant FSAR i sections, and a reference to the supporting safety evaluation (s). .

No tests or experiments were performed during the report period.

H. V. Oheim i

HVO/MTL/pkk/radmisc/5059RPT

Attachment:

Report of Changes, Tests and Experiments cc: Mr. Alan B. Wang, Project Manager i Project Directorate I-1  !

Mail Stop: _14B2 -l Office of Nuclear Reactor Regulation 1 White Flint North 11555 Rockville Pike

Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region 1 -

475 Allendale Road King of Prussia, PA 19406 [h/ 9 l, 1 l

Senior Resident inspector Igrim Nuclear Power Station 4

9607080455 960628 PDR ADOCK 05000293 .}

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, Attachment to Bnston Edison Re, port of, Changes, Tests and Experiments Page 1 of 5

' Replace'All Pinina Thermal Insulation in the Drywell i PDC 83-62 1 Safety Evaluation Numbers 2971,1638 Rev.1

. FSAR Sections Affected: 4.8.5.1,6.4.3,14.5.3.1.3, F14.5-9, F14.5-10, F14.5-13 4

- The change replaced all the piping thermal insulation in the drywell with Owens-Coming NUKON

. fiberglass insulation. This change was previously reported in Boston Edison letter dated July 25, i 1986. Safety evaluation 1638 Rev.1 was superseded by safety evaluation 2971 because an original i General Electric report attached to the safety evaluation has been revised. Safety evaluation 2971 i al.so expanded the background information related to the issue of pump NPSH and the Pilgrim design

basis.  ;

The design change reviewed by this safety evaluation does not constitute an unreviewed safety j J question.

Uoarade 480V AC Station Semice Substation No.1 );

5 ' PDC 85-84 j i Safety Evaluation Number 2498 l FSAR Sections Affected: Figure 8.2-1  :

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This modification replaced the existing transformer and its associated 480V AC distribution system .

l with a new substation. l The replacement system does not have a safety-related function. The new system is an improvement over the'old system and is not located near any safety-related equipment; therefore, this change did l not constitute an unreviewed safety question. ,

[ l l Auamented Fuel Pool Coolina and Purification

i PDC 91-23 I p Safety Evaluation 2576 1

FSAR Sections Affected

4.8.5.6,10.4.3 l

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This modification revised the reactor cavity cleanup mode of the residual heat removal and fuel pool l' cooling and demineralizer systems. This modification allows effluent from the fuel pool filter and

. domineralizer to flow continuously to either the spent fuel pool or the reactor cavity to facilitate spent i j fuel pool cleanup and reactor cavity cooling during refueling. l

' The modification did not compromise the ability of the affected safety-related components from performing their safety-related functions; therefore, there was no unreviewed safety question involved.

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Attachment to Boston Edisen '

Report of, Changes, Tests and Experiments

. Page 2 of 5 Removal of Fire Damoors CR-6 and CR-7  !

t PDC 91-66'

Safety Evaluation 2654

[ ' FSAR Figure Affected: F10.9-6 This modification removed fire dampers CR-6 and CR-7 that were located in the control room high

! efficiency tir filtration system (CRHEAFS) because they had the potential to impact CRHEAFS if they were to c. de inadvertently; There was also potential degradation of the cinch t, traps, and they may  ;

4 not have been capable of holding the dampers open in a seismic event. Removal of these dampers . '

eliminated the concems and did not adversely affect the integrity of the fire barrier. This change did i not involve an unreviewed safety question.  ;

LCable Replacement From D16 to MCC D7 PDC 93-46 i i  : Safety Evaluation 2811

. FSAR Section Affected

F8.6-1

This modification replaced the cable from D16 to MCC D7 to improve the voltage at the motor terminals for certain motor operated valves (MOV) fed from MCC D7. Replacing this feeder cable  !

reduced the scope of MOV modifications required to improve the design margin under the Generic  !

j Letter 89-10 program.

' This change did not involve an unreviewed safety question.  ;

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- Replacement of Turbine Buildina Trucklock Rolluo Door PDC 94-08 Safety Evaluation 2058 _

t FSAR Figures Affected: F12.1-2, F12.1-3, F12.1-11, F12.2-7, F12.3-2 c This change removed the existing 16' wide rollup door in the turbine building trucklock and replaced it wdh a new 20' wide rollup door.

Replacing the trucklock door did not adversely affect safety-related structures or equipment and did not involve an unreviewed safety question.

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! Modification to' M01001-50 for Generic Letter 89-10

- PDC 94-18E . i

Safety Evaluation 2861 l FSAR Section Affected

Table 5.2-4

$ - This modification involved installing a new !arger valve operator motor, revising the four rotor limit switches, added a new torque switch, an( rep',acement of the thermal overload relay and overioad ,

, - heaters. A Liberty Quicktest cable assembly was also installed in the actuator to allow diagnostic *

~ testing of the motor operated valve without opening the actuator switch compartment. These

' modifications were part of the Generic Letter 89-10 program.

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1 Attachm:nt to Boston Edison Report of, Changes, Tests and Experiments Page 3 of 5 This change did not involve a unreviewed safety question. The safety related function of the valve remained qualified for plant design bases loads after completion of this modification.

Actuator ReDiacement for MO1001-47 PDC 94-18K -

Safety Evaluation 2888 FSAR Section Affected: Table 5.2-4 This modification included installation of a new larger valve operator motor and replacement of the thermal overload heater as part of the Generic Letter 89-10 program.

This modification improved the soility of MO1001-47 to perform its safety function and did not involve an unreviewed safety question.

SDent Fuel Control Rod Blade Storaae ,

l PDC 94-26 i Safety Evaluation 2818 I I

FSAR Section Affected: 10.3.4.1 This change provided brackets, hardware and cables to individually suspend control rod blades from l the fuel pool curb. This change provides open space on the fuel pool floor for spent fuel racks and waste containers.

This change did not constitute an unreviewed safety question.

Auumentt:d Fuel Pool Coolina - Phase 2 Modifications PDC 94-37 Safety Evaluation Number: 2886 FSAR Sections Affected: 4.8.5.5,4.8.5.6,10.4.3 This change modified the residual heat removal / fuel poc, cooling intertie to improve the operation of the augmented fuel pool cooling mode 1 and establish a new augmented fuel pool cooling mode 2.

This modification does not compromise the ability of the affected safety related components to perform their safety functions, and there is no unreviewed safety question involved.

- ,I Attachment to Bost:n Edison Report of, Changes, Tests and Experiments Page 4 of 5 Reactor Shroud Repair PDC 94-43 Safety Evaluation 2926 FSAR Sections Affected: 3.3.4, 3.3.4.1.1, 3.3.6.7.1, 3.3.6.9, F3.3-10, C.3.4.2, TC.3-7 This change provided a permanent preemptive repair to the core shroud in the Pilgrim reactor pressure vesselin response to Generic Letter 94-03. The repair structurally replaced all of the shroud circumferential girth welds by installing a vertical tie rod and lateral spring arrangement at each of four

- locations on the outside of the shroud.

The shroud repair did not constitute an unreviewed safety question.

Salt Service Water Pump Cubicle Exhaust Fans PDC 95-12 Safety Evaluation Number: 2911 FSAR Section Affected: 10.9.3.7.2 This change replaced the air operated intet dampers for the Salt Service Water cubicle exhaust fans with manually operated dampers. No unreviewed safety question was identified by this safety evaluation.

Annual Revision of the Emeroency Plan Safety Evaluation 2950 FSAR Section Affected: Appendix N This revision to the Pilgrim Station Emergency Plan reflects tiiose changes previously approved and administrative changes that have been identified since the last revision of the plan. This change did not involve an unreviewed safety question.

- Surveillance Reauirements For Fire Protection Safety Evaluation 2976 FSAR Sections Affected: 10.8.4,10.8.4.1.2,10.8.4.2.2,10.8.4.3.2,10.8.4.5.2,10.8.4.6.2 This change incorporated changes to the NFPA codes and standards for fire protection. In particular, the test frequencies for detectors, pumps, batteries, valves, fire hoses and penetration seals have been modified.

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= No unreviewed safety questions were identified in this evaluation.

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. ,i Attachment t2 Bost:n Edisin

. Report of, Changes, Tests and Experiments Page 5 of 5 Salt Servico Water Temperatura of 75*F Safety Evaluation: 2983 FSAR Sections Affected: 1.6,4.8, 5.2,10.5,14.5,14.7 i This change resulted from a new plant safety analyses performed using a constant salt service water system injection temperature of 75 F. This evaluation also documented the proposed changes to the FSAR which incorporated results from the design verification consistent with the scope of information ,

cnd level of detailin the current FSAR. The new analyses presented in this evaluation supplement the current analyses.

This change did not involve an unreviewed safety question.

Buildina Waterproof Membrane Bypass Seepaae

. Safety Evaluation Number: 2986 ,

FSAR Section Affected: 12.2.4.4.3 This evaluation clarifies the current FSAR descriptions of the waterproof membrane feature of the ,

reactor building, turbine building and radwaste building. The clarification states the waterproof membrane systems are designed to prevent or minimize groundwater in-leakage.

. This change did not involve an unreviewed safety question.

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