BECO-89-040, Forwards Update to long-term Plan as Part of Semiannual Rept,Consisting of Commitment Description,Progress Since Mar 1986 Update & Summary of Changes & Reasons Associated W/Regulatory Requirements

Forwards Update to long-term Plan as Part of Semiannual Rept,Consisting of Commitment Description,Progress Since Mar 1986 Update & Summary of Changes & Reasons Associated W/Regulatory Requirements

ML20247K008
Person / Time
Site:	Pilgrim
Issue date:	03/27/1989
From:	Bird R BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 BECO-89-040, BECO-89-40, GL-82-33, GL-83-28, GL-87-02, GL-87-2, GL-88-14, IEB-87-001, IEB-87-1, IEB-88-010, IEB-88-10, TAC-44328, NUDOCS 8904050144
Download: ML20247K008 (19)

Text

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nsnw-Pilgrim Nudear Power Station Rocky Hil: Road Plymouth, Massachusetts 02360 l

1 Ralph G. Bird March 27, 1989 Senior Vice President - Nuclear BECo 89 040 l

U. S. Nuclear Regulatory Commission Document Control Desk Hashington, DC 20555 I

l License DPR-35 {

Docket 50-293 LONG TERM PROGRAM: SEMI-ANNUAL REPORT I

Dear Sir:

This lotter provides the update to the Long Term Plan (LTP) in accordance with Section V.A of the " Plan for the Long Term Program - Pilgrim Nuclear Power l Station". This update consists of the following:

4 Attachment 1: Schedules A, B and Additional Items List Attachment 2: Commitment Description Attachment 3: Prograss Since March 1986 Update Attachment 4: Summary of Changes and Reasons Associated with Regulatory Requirements In addition to Schedule A and B items, BECo is implementing plant betterment modifications and activities. These additional items are outside the regulatory scope of the Long Term Program and thus exempt from the license conditions imposed on Schedule B items. These additional items could have potential influences on Schedule B items. ,

4 R. G.hA

~ Bird HGL/1280

, Attachments 1, 2, 3, and 4 1

cc: See next page gir$M M88jhs ,

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BOSTON EDIS0N COMPANY

, , March 27, 1989 U.S. Nuclear Regulatory Commission Page 2 cc: Mr. D. Mcdonald, Project Manager Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Mail Stop: 14D1 U. S. Nuclear Regulatory Commission i 1 White Flint North 11555 Rockville Pike Rockville, MD 02852 U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior NRC Resident Inspector Pilgrim Nuclear Power Station l

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1 ATTACHMENT 2 I

COMMITMFNT DESCRIPTION SCHEDULE A 4

Item Description Reference Document (s) 1

1. ATHS Rule Comoliante l The Rule issued by NRC requires modifications 1) 10CFR50.62 to the Standby Liquid Control System, Alternate 2) BECo Ltr. #85-140 dated l Rod Insertion and Reactor Recirculation August 7, 1985 Pump Trip by the Second refueling outage from June 26, 1984 (i.e., RF0 #8 for BECo).

BECo has implemented the Standby Liquid Control 3) NRC Ltr. from Mr. H. R.

System modification in RF0 #7. The Technical Denton to BWROG Chairman Specification changes for Standby Liquid Control dated August 19, 1985 System were approved by NRC on August 5, 1987 (Amendment #102). The ARI/RPT modifications I

l were implemented in 1980 in response to NUREG-460, as directed by the NRC.

NRC requested additional information 4) NRC letter dated, regarding ARI/RPT modifications by September 27, 1987 Ref. 4) to determine compliance with 5) BECo letter #88-073, this rule. BECo submitted response dated April 27, 1988.

, to NRC request by Ref. 5). The diversity of 6) NRC letter to BECo, l .ARI is yet to be resolved with BHROG, NRC dated January 9, 1989.

l and licensees, as identified in the meeting notes from the NRC (Ref. 6), All other items are resolved. BECo is waiting for NRC Safety Evaluation Report. The schedule, RF0 #8, represents resolution of the diversity issue and does not represent time required to complete modifications if required by the NRC.

2. Station Blackout Rule (SBO)

The rule requires BECo to submit a response 1) 10CFR50.63 (53FR23203, by April 17, 1989, which includes the dated June 21, 1988) l

! following:

a) a proposed station blackout duration with justifications.

b) a description of procedures for SB0 events and recovering from them.

c) a list of proposed modifications and schedule including procedures for meeting the SB0 duration.

l The NRC will issue a safety evaluation following BECo submittal and the schedule for completion of modifications will then be determined.

i l

Page 1 of 6

v-ATTACHMENT 2 (Continued) fpMMITHENT DESCRIPTION l

l SCHEDULE A Item Description Reference Document (s)

3. Decommissioning Rule

]

The rule sets forth technical and financial Final Rule, 53FR240418, criteria for decommissioning. Each utility dated 6/27/88.

must submit a decommissioning funding report by July 27, 1990, containing a certification that financial assurance for decommissioning will be 1 provided by a method acceptable to the NRC and i in an amount that may be more (but not less) than the amount stipulated in the rule.

SCHEDULE B

)

1. Hydrogen Water Chemistry I A Hydrogen Hater Chemistry system 1) BECo Letter #84-146, dated l was designed and installed. This September 11, 1984 l

system is planned for operation in September 2) NRC Letter #1.84.357, i

1989. The procedures for the dated December 4, 1984 operation of the system and training are yet 3) BECo Letter #85-022, to be completed. As a part of the Hydrogen dated February 1, 1985 l l Water Chemistry Program, a Crack Arrest 4) BECo Letter #85-034, l Verification System (CAVS) was installed, dated February 5, 1986 1 5) BECo Letter #85-089, dated April 5,1985  ;

6) BECo Letter #86-136, I dated September 9, 1985 (T.S. Change)

7) NRC Letter, June 17, 1988 l (Am. #118 to T.S.)

2. Control Room Design Review (G. L. 82-33)

By letter (Ref. 5), BECo committed to submit 1) NUREG 0737: Item I.D.1 a supplementary summary report within four (4) 2) BECo Letter #84-159, dated months after the completion of RF0 #7 (i.e.., September 24, 1984 l by April 30, 1989). 3) NRC Letter #85-157, dated May 16, 1985

4) NRC Letter #86-002, dated January 6, 1986

5) BECo Letter #87-008, dated January 20, 1987 Page 2 of 6

w ATTACHMENT 2-(Continued)

~

COMMITMENT DESCRIPTION SCHEDULE B Item Description Reference Document (s)

3. Reaulatory Guide 1.97 (G. L. 82-33)

Generic Letter 82-33 required each licensee to 1) NRC Generic Letter #82-33 review the accident monitoring instrumentation 2) BECo Letter #84-187, dated available at their facility and to compare this November 1, 1984 instrumentation with the recommendation of 3) NRC Letter #85-372, dated Regulatory Guide 1.97. The results of BECo's December 12. 1985 review and comparison for PNPS was provided by 4) BECo Letter #87-021, dated Reference 2. The present known scope of plant February 10, 1987 modifications required to comply with the intent 5) NRC Letter.#85-044, dated of Regulatory Guide 1.97 were committed to be January 24, 1989 completed by the end of RF0 #8. Additional information on compliance was requested by the NRC and supplied by BECo by References 3 and 4, respectively. BECo is currently preparing a response to the additional' request for information contained in Reference 5. This response will be submitted by April 3, 1989. Based on NRC disposition of the remaining issues, additional modifications may be required, which may change the current schedule for final completion.

4. Safety Parameter Disolav System (G. L. 82-33)

A Safety Parameter Display System to 1) NUREG 0737: Item I.D.2 provide a concise display of critical 2) Generic Letter #82-33 plant operating variables will be 3) BECo Letter #84-133, dated implemented at PNPS. The plant August 10, 1984 computer system was replaced and SPDS has been 4) NRC Letter (SER) #85-100, integrated into the new system. (The computer dated March 21, 1985 upgrade is a plant improvement and is not an 5) BECo Letter #85-107, dated NRC commitment). June 13, 1985

5. Seismic Verification Proaram (G. L. 87-02)

As a member of the Seismic Qualification Utility 1) NRC Letter #87-078 (G.L.

Group (SQUG), BECo plans to implement the seismic 87-02) dated February 19, verification program at PNPS through the generic 1987 implementation procedure developed by SQUG. 2) BECO Letter #88-145, dated During Operating Cycle 8 in 1989, 1990, and RF0 October 11, 1988

1. 8, BECo will develop a safe shutdown equipment list; locate, assemble, and/or recreate original design basis seismic documentation for the above identified equipment; provide training for our walkdown team members; and commence the walkdown in accessible areas. The schedule for completion of the seismic verification program will be submitted in a later LTP update.

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ATTACHMENT 2 (Continued)

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COMMITMf,NT DESCRIPTION SCEDMLLfl LttiLQpjcriotion Reference Document (s)

6. Ehysical_1gurity Improvements In response to NRC inspection findings, and as 1) NRC Letter #85-119, dated '

a plant betterment activity, BECo committed April 30, 1985 (RER Report) ,

to replace the security computer and improve 2) I&E Inspection Report 86-08 I upon certain security activities. This includes dated 5/29/86 miscellaneous perimeter improvements and installation of a new security computer and access control equipment.

7. Instrument Air Supply System Problem L Affectina Safet/-Related Eauioment (G. L. 88-14)

BECo submitted initial response by ref erence 2) 1) NRC Generic t.etter 88-14,  ;

I and committed to provide a supplementary dated. August 8, 19EL response by May 31, 1989, on items not completely 2) BECo Letter #89-010, dated addressed in Ref. 2). February 3, 10S9 1

8. NRC Bulletin 88-10. Molded Case Circuit Breakers Bulletin 88-10 requires the review of certain 1) NRC Bulletin 88-10, dated molded case circuit breakers to determine that November 22, 1938 they were procured from circuit breaker i manufacturers (traceability determination) and to test CBs that are not traceable to the circuit breaker manufacturer.

9. Emngency Preparedness Complete Emergency Operations Center 1) FEMA Report, dated renovations, equipment procurement August 6, 1987 and onsite program upgrade identified in the FEMA Report (Ref. 1).

10. I!alletin 87-01. Thinnina of Pioe H uli In response to the Bulletin (Rei. 1), BECo 1) BECo Letter 87-208, stated that we will develop criteria for dated July 19, 1987, determining how frequently to make thickness measurements and develop a database for l

determining erosion / corrosion and specific locations and frequencies of future inspections.

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11. Emeraency Ooeratina Procedures (EOP) Uodata Rewriting of E0Ps and support documentation to 1) IE Inspection Report close the open items identified in the E0P 50-293/ 88-11, dated Verification Summary Report. May 17, 1988

2) NRC SER dated June 6, 1988 (TAC No. 44328)

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ATTACHMENT 2 (Contit.ued)

COMMITMENT DESCRIPTIQM 1.

SCHEDULE B Item Dascriotion' Reference Document (s)  ;

I 12. IE Bulletin A3 MOV Common Mode Failure Testing This Bulletin requests licensees to develop 1) NRC Bulletin 85-03, and implement a program to ensure that switch dated November 15, 1985 settings on certain safety related MOV's are 2) BECo Letter #87-183, selected, set and maintained correctly. BEco1 dated November 13, 1987 committed (Ref. '2) to submit its final report on the results of testing to be performed after full power + 120 days. This schedule is dictated by.the need for system steam pressure to complete the tests.

P1P_S RESTART REPORT COMMITME_NIS In the PNPS restart report, BECO committed 1) BECo Letter #88-140, to complete certain activities on a long dated Septeinber 28, 1988 term basis. Activities 13 thru 17 are I identified with schedules as committed in the restart report.

13. Generic Latter 83-2fl (Items 2 1 & 2.2) BECo committed to complete evaluation of existing Vendor Interface activities and l identify recommendations to improve upon vendor interface activities.

14. Salt Service Hater Pioinq Corrosion A. Define inspection criteria for Salt Service l Water piping B. Identify improved materials for Salt Service Hater piping ,

15. Electrical Use of Fuses and Metal links in Control gircuitry A. Correct and revise fusable link drawings based upon walkdowns Page 5 of 6

ATTACHMENT 2 (Continued)

(

COMMITMENT DESCRIPTION )

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SCHEQUlf_B f I

Item Description Reference Document (s)

8. Perform engineering evaluation to replace metal links. Review non-safety related MCC drawings for metal links that require replacement with fuses.

1 C. Implement design change to replace metal links  :

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16. Igniement Root Cause and Corrective Actions to Address Causes of Held Failure Replace RHR Vent Valves, if required, investigate alternatives to throttling globe and gate valves su j review methods to establish MOV thrust.

17. Realignment of Core Sorav Check Valves l

l Replace and or realign check valves currently in vertical position 4

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y ATTACHMENT 3 I

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PROGRESS SINCE MARCH 19E SCliEDULE._6 Status  ;

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- Appendix R Modifications Complete

- ATHS Rule Compliance: Complete SLCS Modification Complete ECHEDULE B

- IE Bulletin 80-11: Additional Masonry Hall Complete

. Modifications 1 l

- IEB 84-02 HfA Relay Replacement Program Complete

- Hydrogen Water Chemistry

• Conduct Feasibility Studies Complete i

• Install Test System Complete i e Install Primary System Continuing (See Attachment -1) '

- Emergency Operations facility (Offsite) Construction Complete

- Submittal of Augmented Inspection Program of Complete '

Piping Susceptible to IGSCC

- Analog Trip System Complete

- Reactor Water Level Complete

- Hydrostatic Tests, Class II and III Complete

- CROR - Operator Work Stations Complete

- Radiological improvement Program, Improved Complete HP access control area for Process Building

- IE Bulletin 85-03 BECo participated with BHROG and developed a generic analysis to address the concerns identified in the ,

Bulletin. The completion of testing will be 90 days after full power is reached, and test results will be provided 120 (BECo letter l

87-183) days after i

completion of testing, 611ditional Items

- Fuel Pool Rerack Complete

- Radwaste Betterment (fuel pool filter Complete replacement only. Haste concentrator removal is in hold) fqe 1 of 2

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ATTACHMENT 3 Continued)  !'

PROGRESS SINCE HARCH 1986 Mditional Items (continued) Status

- Plant Computer Replacement Complete except for testing and upgrading of software  !

- Control Room Recorders Complete

- Refuel Bridge Replacement Complete

- Secondary Containment Da:nper Replacement Complete

- BWR Nuclear Instrument Dry Tube Inspect / Replace 11 replaced, I recaining

- BWR Shroud Head Bolt Inspection Complete 1

- BWR In-vessel Instrument Line Inspection Complete I

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.v-ATTACHMENT 4 j

SUMMARY

OF CHANGES AND REASONS  ;

ASSOCIATED HITH REGULATORY 1 REQUIREMENTS Schedule A -

ATHS SLCS modification which was originally scheduled for RF0 #8 was completed in RF0 #7. q Schedule B  !

SPDS/ Computer 81olacement l l

The completion date for the SPDS has been extended to December 1989 because of our  !

commitment to monitor the Analog Trip System (ATS). He also are receiving new l software for the Emergency Operating Procedures (EOP's). These items are discussed  ;

below. i In 1987, the nuclear industry identified problems with " ringing" (harmonic type I mechanical noise) in Rosemount 1154 Transmitters. On January 29, 1988 the NRC' issued BECo a letter identifying this as one of six items to be addressed for the 1 Pilgrim Power Ascension Program. In BECo's letter of February 29, 1988 (2.88.033)  !

we committed to conducting a surveillance program. The Power Ascension Program was further discussed in an NRC/BECo Hanagement Meeting held at the Region I offices on April 8, 1988 (NRC letter dated May 17, 1988, 1.88.173) and we committed to submitting additional information on the transmitter problem.

In BECo's letter of August 4, 1988 (letter 2.88.117) we stated that we would use the Emergency and Plant Information Computer (of which SPDS is a part) to monitor Rosemount transmitters in the ATS. This approach was discussed in a NRC/BECo  ;

meeting held at the Region I offices on August 31, 1988 (NRC letter dated September '

i 7, 1988, 1.88.327). The NRC staff agreed with our conclusion that this is not a l safety issue but that monitoring these transmitters during the Power Ascension l Program is desirable: To perform this monitoring, fifty-six new signals were added I

to the EPIC system. This transmitter monitoring will continue throughout the Power Ascension Program. SPDS operability testing cannot be completed until after the l' ATS monitoring is complete.

Also, we plan to install software that will include the capability to upgrade the SPDS to accomodate Revision 4 of the E0P's. This revised software will also incorporate corrections previously identified by BECo during factory and site I acceptance testing. This new software is expected to be delivered in March 1989 with installation scheduled to be complete after the Power Ascension Program.

Deferring operability testing of the SPDS until this software is added will eliminate the need to repeat system testing and the subsequent procedure revisions and operator training.

Our current schedule calls for the ATS monitoring to be completed during the Power Ascension Program. Following this, the software will be installed and there will be several months of operability testing. Plant operator training is scheduled to be conducted in November and Deceinber 1989.

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l ATTACHMENT 4 (Continued)

SUMMARY

OF CHANGES AND REASONS ASSOCIATED HITH REGULATORY REQUIREMENTS 1

j Can. trol Room Dni.ign Review I l

In a meeting on April 18, 1986 between NRC and BECo, it was agreed that a 1 supplementary summary report would be submitted to the NRC four (4) months after i RF0 #7. This report will inglude a committed scope and schedule for the j implementation of identified ccrrective actions, a discussion of items requiring further review and response to NRC Safety Evaluation Report. The existing data on .

control room discrepancies is over four years old. In accordance with NRC  !

suggestion, BECo will perform a new data collection effort (including system I function task analysis) before making major panel modifications. This new effort I will be scoped and scheduled in the supplementary summary report.  !

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