ML20213H120

Forwards NRR Input for Commissioner Carr Info Package on Facility,Per Request.Nrr Will Provide Support for Carr 870522 Site Visit

ML20213H120
Person / Time
Site:	Pilgrim
Issue date:	05/08/1987
From:	Wessman R Office of Nuclear Reactor Regulation
To:	Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
2.206, NUDOCS 8705190152
Download: ML20213H120 (4)

Text

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i g 0 81987 MEMORANDUM FOR:

,1arres T. Wiggins, Section Chief 83 Division of Reactor Projects, Region I FROM:

i Richard H. Wessman, Project Manager Project Directorate I-3 Division of Reactor Projects I/II

SUBJECT:

NRR INPUT FOR C0fiMISSIONER CARR INFORMATION PACKAGE ON PRif GRm Attached is the NRR input for Commissioner Carr's information n package o Pilgrim, submitted in response to your request.

NRR will provide support as necessary for Comissioner Carr's visit to Pilgrim on May 22, 1987 .

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Richard H. Wessman, Project Manager Project Directorate I-3 Division of Reactor Projects I/II

Enclosure:

As stated cc: V. Nerses B. Boger W. Kane I

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i PILGRIM - NRR PROXCT, MANAGER ' ASSESSMENT BECo has had a good history of a. technically capable and responsive licensing organization; however recently there have been instances of slow responses to requests for additional information, poor handling of known Technical Specification weaknesses, reluctance to provide information and cancelled meetings. BECo's recent SALP ev'aluation ih this area was "2", down from a "1" tho previour period. The following summarize major licensing issues:

Y. The most significant licensing action in NRR affecting the Pilgrkm facility is response to the'10 CFR 9.706 Petition submitted

' July 15, 1986, by William B. Golden and others. Petitioners request that BECo,show cause why Pilgrim should not remain shutdown until REco demonstrates that certain issues are: resolved. Petitioners assert as grounds for their petition (1) numerous deficiencies in licensee management, (2) inadequacy of the existing radiological emergency

"; response plan and (3) . inherent deficiencies in the facility's containment s truc tu re. Staff is developing Director's response to management and containment issues. Response on emergency response plan issue is dependent on FEMA evaluations, currently in progress.

2. About15TechhicalSpecificationchangesorlicensingactionsareexpected to be necessary in the next few months. Many of these are dependent on

, submittals to be received from REco in the next 30-60 days and result from plant modifications, refueling or technical specification deficiencies t

identified during the current outage. Completing these actions to support restart may require extra NRR resource commitments.

3. BEco is voluntarily planning several enhancements to its Mark I contain-ment including modifications that would permit direct venting from the torus to the main stack, a modification to the containment spray nozzles, installation of a fire-water intertie to RHR system, procedure changes, a modification to the nitrogen system, and the addition of a third diesel generator. These will be completed before restart from present refuelino outage (R0 7).

4 Several deficiencies in the Fire Protection Program have been identified as a result of NRC's review o' the program and inspections. These are in the areas of maintenance, degraded fire barriers, excessive *use of fire watches as compensatory measures and inadequate training. Staff is also reviewing the reauested exemptions from Appendix R. BEco has committed to resolve all open items prior to restart from RO 7 The NRC fire protection audit was conducted the week of May 11, 1987.

5. BECo is one of the first facilities to install a permanent hydrogen water chemistry process. This will be completed prior to restart from RO 7.

The system will iniect hydrogen into the reactor coolant via the feedwater system to reduce the dissolved oxygen concentration. Reducing the dissolved oxygen concentration and maintaining high purity in the reactor coolant should reduce the susceptibility of reactor piping and materials to intergranular stress corrosion cracking.

6. As a result of NRC's review of the Control Room Design Review report, BECo has informed the staff of its intention to re-screen the Human Engineering Discrepancies using a more detailed process than previously used. The schedule for the supplementary sunnary report is 4 months following the end of R0 7.

7. On July 13, 1084, the NRC staff, by Amendment No. 75 to the license, approved BEco's Plan for an integrated program for scheduling safety modifications at the Pilgrim Station. The program integrates the engineering, procurement and installation of planned NRC-required modifications with BEco's own requirements for plant modifications, maintenance, refueling, and operations. The semi-annual update to this plan, however, is overdue.

~ 8. Over the last few years, the licensee has requested may TS changes which should be either withdrawn or modified to reflect the current plant design. BEco was infomed and is currently reviewing all the previous TS change requests.

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9 DISTRIBUTION Docket or Central: File NRC Local PDRS*

PD I-3 Reading File VNerses RWessman MRushbrook 1

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