ML20196F348

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Summarizes Minutes of 871023 Meeting W/Project Manager Re Proposed Schedule & Approach to Response to State of Ma 871015 2.206 Petition
ML20196F348
Person / Time
Site: Pilgrim
Issue date: 10/26/1987
From: Boger B
Office of Nuclear Reactor Regulation
To: Collins S, Miraglia F, Starostecki R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), Office of Nuclear Reactor Regulation
Shared Package
ML20150E198 List:
References
FOIA-88-198 2.206, NUDOCS 8812120270
Download: ML20196F348 (2)
v • d • e


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NOTE TO: F. Miraglia, NRR R. Starostecki, NRR S. Collins, RI FROM: Bruce A. Boger, Assistant Director for Region 1 Reactors Division of Reactor Projects I/i!

SUB.1ECT: RCSPONSE TO MASSACHUSETTS 2.206 PETITION OF OCTOBER 15,1987 REGARDING PILGRIM On October 23, 1987, representatives of Plant Systems, OGC, Emergency preparedness, and Regica 1 (by telephone) met with the Pro.iect Manager and I to discuss the proposed schedule and approach to the response to the Massachusetts 2.206 petition of October 15,1987. Assignments and due dates for inputs to the PM are shown on the Enclosure. Several initial observations regarding our approach are er.ade:

-The initial response to Petitioners (letter of receipt 1 needs to be issued promptly. It nJst put the issue of Petitioners' request for preventing any BECo actions leading to restart (Power Ascension Program) in persnactive with current plant activities that appear to be leading to restarf.

-The mat agement issues appear to call for a response similar to our response of Auoust 21, 1987 to Senator Golden,

-Plant Systems will have to determine if the containrent concerns are essentially the same as the issues dealt with in our response to Senator Golden on August 21, 1987 If additional issues must be dealt with, additional time will be required for their portion of the response.

-Errergency preparedness issues in this Petition are different than thnse issues raised by Senator Golden, and a conclusion regarding these issues may not be possible at this time.

The point of contact for this activity will be R. Wessman. The TAC nunber to be used is 66425.

A Bruce A. Bog r. Assistant Director for Region 1 Reactors Division of Reactor Projects 1/I!

Enclosure:

As stated cc w/ enclosure:

T. Murley A. Thadant 8;fWeTina W. Russell J. Craig J. Kudrick S. Varga F. Congel L. Chandler D. Matthews W. Paton L. Doerflein

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EtiCLOSURE I It4171 AL ASSIGt1MErlTS Ati1> h1LEST0 ties [A 11 Due Ecs ;___

Area s Initial Task assignments 10/03C _

k Restart pernpective i n receipt letter 10/27 RI 10/26 =

PM Receipt let',er to OGC 11/3 PM Receipt let er to Dr. Murley for signature 11/6 o PM Introduction 11/6 ;t Management (Incl. SALPs, securtt f , e n 4'o rc e .

RI 11/13 SPLB SPLB PRA Containment Adequacy (

10/30 Ar.sess if issues similar to Golaen 11/13 If like Golden, devel. respense 10/30 i If unlike Golden, provide approach & sched. 11/6 PEPB Emergency Preparednest 11/20 PM Integrate inputs and nvide te OGC Re n.s ining milesto..ea are primarily .ependent on completion of the

- containment adequacy area, but a dispatch target of early December is desired.

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i 5 OFFICE OF GOVERNMENTAL AND PUBLIC AFFAIRS, REGION I 631 Park Avenue, King of Prussia, Pa.19406 i %,,

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No. 1-87-154 November 3, 1987

Contact:

Karl Abraham NOTE TO EDITORS AND STATION ASSIGNMENT EDITORS Allen R. Blough, Chief of the Reactor Projects Section that inspects Pilgrim nas issued a status report summarizir.g activities of the inspection staf f during the period October 8-21, 1987.

Be report is attached.

October 27, 1987 Docket No. 50-293 MLMORANDUM FOR: James T. Wiggins, Chief Projects Branch No. 3 FROM: Allen R. Blough, Chief Reactor Projects Sec. tion 3B

SUBJECT:

PILGRIM STATUS REPORT FOR THE PERIOD OCTOBER 8 - 21, 1987 Enclosed is the Dilgrim bi-weekly status report from the NRC Resident Office at Pilgrim. The resident inspectors and a region-based specialist inspector monitored activities at the plant during the report period.

Toese status reports are intended to provide NRC management and the public with ar overview of plant activities and NRC inspection activities. Subsequent inspection reports will address many of these topics in more detail.

Allen R. Blough, Chief Reactor Projects Section 3B

Enclosure:

As stated (more)

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. 2 ENCLOSURE  :

PILGRIM STATUS REPORT FOR THE PERIOD OCTOBER 8 - 21, W

1. 0 Plant Statuj Currently the plant is in the cold shutdown mode with all 580 fuel assem-blies in the reactor vessel. As of 9:00 a.m. on October 21, 1987, the licensee was in the process of reinstalling the reactor vessel internal components.

2.0 Facility Operations Summary The plant has been shutdown for maintenance and to make program improve-ments since April 12, 1986. The reactor core was completely defueltd on

February 13, 1987 to facilitate extensive maintenance and modification of l piant equipme't. The licensee completed fuel reload on October 14, 1987.

3.0 Items of Special Interest Meeting between the NRC and Officials Representing the Commonwealth of Massachusetts l

l On October 8, 1987, a meeting was held in NRC Region I offices to discuss a variety of issues affecting the Commonwealth of Massachusetts. The j meeting was scheduled at the request of Peter Agnes, Massachusetts Assistant Secretary of Public Safety. In attendance from Massachusetts j

were representatives of the Governor's Office, the Attorney General's j Office, the Massachusetts Civil Defense Department and State Representative Alexander.

Senior NRC Region I and Office of Nuclear Reactor Regulation management

.' were present. In addition, two private citizens, Mary Ott and Dr. Donald

{ Muirhead attended and made brief statements. The topics discussed during the meeting will ta documented in minutes and will be available in the

public document room.

l Completion of Fuel Reload The licensee began refueling on September 29, 1987. The last of the 580

( fuel assemblies was inserted into the reactor at 11:25 a.m. on October 14.

Following completion of fuel reload, the licensee performed control rod friction testing and the final visual inspection of the reactor vessel core. The visual inspection of the core, including an independent verification with an underwater camera, ensures that all the fuel assemblies have been placed into the correct locations within the reactor vessel.

(more)

3 NRC resident and regional inspectors monitored refueling activities on a continuous basis for the initial forty eight hours, and subsequently provided augmented coverage during both normal and backshift hours. The results of these insper:tions as well as NRC monitoring of t5e licensee's preparations for the start of refueling, will be documented in NRC inspection report 50-293/87-45. Currently, the licensee is in the process of reinstalling the reactor 'iessel internal components. This act(vity could take about ten days and will be followed by vessel hydrostatic testing.

10 CFR 2.206 Petition On October 15, 1987, Massachusetts Attorney General James M. Shannon filed a petition with the NRC requesting an order to show cause why the Pilgrim Nuclear Power Plant should not remain closed until a full adjudicatory hearing resolves the issues identified in the petition. The petition requests that, pending further review, the Boston Edison Company be prevented from proceeding with the restart and power ascension of Pilgrim.

The petition was filed by Shannon on behalf of his of fice and Governor Michael S. Dukakis. The material provided is currently under review by the NRC.

Emergency Siren Test On October 15, 1987, at 4:00 p.m., the licensee tested the 97 siren network around the Pilgrim Nuclear Power Station. The sirens would be used in an actual emergency to alert residents within the 10 mile radius of the plant to turn on their radios to the Emergency Broadcast System stations. The siren test is performed annually in accordance with the

{ Federa! Emergency Management Agency (FEMA) guidelines. The licensee j notified FEMA, the state, and the local towns prior to the test.

4.0 Emergency Notification System (ENS) Reports During this period, the licensee made three ENS reports to the NRC pursuant to 10 CFR 50.72:

l On October 8, 1987, a plant worker observed a security guard at his i post with his eyas closed. The guard was assigned to control access l to a plant security area while maintenance was underway. The guard had assumed the post responsibilities approximately one half hour

! earlier. When informed, the licensee's on-shift security supervisor j relieved the individual and initiated security followup actions.

l Investigation by the licensee indicates that the guard had been l inattentive for less than two minutes. The resident inspectors are

monitoring licensee corrective actions.

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l. _ _ _ - - , . _ _m,-

o On October 15, 1987, a spurious partial primary containment isolation signal (PCI3) ws: rc:cised, resulting in the automatic isolation of the shutdown cooling system. A contractor electrician implementing an approved plant design change lifted a PCIS wire from its associated terminal board to allow installation of new wiring.

Lif ting of the wire deenergized a portion of the PCIS which in turn caused two shutdown cooling suction isolotion valves to close and the inservice residual heat removal pump to trip. All equipment functioned as designed in response to this error. The licensee investigated the isolation, reinstalled the wire and reset the isolation signal a short time later.

Ouring performance of an average power range monitor (APRM) calibration on October 18, 1987 a spurious reactor scram signal was generated. Instrument aid controls (I&C) technicians were performing caifbration of the 'A' APRM. A hal f-scram signal had been intentionally generated as a result of this testing. The calibration procedure required that the 'A' APRM mode switch be turned to the "test power" position. The technician inadvertently operated the 'O' APRM mode switch which is located directly under the 'A' APRM switch.

Inadvertant removal cf the 'O' APRM f rom service by operation of its mode switch completed the logic needed to g'nerate the full scram.

The unit was shutdown with all control rods insarted at the time of the scram.

5.0 NRC Staff Status Durino the Period

, The inspection staf f at Pilgrim during the report period consisted of the following:

l j Jeffrey Lyash ---

Resident Inspector Tae Kim ---

Resident Inspector l

l Frank Crescenzo ---

Resident Inspector (Shoreham)

! In addition, one regional specialist inspector was onsite during the week

, of October 19, 1987 to review licensee corrective actions in response to l previous inspection findings. The results of this inspection will be

! documented in NRC inspection report 50-293/87-46.

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