ML20196F459

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Discusses Minutes of Util Restart Assessment Panel 880630 Meeting Re Status of NRC & Licensee Activities Associated W/ Proposed Plant Restart
ML20196F459
Person / Time
Site: Pilgrim
Issue date: 07/12/1988
From: Collins S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Russell W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20150E198 List:
References
FOIA-88-198 NUDOCS 8812130090
Download: ML20196F459 (7)
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.~ $8 '00 UNITED STATES 4

i-NUCLEAR REGULATORY COMMISSION

' 3- f': I. REGION I c5 ALLENoALE ROAD y

% KING OF PRUSSIA, PENNSYLVANIA 19408 JUL 121988 MEMORANDUM FOR: William T. Russell Regional Administrator FROM: Samuel J. Collins, Deputy Director Division of Reactor Projects

SUBJECT:

PILGRIM RESTART ASSESSMENT PANEL MEETING MINUTES On June 30 1988, the Pilgrim Restart Assessment Panel met onsite to discuss the status of NRC and licensee activities associated with the proposed plant Restart. The following personnel were in attendance:

Chairman: Samuel J. Collins, Deputy Director, Division of Reactor Projects (ORP)

Members: A. Randy Blough, Chief, Reactor Projects Section No. 38, ORP (By Teleconference)

Richard H. Wessman, Director, Project Directorate I-3, Office of Nuclear Reactor Regulation (NRR) (By Teleconference)

James T. Wiggins, Chief, Reactor Projects Branch No. 3, ORP Ronald R. Bellamy, Chief, Facilities Radiological Safety and Safeguards Branch, Division of Radiation Safety and Safeguards (DRSS) (Part-Time)

Daniel G. Mcdonald, Project Manager, NRR Others: Lawrence T. Doerflein, Project Engineer, RPS 38, ORP (By Teleconference)

Frank M. Akstulewicz, PO I-3, NRR (By Teleconference)

Cynthia A. Carpenter, Resident Inspector - Yankee Frank J. Congel, Acting Director, ORSS William O. Travers, Chief, Emergenecy Preparedness Branch, NRR (Part-Time)

Clay C. Warren, Senior Resident Inspector Jeffrey J. Lyash, Resident inspector Tae K. Kim, Resident Inspec ;r The panel discussed the issues from the last meeting, as well as the overall integration of NRC inspection and review activities. As a result of the meet-ing, the below listed actions with responsibility were agreed upon by the Panel.

A panel meeting will be held at Headquarters (NRR), July 15, 19CS, at 10:00 a.m. (Bridge No. 492-9894). All items below will be u pd a *.e d . No separate agenda will be provided for the July 15 meeting.

8912130090 081208 J NS Oh-190 PDR ,

, Memorandum for William T. Russell 2 dO[ l2 [30$ ,

Task Responsibility Due Date

1. Plant Status Update Resident Inspector Next Panel
2. Staffing / Organization Update Resident fai, vector Next Panel
  • Obtain Experience Matrix Blough July 18 frem BECo as part of IATI Preparation
3. Site Inspection Activities Resident Inspector Next Panel Update
4. Update fire barrier issue Roger /Blough Next Panel status of BECo submittal
5. Review and update NRC Restart All Next Panel checklist
6. Provice OIL Updates All Next Panel
7. Indapendent Assessment Team Inspection Plan
  • Provide final comments All Next Panel e Assemble team briefing Blough Next Panel 4

packages

  • Update IATI Organization Blough Next Panel Chart / Team Members
8. NRR to continue liaison w/ACRS Boger Next Panel staff to reach agreement on involvement and scheduling
9. Restart Assessment Report -- All Next Pinel Begin work IAW assignments-discuss each panel ,
10. Update Overall Milestone Collins Next Panel Schedule
11. Update Subset Milestone All Ongoing Schedules

+ Update EP Subset Bellamy Next Panel

  • Provide comments to Mcdonald Next Panel 2.206 Subset

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  • Memorandum for William T.. Russell 3 Task Responsibility Due Date
12. Update Status of Power Ourr Next Panel Ascension Program Deficiencies
13. SEP issues Status Beger Next Panel
14. Self-Assessment Report Review Doerflein Next Panel
15. IATI Request Letter Review Blough Next Panel (BEco Ltr.88-099,6/25/88)
16. Maintenance Inspection Response ORS /Blough Next Panel Review (BECo 88-098,6/25/88) ue , o ins, eputy Director Division of Reac'.or Projects

Enclosures:

1. Pilgrim Overall Milestone Schedule, Revision 7
2. Pilgrim Subset Milestone 2.206 Approach, Revistan.1
3. Pilgrim Subset Milestone Topic Listing, Revis'on 7 l

Memorandum for William T. Russell 4 M j g ]ggg cc w/encis:

T. Murley, NRR F. Miraglia, NRR T. Martin, NRR S. Varga, NRR B. Boger, NRR R. Wessman, NRR

0. Mcdonald, NRR F. Akstulewicz, NRR J. Roe, NRR J. Hannon, NRR W. Re an o

, t., ayton, E00 J. Allan, RI W. Kane, RI J. Wiggins, RI R. Blough, RI G. Sjoblom, RI J. Ourr, RI R. Bellamy, RI L. Doerflein, RI M. Kohl, RI C. Warren, SRI - Pilgrim J. Lyash, RI - Pilgrim T. Kim, RI - Ptigrim

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ENCLOSURE 3 4

Subset Milestones Topic Listing ,

Area Responsibility i A. Overall Milestones S. Collins l B. Public and State Involvement R. 81ough Meetings with Licensee C. NRR Actions for Restart D. Mcdonald O. Management Transition C. Warren E. Site Inspections / Reviews R. Blough F. EP Status R. Bellamy/F. Congel G. Power Ascension Program J. Ourr H. 2.206 Item Closecut Approach R. Wessman i

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Pilgrim Subset Milestones 6/30/88 Rev. 7 f

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/"%g UNITED STATES

! n NUCLEAR REGULATORY COMMISSION

, f OFFICE OF GOVERNMENTAL AND PUBLIC AFFAIRS, REGION I 475 Allendate Road, King of Prussia, Pa.19406

...../ Tel. 215 337 5330 No. I-88-120 July 28, 1988

Contact:

Karl Abraham NOTE TO EDITORS AND STATION ASSIGNMENT EDITORS A. Randy Blough, Chief of the Reactor Projects Section that inspects Pilgrim has issued a status report summarizing activities of the inspection staff during the period July 2 to 15, 1988.

The report is attached.

July 25, 1988 Docket No. 50-293 HEMORANDUM FOR: James T. Wiggins, Chief Reactor Projects Branch No. 3 FROM: A. Randy Blough, Chief Reactor Projects Section 3B

SUBJECT:

PILGRIM STATUS REPORT FOR THE PERIOD JULY 2 - 15, 1988 Enclosed is the Pilgrim bi-weekly status report from the NRC Resident Office at Pilgrim. Three resident inspectors monitored activities at the plant during the report period. During the week of July 4, 1988, a Systematic Assessment of Licensee Performance (SALP) board meeting was held for Pilgrim at the NRC Regional office in King of Prussia, Penrisylvania. The SALP assessment covered the period of February 1, 1987 through May 15, 1988. The SALP report will be issued upon completion of NRC management review. By a letter dated July 11, 1988, the NRC notified the licensee management that the NRC has completed its review of the licensee's Self-Assessment Report and the associated action schedules for restart. The NRC has tentatively scheduled a comprehensive Integrated Assessment Team Inspection (IATI) to begin on August i 8, 1988. Onsite preparation for the IATI will be conducted during July 19 -

l 21, 1988.

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The Pilgrim bi-weekly status report is intended to provide NRC management and r the public with an overview of plant activities and NRC inspection activities.

Subsequent inspection reports will address many of these topics in more detail.

(Original signed b F. I. Young, for) y i A. Randy Blough, Chief Reactor Projects Section 3B

Enclosure:

I As Stated l L

ENCLOSURE l

PILGRIM STATUS REPORT FOR THE PERIOD JULY 2 - 15,19% ,

1.0 Plant Status As of 8:00 a.m., on July 15, 1988, the reactor was in cold shutdown mode l with moderator temperature about 96 digrees Fahrenheit. l 3 2.0 Facility Ooerations Summary The plant has been shutdown for maintenance and to make program  ;

improvements since April 12, 1986. The rector core was completely i defueled on February 13, 1987 to facilitate extensive maintenance and l modification of plant equipment. The licensee completed fuel reload on '

October 14, 1987. Reinstallation of the reactor vessel internal components and the vessel head was followed by completion of the reactor vessel hydrostatic test. The primary containment integrated leak rate test was also completed during the week of December 21, 1987. During l

f this period, the licensee performed routine maintenance and surveillance i tests. Some of the ongoing projects include: degrade voltage protection modification, DC electrical breaker testing, and RHR low pressure coolant injection valve repair work.

) 3.0 Items of Special Interest

! Pilgrim Systemmatic Assessment of Licensee Performance (SALP) Board -

l l Meeting  !

l l The SALP process is supplemental to the normal regulatory processes used l

, to ensure compliance to NRC rules and regulations. It is intended to be '

sufficiently diagnostic to provide a rational basis for allocating NRC [

resources and to provide meaningful guidance to licensee management in  !

! order to improve the quality and safety of plant operations.  !

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On July 5-6, 1988, a SALP board meeting was held for Pilgrim at the NRC  !

Regional Office in King of Prussia, Pennsylvania. The SALP assessment i covered the period of February 1, 1987 through May 15, 1988. The SALP board, composed of members from NRC management in Region I and NRR, reviewed the collection of performance observations and inspection results by the resident inspectors and regional inspectors in order to assess the licensee's performance at the Pilgrim station. The SALP report will be issued upon completion of NRC management review. During ,

the SALP period, the NRC expended a total of 9698 direct inspection hours at Pilgrim which is substantially above the typical level of inspection effort, NRC Assessment Panel Meeting A NRC Assessment Panel meeting for Pilgrim was held on July 15, 1988 at the NRC headquarters offices in Rockville, Maryland. NRC management from Region I and the NRC resident staf f participated via tele-conference.

NRC Assessment Panel meets periodically tu coordinate preplanning and execution of NRC inspection and licensing activities related to Pilgrim.

The Panel is chaired by Mr. Samuel J. Collins, Deputy Director, Division of Reactor Projects, NRC Region I.

Scheduled NRC Integrated Assessment Team Inspection (IATI) j By a letter dated July 11, 1988, the NRC notified the licensee management a

that the NRC has completed its review of the licensee's Self-Assessment Report and the associated schedules for resolution of remaining items prior to restart. The NRC has tentatively scheduled a comprehensive IATI to begin ,n August 8,1988. Onsite preparation for the IATI will be conducted during July 19 - 21, 1988. The IATI will independently review the licensee's readiness for restart. Development of an NRC staff recommendation to the Commission relative to restart will be based on the SALP and IATI results.

The team will consist of a senior manager, inspection team leader, four shift inspectors, and several specialist inspectors from both Region I and the Office of Nuclear Reactor Regulation. The senior manager is Mr.

Samuel J. Collins, Deputy Director, Division of Reactor Projects, Region I, and the team leader is Mr. A. Randy Blough, Section Chief, Reactor Projects Section 38, Region I.

Arrangements have been made for a representative from the Conmonwealth of Massachusetts to be on the team as an observer throughout the IATI.

4.0 Emergency Notification System (ENS) Report During this period, the licensee made the following reports to the NRC i

pursuant to 10 CFR 50.72:

1 (more)

4 On July 5, 1988, an inadvertent reactor scram occurred during electrical maintenance on the intermediate range power monitor (IRM) system. The actuation resulted from spurious spiking of "A" and "B" intermediate range power monitor channels when a third IRM was returned to service. The licensee's preliminary investigation indicated a procedural error contributed to the observed actuation. .

On July 8,1988, the licensee experienced an unexpected reactor scram during performance of a post-modification test on the Anticipated Transient Without Scram (ATWS) system. The ATWS system is designed to provide independent means of introducing negative reactivity to the reactor by tripping the reactor recirculation pumps and initiating the alternate control rod insertion system in i the unlikely event of a reactor protection system failure. The  !

licensee's preliminary investigation determined that all equipment performed as designed and that the cause of the actuation was due to a procedural inadequacy. The test procedure did not identify a potential reactor scram due to high water level in the scram discharge instrument volume.

l On July 12, 1988, an inadvertent start of the "B" emergency diesel generator (EDG) occurred during implementation of clactrical l equipment isolations on associated safety-related 4160 VAC bus. The isolations were being conducted in accordance with an approved work ng sheet. The effect of the isolations on the start plan logic and taggi,B" of the ' EDG, had not been identified.

The NRC inspector's review of these events will be further discussed in Inspection Report 50-293/88-25.

5.0 NRC Staff Status During the Period j The inspection staff at Pilgrim during the report period consisted of the

followir.g

Clay Warren ---

Senior Resident Inspector Jeffrey Lyash ---

Resident Inspector Tae Kim ---

Resident Inspector  !

In addition, a reactor engineer from the regional office was onsite during the week of July 11, 1988 to assist the resident inspectors in reviewing the licensee's corrective actions on previous inspection findings. The results of these inspector activities will be documented I

in the NRC inspection report 50-293/88-25.
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