ML20196F424
| ML20196F424 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/09/1988 |
| 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 8812130078 | |
| Download: ML20196F424 (6) | |
Text
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g, "y-FEB 091988 MEMORANDUM FOR: William T. Russell Regional Administrator FROM: Samuel J. Collins, Deputy Director Division of Reactor Projects ,
4
SUBJECT:
PILGRIM RESTART ASSESSMENT PANEL MEETING MINUTES On February 2, 1988, the Pilgrim Restart Assessment Panel met by teleconference e 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, DRP Members: Ronald R. Bellamy, Chief, Radiological Protection and Emergency Preparedness Branch, ORSS J. Durr, Chief Engineering Branch, DRS A. Randy Blough, Chief, Reactor Projects Section No. 3B, ORP Bruce Boger, Asststant Director for RI Reactors, NRR Richard H. Wessman, Director, Project Directorate I-3, NRR Others: Daniel Mcdonald, Project Manager, NRR 4 Clay C. Warren, Senio, Resident Inspector, Pilgrim Jeff Lyash, Resident Inspector, Pilgrim i T. J. Kim, Resident Inspector, Pilgrim H. Gray, Senior Reactor Engineer, MPS, DRS M. Evans, Operations Engineer, BWRS, DRS Lawrence T. Doerflein, Project Engineer, RPS 38. DRP ,
The panel discussed the issues li'. V ' .i Enclosure 1. As a result of the ;
meeting, the below listed actions with responsibility were agreed upon by the Panel.
l The next panel meeting will be held onsite at 1:00 p.m., February 17, 1988. ,
All items below will be updated. No separate agenda will be provided for the ,
'r*ebruary 17 meeting.
< Task Responsibility Due Date
- 1. 10 CFR 50, Appendix r Issues:
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- Couplete review of control NRR Est. April 1 room floor exemption request
- Submit exemption request on BECo Est. February 6 conduit sealing I
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f 8812130070 081208 "S$NS Oh-198 PDR
, . Merdoranoum for William T. Russell 2 ((gQgj@@@
Task Responsibility Due Date t
- 2. Arrange transcription service Blough ASAP for February 18 public meeting
- 3. Formalize system for identifying Doerflein February 12 and tracking (to resolution) [
public comments on Restart Plan j
- 4. Open Items - Designate who will Ourr/Bellamy/ Next Panel h I
close and who controls packages Boger/Blough/ SRI
- 5. Review Restart Plan Task Force February 12 r l
- 6. Provide comments on Readiness All Next Panel !
Report Format .
- 7. Inform BEco of 50.38, basis for Mcdonald Next Panel j removing Tech Specs on organization ,
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- 8. Develop TAC for review of Boger Next Panel [
Direct Torus Vent proposal l I
- 9. Discuss deficiencies with Collins Next Panel l Power Ascension Program ,
with BEco l
- 10. Provide comments on Draft Doerflein February 4 !
Response to State 2.206 i Petition
- 11. E0P Status
- Letter to BEco confirming Boger Next Panel delay and new date for onsite review ;
Provide new schedule BECo (response)
- 12. Discuss Readiness Assessment Blough Next Panel Team Inspection Plan
- 13. Discuss INPO evaluation schedule Collins Next Panel ,
with BEco e
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A D.IAAw^' h1 .
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' Memorandum for William T. Russell 3 FEB 091988 1 i i
Task Rtsponsibility Due Date
- 14. Develop form letter for Doerflein Next Panel acknowledging receipt of written public comments
- 15. Discuss team inspection schedule Collins Next Panel with BECo l O!W amue . o ins, Deputy Ofrector Division of Reactor Projects ,
Enclosure:
As stated
, cc w/ encl-T. Murley, NRR i F Miraglia, NRR :
., S. Varga, NRR B. Boger, NRR R. Wessman, NRR r D. Mcdonald, NRR l J. Roe, NRR r J. Hannon, NRR i
J. Allan, RI W. Kane, RI J. Wiggins, RI R. Blough, RI T. Martin, RI
( J. Durr, RI R. Bellamy, RI ,
L. Deerflein, RI R. Fuhrmeister, RI C. Warren, SRI - Pilgrim J. Lyash, RI - pilgrim T. Kim, RI - Pilgrim l i
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$NCLOSUE2 Restart Panel Items Discussed February 2. 1988
- 1. 10 CFR 50, Appendix R issues of control room floor and conduit sealing.
- 2. Status of preparations for February 18, 1988 public meeting.
- 3. Status of the administrative Technical Specifications conesrs.ing recent orga.nizational changes.
- 4. Status of open item review.
- 5. Status of Task Force for Restart Plan review and public comment resolution.
- 6. Format for Readiness Report.
- 7. Results of NRR review of the Direct Torus Vent proposal.
- 8. Status of Power Ascension Program review.
- 9. Status of Region I review of draft response to State 2.206 Petition.
- 10. Status of E0P implementation and schedule for onsite review,
- 11. Review of plant status.
- 12. Review of recent inspection findings.
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ARE SHOWN. 11EED TO HEAR 6AC/ PROMPTL'I IF YOU g" 9J5 Ol$ AGREE.
TABLB 0F CONTENTS 'U'M/$ b~~l Af+r THANKS WF7~//U lTJ,Q 6 au RANDY B. T. alt "i
- 1. E x e c u t i ve s uavna ry . . . . . . . . . . . . . . . . . . . . . . . . . . .h. . e.n/ 7As(4.
II. Introduction.............................D.k.T 9 4 N ON A. Purpose...................................
B. Background................................
III. Systematic Assessment of Licensee Performance.49.W/ -WWn A. Sunnary (47 99. period. areas covered.etc)..
B. Results...................................
IV. Integrated Assessment Team _. Inspection.........Y " b W 4. !
4 A. Sunnary (areas covered. insp plan. etc)
. B. Results...............................t (
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V. Boston Edison Restart Plan & Self Assessment. P.*GWCd' B4w.n CrA R N e )/
A. Summary of NRC Request and Review Process.
B. Results of NRC review..................... (
C. Disposition of public corzents............
VI. jpstonFdisonPowerAscensionProter.m.......9.M!0MO A. R e sul t s o f t'RC r ev i ew . . . . . . . . . . . . . . . . . . . . . "
l B. Planned NRC inspection activities during startup...........................
VII. Confirmatory Action Letter No. 8610........h. 4II J r A. Licensee corrective actions. . . . . . . . . . . . . . . t B. Status of NRC review and acceptance.......
g h g ~i VIII .Manaument Meet ina 86 41 I s sue s. . . . . . . . . . . . . . 'Th .k'
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A. Licensee corrective actions...............
g' w u .y # L.,; . B. Status of NRC review and acceptance.......
s,\ ,b .,% ~ ~ ~ - - - -- _ _ D (b if 8 dks ,)
y M. Overall conclusion.............................
Au. ** Whl,}
A.
B.
Outstanding Recocusendation issues / licenserestart........
regarding conditions... M.. "- Ah Attachments
- 1. SALP Report No. 87 99
- 2. Integrated Assessment Team Inspection Rpt
- 3. Disposition of public coesoents
- 4. BECo Self Assessment Rpt
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. W f""" %,, UNITED STATES 5,
j NUCLEAR REGULATORY COMMISSION OFFICE OF GOVERNMENTAL AND PUBLIC AFFAIRS, REGION l i
475 Allendale Road, King of Prussia, Pa.19406
%, . . . . . ,/ Tel,215 337 5330 No. I-87-23 March 11, 1988
Contact:
Karl Abraham NOTE TO EDITORS AND STATION ASSIGNMENT EDITORS James T. Wiggins, Chief of the Reactor Projects Section that inspects Pilgrin: has issued a status report sur'es 'izing a.ctivities of the inspection staff during the period February 13-26, 1988.
The report is attached.
t March 4, 1988 Occket No. 50-293 MEMORANDUM FOR: James T. Wiggins, Chief Reactor Projects Branch No. 3 FROM: A. Randy Blough, Chief Reactor Projects Section No. 3B SUB 'ECT: PILGRIM STATUS REPORT FOR THE PERIOD FEBRUARY 13-26, 1988 Enclosed is the Pilgrim bi weekly status report from the NRC Resident office at Pilgrim. Three resident inspectors and a region-based inspector monitored activities at the plant during the report period. On February 17, 1988, senior management representatives from both NRC Region I and NRC Office of Nuclear Reactor Regulation (NRR) were onsite and met with the resident inspectors. On February 18, 1988 NRC conducted public meetings at the Plymouth Memorial Hall, in Plymouth, Massachusetts to receive public corments on the Boston Edhon's Pilgrim Restart Plan.
The status reports ~.re intended to provide NRC management and 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 by) l A. Randy Blough, Chief Reactor Projects Sectic's No. 3B
Enclosure:
As stated (more)
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2 ENCLOSURE J
PILGRIM STATUS REPORT FOR THE PER!00 FEBRUARY 13-26, 1988 4
1.0 Plant Status As of 8:00 a.m. on February 26, 1988, the reactor was in cold shutdown mode with moderator temperature about 96 degrees Fahrenheit.
2.0 Facility Operations Summary The plant has been shutdown for maintenance and to make program improvements since April 12, 1986. The reactor core was completely defuelod on February 13, 1987 to facilitate extensive maintenance and modification of plant equipment, The licensee completed fuel reload on October l',, 1987. Reinsta11ation of the reactor vessel internal coa $onents 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.
Durin modi 1*gcation this report period, the
/ maintenance licensee testing of plantcontinued withSome equipment. the postof the major ongoing projects include process computer tie ins, hydrogen water chemistry system pre-operational testing, and load testing of the third emergency diesel generator.
3.0 Items of Special Interest NRC Public Meetinos to Receive Comments on BEco's_ Pilgrim Restart Plan The NRC held settings to receive public comments on the Pilgrim Restart Plan in Plymouth, Massachusetts on February 18, 1988. The meetings took place in the town's Memorial Hall from 1:00 p.m. to 4: 00 p.m., and from 7:00 p.m. to 10:00 p.m. State and local officials, and private citizens were invited to comment on the plan or to subalt cossments in writing.
The meetings were formal, transcribed sessions where the public's testimony was heard by the panel of NRC management. The panel consisted of Mr. Samuel J. Collins, Deputy Director Division of Reactor Projects, NRC Region I, Dr. Ronald R. Bellamy, Chief. Emergency Preparedness and Radiological Protection Branch, NRC Region I, Mr. A. Randy Blough, Chief, Reactor Projects Section 38, NRC-Region I and Mr. Richard M. Wessman, Director, Reactor Projects Directorate I 3, NRC Office of Nuclear Reactor Regulation (NRR).
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3 Early on February 18, 1988, the Massachusetts Attorney General announced during a press conference that he and the Governor would not support or attend the meetings. Prior to that, NRC had expected and desired the Comonwealth to participate. NRC Region I had sent a letter to the State Liaison Officer (i.e. , the individual within the Commonwealth of Massachusetts government designated by the Governor to be the primary point of contact with NRC) in early November requesting cooperation and ,
, advice regarding meeting location and schedule. On January 4, 1988, the Comonwealth replied by letter reiterating earlier demands for an adjudicatory hearing, but stating that the Comonwealth would participate in the meetings so long as the Comanwealth received written assurance that such participation would not be relied upon or cited as a waiver of the Comonwealth's demand for an adjudicatory hearing. NRC Region I endeavored to provide that assurance in a January 15, 1988 letter, which stated, "Your support of these meetings is separate from and does not constitute a waiver of any rights related to the Comonwealth's October 15, 1987 Petition for a formal adjudicatory hearing."
Written coments from those unable to attend the meetings may be mailed to Mr. A. Randy Blough, U.S. Nuclear Regulatory Comission, 475 Allendale Road, King of Prussia, PA 19406. NRC has been asked how it will handle coments received af ter the established deadline of February 25. Based on the current projections, any written coments receiveo by March 11, i 1988 will be incorporated into the current staff review. Coments received after that date will be evaluated and reviewed separately on a schedule and priority consistent with their potential safety significance. The NRC considers it an important part of its job to respond appropriately to legitimate safety concerl.s raised at any time. ,
The transcript of the meetings will be placed in local public libraries for public review. NRC plans to hold one or more follow up public meetings to explain the NRC response to the public coments. These followup meetings would occur af*er the staff has evaluated the comments and decided on the appropriate sponse actions, but prior to a staff recomendation to the full Co Aston regarding plan restart.
NRC Assessment Panel Meetir On February 17, 1988, members of NRC management from Region I and NRR were onsite and discussed restart inspection plans with the NRC resident staff. The NRC Assessment Panel meets periodically to coordinate the planning and execution of NRC inspection and licersing activities related to Pilgrim. The panel is chaired by Mr. Samuel J. Collins, Deputy Director,DivisionofReactorProjects,NRC-RegionI.
In developing a coordinated program to assess licensee perfomance, the restart assessment panel has recomended the following actions and they have been subsequently approved by the Regional Administrator, NRC Region 1:
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-- The restart assessment report will contain detailed assessments using a Systematic Assessment of Licensee Performance (SALP) like methodology of those problem areas recognized as needing improvement and evaluation prior to plant restart. Performance in other applicable SALP functional areas will also be assessed but in less detail.
The current assessment period for a full SALP board assessment of Pilgrim will be an ei hteen C month period of 2/1/87 - 7/31/88. This extended assessmint period will provide for a r'aningful evaluation of licensee actions in conjunction with its approach to readiness for plant restart and, if restart is authorized, a period of licensee operation. The SALP schedule allows the assessment panel to focus its efforts in the next few months on continuing evaluation of licensee improvement programs and to finalize its evaluation of Boston Edison's Restart Plan (including consideration of public comments).
Management Meetin,gs On February 24, 1988, a publicly-noticed management meeting was held between NRC and Boston Edison company (BEC:) officials at the NRC offices in King of Prussia, PA. The Commonwealth of Massachusetts Offi:a of Public Safety and the Office of the State Senator William Golden monitored the meeting via telephone conference. BECo senior management presented its "self-assessment process" designed to determine readiness for requesting restart. The minutes of this meeting will be documented in NRC Report No. 50-293/8S-10, 4.0 Eme gency Notification System (ENS) Report During this period, the licensee made the following reports to the NRC pursuant to 10 CFR 50.72.
l On February 23, 1988, at about 10:00 a.m., the licensee identified two scram circharge volume (SDV) isolation valves which failed to close within the required time. As part of t.he reactor protection system, SDV vent and drain va hes are required by the station technical specifications to close on a reactor scram sigral within !
30 seconds. SDV vent valve CV302-23A closed in 90 seconds and drain valve CV302-22A closed in 45 seconds. The average closing tire for the remaining operable valves on the SDV was 9 seconds. There are four drain and four vent valves on the SDY. The licensee's evaluation and corrective actions will be docusented in Inspectien Report No. 50-293/88-07.
-- On February 23,1988, at 2:24 p.m. , the licensee experienced inadvertent isolation of all inboard secondary containment dampers, an automatic start of the "A" standby gas treat. ment system, and an isolation of the inboard RHR to Radaaste primary contairnent isolation valve. The observed actuations occurred during a relay (more) ,
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i coil replacement in the R4R to Radwaste primary containment isolation logic circuit. It appears that the licensee failed to i fully identify the effect of deenergizing the circuit. The fuse was l reinserted and the actuations cleared a short time later. The inspector's review of this event will be further discussed in Inspection Report No. 50-293/88 07. ,
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- On February 26, 1988, at 1:10 p.m., the control room received {
spuricus automatic closure of the outboard containment 1.olation !
j valve on the reactor water cleanup system. The licensee is in the i process of investigating the esase of the actuation. The inspector's review of this event will be further discussed in Inspection Report No. 50 293/8E-07.
i 5.0 NRC Staff Status Durino the Period I l The inspection staff at Pilgrim during the report period consisted of the j 1 following: :
Clay Warren -- Senior Resident Inspector l
Jeffrey Lyash -- Desident Inspector Tae Kim -- Resident Inspector In addition, one regional specialist inspector was onsite during the week ,
s of February 22, 1988 to review the adequacy of the licensee's emergency I notification system. The results of this inspection will ba documented '
i in NRC Inspection Report 50 293/88 09.
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