ML20151T930
| ML20151T930 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/25/1988 |
| From: | Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8808180334 | |
| Download: ML20151T930 (6) | |
Text
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A L 2 6 1989 Docket No. 50-293 MEMORANDUM 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, Pennsylvania.
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 8, 1988. Onsite preparation for the IATI will be conducted during July 19 -
21, 1988.
The Pilgrim bi-weekly status report is 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.
$r W SignedBy:
dE A.
andy Blough, hief Reactor Projects Section 3B
Enclosure:
As Stated 0FFICIAL RECORD COPY PILGRIM STATUS RPT 7/20 - 0001.
0 11/29/80 G808100334 880725
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POR ADOCK 05000293 R
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JUL 2 51988 cc w/ encl:
L. C. Gustin, Vice President - Corporate Relations, BECo R. Bird, Senior Vice President-Nuclear, BECo K. Highfill, Station Director, BEC0 J. D. Keyes, Licensing Division Manager, BEco Chairman, Board of Selectmen, Plymouth Chairman, Board of Selectmen, Carver Chairman, Board of Selectmen, Duxbury Chairman, Board of Selectmen, Marshfield Chairman, Board of Selectmen, Kingston The Honorable Edward P. Kirby The Honorable Peter Forman The Honorable E. J. Markey M. D. Ernst, Committee on Energy, Commonwealth of Massachusetts S. M. Pollard, Energy Secretary, Commonwealth of Massacnusetts B. McIntyre, Chairman, Department of Public Utilities N. Johnson, Chairman, Duxbury Nuclear Committee Plymouth Civil Defense Director R. Boulay M. Conyngham M. R. Jeka K. R. Anderson Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Massachusetts (2)
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JUL 2 51988 bec w/ enc 1:
Region I Docket Room (with concurrences)
T. Murley, NRR F. Miraglia, NRR T. Martin, NRR S. Varga, NRR B. Boger, NRR D. Crutchfield, NRR J. Partlow, NRR C. Rossi, NRR L. Shao, NRR R. Wessman, NRR D. Mcdonald, NRR J. Roe, NRR W. Russell, RI W. Kane, RI W. Johnston, RI F. Congel, RI S. Collins, RI R. Blough, RI L. Doerflein, RI M. Kohl, RI M. J. 0100 nato, RI K. Abraham, RI PA0 (2) f C. Warren
.A. Bloug
[Wigise Date Date lDate 4
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0FFICIAL RECORD COPY PILGRIM STATUS RPT 7/20 - 0003.0.0 11/29/80 l
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l ENCLOSURE PILGRIM STATUS REPORT FOR THE PERIOD JULY 2 - 15, 1988 1.0 Plant Status As of 8:00 a.m., on July 15, 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 rector core was completely defueled on February 13, 1987 to facilitate extenshe maintenance and modification of plant equipment.
The licensee completed fuel reload on October 14, 1987.
Reinsta11ation 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 this period, the licensee performed routine maintenance and surveillance 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 Meeting The SALP process is supplemental to the normal regulatory processes used 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.
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 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.
I 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 staff participated via tele-conference.
NRC Assessment Panel meets periodically to 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)
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 schedules for resolution of remaining items prior to restart.
The NRC has tentatively scheduled a comprehensive IATI to begin on 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 3B, Region I.
Arrangements have been made for a representative from the Commonwealth 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 pursuant to 10 CFR 50.72:
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.
4, '.
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 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.
On July 12,'1988, an inadvertent start of the "B" emergency diesel generator (EDG) occurred during implementation of electrical equipment isolations on associated safety-related 4160 VAC bus. The isolations were being conducted in accordance with an approved work plan and tagging sheet. The effect of the isolations on the start logic of the "B" 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 The inspection staff at Pilgrim during the report period consisted of the following:
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 in the NRC inspection report 50-293/88-25.