ML20148C693

Forwards Plant Biweekly Status Rept for 880227-0311

ML20148C693
Person / Time
Site:	Pilgrim
Issue date:	03/15/1988
From:	Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8803220486
Download: ML20148C693 (6)

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Q MAR 151988 Docket'No. 50-293 MEMORANDUM FOR: .' James T. Wiggins, Chief Reactor Projects Branch No. 3 FROM: A. Randy Blough, Chief Reactor Projects Section No. 3B

SUBJECT:

PILGRIM STATUS REFORT FOR THE PERIOD FEBRUARY 27 - MARCH 11, 1988 Enciesed 1. 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. Three specialist engineers from the NRC Office of Nuclear Reactor' Regulation (NRR) were onsite during the week of February 29, 1988 to.

observe the current configuration of the direct torus vent modification and its supporting safety evaluation.. On March 9,1988, the Regional Administrator of NRC Region I toured the station with the resident inspectors. Also, on that date, several management representatives from NRC Region I and NRR were onsite and. met with the resident inspectors. On March 10, 1988, Dr.. Thomas E. Murley, Director, NRR, Mr. William T. Russell, Regional Administrator, Region I, and other management representatives from NRR were onsite and toured the station.

The _ status reports are 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.

Ord31r:1 Ji rdd IgJ A. Randy Blough, Chief ,

Reactor Projects Section No. 3B

Enclosure:

As stated d

$$[2gg h y 0FFICIAL RECORD COPY PILGRIM STATUS 3/14/88 - 0001.0.0 19' t

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Memorandum for James T. Wiggins 2 M 151988 cc w/ encl:

W. Russell, RI W. Kane, RI W. Johnston, RI F. Congel, RI S. Collins, RI 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 L. Gustin, Vice President - Corporate Relations, BECo R. Bird, Senior Vice President-Nuclear, BECo K. Highfill, Station Director, BECO The Honorable Edward P. Kirby The Honorable Peter V. Forman The Honorable Edward J. Marley Chairman, Board of Selectmen, Plymouth Chairman, Board of Selcctmen, Carver Chairman, Board of Selectmen, Duxbury Chairman, Board of Selectmen, Marshfield Chairman, Board of Selectmen, Kingston N. Johnson, Chairman, Duxbury Nuclear Committee Plymouth Civil Defense Director B. McIntyre, Chairman, Department of Public Utilities M. Ernst, Committee on Energy, Commonwealth of Massachusetts J. Keyes R. Boulay S. Pollard M. Co.iyngham M. Jeka K. Anderson Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector Commonwealth of Massachusetts (2) 0FFICIAL RECORD COPY PILGRIM STATUS 3/14/88 - 0002.0.0 03/lU88

Memorandum for James T. Wiggins 3 MAR 151988 bec w/ encl:

Region I Docket Room (with concu~rrences)

R. Blough, DRP L. Doerflein, DRP M. Kohl, DRP M. J. DiDonato, DRP (2)

K. Abraham, PA0 (2)

C. Warren, SRI - Pilgrim (w/ concurrences) c RI:DRP RI:DRP R :DRP RI: P CWarren/mjd ABlough Wie ins SCol ins 3//( /88 3//h88 3/ 88 3/ 8 0FFICIAL RECORD COPY PILGRIM STATUS 3/14/88 - 0003.0.0 03/16/88

ENCLOSURE PILGRIM STATUS REPORT FOR THE PERIOD FEBRUARY 27 - MARCH 11, 1988 1.0 Plant Status As of 8:00 a.m. on March 11, 1988, the reactor was in cold shutdown mode with moderator temperature about 95 degrees Fahrenheit.

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 defueled on February 13, 1987, to facilitate extensive maintenance and 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 this report period, the licensee continued with the post-modifica-tion / maintenance testing of plant equipment.

3.0 Items of Special Interest NRC Assessment Panel Meeting On March 9, 1988, members of NRC management from Region I and NRR met onsite and discussed inspection plans with the NRC resident staff. The NRC Assessment Panel meets periodically to coordinate the planning 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 Projecis, NRC Region I.

NRC Technical Review of the Direct Torus Vent Modification As part of the Safety Enhancement Program, the licensee had planned to install a direct torus vent line which can be used to relieve the containment pressure in the unlikely event of a severe accident. The generic issue of containment venting is still under review by the reactor owner's group and the NRC and is a complex issue involving a variety of safety objectives. During this outage, the licensee has . installed the direct torus vent line with a blind flange and a blank plate to seal the line. In this configuration, the direct vent system is non-functional and its path is sealed; however, it could be made functional with relatively simple additional modification. The licensee's intent is to make this system functional af ter the desirability of the direct torus vent system is decided upon generically.

OFFICIAL RECORD COPY PILGRIM STAiUS 3/14/88 - 0004.0.0 03/16/88

Enclosure 2 To evaluate the currently installed design configuration of the direct torus vent modification and its supporting safety evaluation, three specialist engineers from NRC:NRR were onsite during the week of February 29, 1988. The evaluation focused on the as-built system to assure that there is no adverse safety impact on the plant resulting from the current installation.

On March 10, 1988, Dr. Thomas Murley, Director, NRR, Mr. William Russell, Regional Administrator, Region I, and other representatives from both NRR and Region I toured the site, inspected the plant areas where the direct torus vent system has been installed, and interviewed licensee engineering department personnel regarding the system.

More details of the above activities will be contained in future NRC inspection reports.

Licensee's Radioactive Effluent and Waste Disposal Report As required by the NRC Regulation 10 CFR 50.36 (a)(2) and the Station Technical Specification 6.9.C.1, the licensee submitted the Semi-Annual Effluent and Waste Disposal Report to the NRC on February 29, 1988. The report covers the period of July 1 through December 31, 1987. This report summarizes the liquid and gaseous effluent activities f rom the Pilgrim Stction and the calculated maximum hypothetical radiation exposure to the public resulting from the effluent. The NRC plans to review the report for conformance to the Technical Specifications and Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Efflu-ents from Light Water Cooled Nuclear Power Plants." A copy of the licen-see's report will be available at the local public document room.

Licensee Management Realignment The licensee announced on March 10, that Mr. Roy A. Anderson, the current Planning and Outage Manager at Pilgrim, will replace Mr. Robert J. Barrett, who has announced his intention to resign. Mr. Anderson will continue to report to Mr. Kenneth L. Highfill, the Station Director. Plant opera-tions, maintenance, and technical sections report to the Plant Manager.

This reassignment will be effective March 30, 1988.

4.0 Emergency Notification System (ENS) Report During this period, the licensee made the following report to the NRC pursuant to 10 CFR 50.72:

OFFICIAL RECORD CCPY PILGRIM STATUS 3/14/88 - 0005.0.0 03/16/88

Enclosure 3 On March 4, 1988, during an internal Quality Assurance audit, the licensee identified that a surveillance test of the "B" emergency diesel generator (EDG) may not have been performed as required during the last operating cycle in 1984. Pilgrim Technical Specifications require that each EDG be started and loaded once per operating cycle with the control circuits isolated from the cable spreading room to demonstrate alternate plant shutdown capability. No record of performance of procedure 8.9.13, Diesel Test From the Alternate Shutdown Panel, for the "B" EDG during the last operating cycle could be found. The test records were available for "A" EDG testing.

This matter will be further reviewed in a future NRC inspection report.

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 --- Resider.t Inspector In addition, three specialist engineers from NRC:NRR were onsite during the week of February 29, 1983 to evaluate the installed design configuration of the direct torus vent modification and its supporting safety evaluations. The results of the evaluation will be included in the routine resident inspection report 50-293/83-07.

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