ML20199E427

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Confirms That Generic Safety Evaluation, Evaluation of Radiological Consequences for Accidental Releases Through BWR 2-Inch Vent & Purge Lines & BWR Owners Group Evaluation of NUREG-0737,Item II.E.4.2 Applicable to Facilities
ML20199E427
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 06/20/1986
From: Kemper J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Butler W
Office of Nuclear Reactor Regulation
References
CON-#386-817, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM OL, NUDOCS 8606230299
Download: ML20199E427 (3)


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PHILADELPHIA ELECTRIC COMPANY

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2301 MARKET STREET P.O. BOX 8699

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PHILADELPHIA. PA.19101 JOHN S. KEMPER

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JUN 20 W c

vics-enssiosur ENGtNSE RONG AND RESE ARCM Docket No. 50-352/353 Mr. Walter R. Butler BWR Project Directorate No. 4 Division of BWR Licensing U. S. Nuclear Regulatory Commissien Washington, DC 20555 3

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SUBJECT:

Limerick Generating Station, Units 1 and 2 NUREG-0737 Item II.E.4.2 (7)

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Containment Isolation Dependability e

REFERENCE:

Letter from W. R. Butler to E. G. Bauer, dated May 20, 1986, and enclosures FILE:

GOVT 1-1 (NRC)

Dear. M'r. Butler:

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dehavereviewedbothtliegenericstaffsafetyevaluation," Evaluation of the Radiological Consequences for Accidental Releases Through BWR 2-Inch Vent and Purge Lines" and the Boiling Water Reactor Owners' Group (BWROG) evaluation of the subject NUREG-0737 item. We have confirmed that both the evaluations, which conclude that BWR purge and vent lines of 2 inches in diameter or smaller need not be provided with a radiation isolation s.{gnal, are applicable to Limerick Generating Station, Units 1 and 2, as discussed below.

The generic staff safety evaluation assumes that operator action to close purge or vent valves in small lines would be taken within 30 minutes. To assure that the generic safety evaluation is appropriate the evaluation stated "the licensee must verify that the 30 minute operating time is valid based upon location and accessibility of the valve operators, and instrumentation necessary to determine the need for manual closure, and that plant procedure and operator training are sufficient to support the approach."

The safety-related remote manual control room switches and safety-related power supplies for the 2" purge and vent containment isolation valve operators assure that the location and accessibility of the valve operators support a 30 minute operator response.

8606230299 860620 DR ADOCK 05000352

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. Instrumentation available to determine the need for manual closure of the purge and vent lines includes instrumentation which would detect small steam leaks inside primary containment as well as increases in radioactive effluent. This instrumentation includes, but is not limited to, south stack effluent radiation monitors (these monitors alarm in the control room at radiation levels below those assumed in the BWROG analysis), containment high range area radiation monitors, containment reactor coolant pressure boundary leakage detection radiation monitors and containment high temperature monitors.

These latter 3 monitors alarm in the control room and serve to provide the operators with indication that an abnormal condition exists inside the containment which may be attributable to the events hypothesized in the BWROG analysis.

Since the operator has taken conscious action to open the vent valves, receipt of any of these alarms is indicative that the valves should be closed.

The plant operator's training sufficiently prepares the operators to handle situations which may require manual containment isolation.

In order to provide additional support, the appropriate operating procedures are being revised to include statements regarding closure of the vent valves within 30 minutes of the event.

Should you have any questions, or require any additional information, please do not hesitate to contact us.

Sincerely, S k" )

RDC/mb/06188601 Copy to:

See attached service list.

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Copy to:. Troy B. Conner, Jr.,.Esq.

' Ann P.'Hodgdon, Esq.

Mr. Frank R..-Ramano Mr. Robert L. Anthony-Ms. Phyllis Zitzer Charles W. Elliot, Esq.

Barry M.' Hartman, Esq.

Mr. Thomas Gerusky Director, Penna. Emergency Management Agency Angus R. Love, Esq.

-David Wersan, Esq.

Robert J. Sugarman, Esq.

Kathryn S. Lewis, Esq.

Spence W. Perry, Esq.

Jay M. Gutierrez, Esq.

Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section Mr. E. M. Kelly

.Mr. Timothy R. S. Campbell I

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