ML20010C773

Request for OMB Review & Supporting Statement Re Guidelines for Confirmatory Implant Tests of Safety Relief Valve Discharges for BWR Plants.Estimated Respondent Burden Is 62,400-h

ML20010C773
Person / Time
Issue date:	07/24/1981
From:	Besaw W, Scott R NRC OFFICE OF ADMINISTRATION (ADM)
To:
References
NUDOCS 8108200404
Download: ML20010C773 (6)

Text

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REQUEST FOR OV.S REVIEW E' '

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Justification r

N The staff has cor.. leted its review of safety relief valve related hydrodynamic loads and suppression pool temi.erature limits..As a result, acceptance criteria have been established and described in our safety evaluation report.

'(NUREG-0661, " Mark I Containment Long-Term Program;" NUREG-0487 and i

Supplement 1, " Mark.II Containment Lead Plant Program Load Evaluation and Acceptance Criteria Report;" SER for GESSAR 238 Nuclear Island, Docket No. STN 50-447.)

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These acceptance criteria are intended for generic application.

Plants in which parameters are substantially,#ifferent from the data base used to establish the acceptance criteria for SRV loads will be required to perfcrm inplant testr..

Transmittal of NUREG-0763 to applicants and licensees provides guioelines to determine if inplant tests are required on the basis i

of the piant unique parameters, for formulating appropriate test matrices, l

establishing test procedures, selecting necessary instrumentation, and reporting test results.

2.

Description of Survey Pl an i

(1)

This reppt will be addressed to 30 licensees and applicants of Boiling Water Reactor (BWR) Nuclear Power Plants.

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(2)

Failure to use the guidelines ' contained in this report would not directly result in a violation of Commission orders; however, it could result in the unacceptability of the design charigas#an.d modifications made to i

account for SRV loads on the BWR containment designs.

This is a concern i

since it could be a violation of the Code of Federal Regulations General Design Criteriog16 which addresses. containment integrity.

(3) NA (4)

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3.

Tabulation and Publication Plans i

This report is provided for guidance.

However, the ' staff will review the implementation of these guidelines including documentation of the SRV inplant test program and the test results report.

4.

Time Schedule for Data Collection and Publication 1

For licenfiees/ applicants with Mark I containments, NUREG-0561 provides specific acceptance criteria for SRV loads and NUREG-0763 is only provided for addit.ional guidance.

For applicants with Mark II and III containments documentation of the SRV inplant test program (where required) should be provided during the 1

FSAR review.

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6.

Estimation of Resoondent ~Recortino ' Burden For licensees / applicants with Mark I containments thare will be no reporting burden.

For applicants of lead plants having Mark II and III containments and those applicants of plants which'are substnatially different from the lead plants the reporting burden is estimated ~to be one man year per licensee.

For applicants with plants for which the parameters are the same as for the lead plants used to establish acceptance criteria t,here will be no reporting burden.

7.

Sensitive Ouestions NA 8.

Estimate o f Cost'to Government The tot'al cost to the Government of this reporting requirement will be 0.5 professional man years and $80K in techr.ical assistance funds.

9.

Practical Utility The tests performed and information obtained will permit design changes and modifications to the containments to be made to restore the original design sa fety. ma rgi n.

E The NRC has programmed the necessary resourcer to.-review this information.

A contractor has also been retained to review the information.

10.

Necessity The primary mission of the Nuclear Regulatory Commission is to ensure that the design, construction, and operation of nuclear power plants does'not endanger the health and safety of the general public.

The purpose of the issuance of this report is to provide guioance to the applicants / licensees to enable meaningful tests to be performed (where needed).

These test results are to be utilized for the design of containment mod,ifications to restore the originally intended containment safety margins.

11.

Copy Reauirements The number of copies submitted should be consistent with that required _for docketing during the FSAR stage of review.

12.

Record Retention The in#ormation submitted by the licensees will be retained for the duration of the facility operating license normally at least 40 years.

13.

Summary Reportine Reouirements_

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For those applicants performing inplant tests, NUREG-0763 requires documentation during the FSAR review.

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.e.s ALL SWR APPLICANTS AND LICENSEES (EXCEPT LACROSSE, BIG ROCK POINT, DRESDEN 1, AND HUMBOLDT BAY)

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Enclosed is a ecpy of WUREG-0763 entitled, " Guidelines for Confirmatory Inplent Tests.of Safety Relief Valve Dischfrges for SWR Plants."

'i The staff has completed its review of safety relief valve related hydrodynamic loads and suppression pool temperifure limits.

As a result, acceptance criteria have been established and described in our safety evaluation report.

(NUREG-0661, " Mark I Containment Long-Term Program;" NUREG-0487 and Supplement 1, " Mark II Containment Lead Plant Program Load Evaluation and Acceptance Criteria Report;" SER for GESSAR E38 Huclear Island, Docket No. STN 50-447.

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These acceptance criteria are intended for generic application.

Plants in wnich parameters are substantially different from the data base used to establisn the acceptance criteria for SRV loads will be required to perfurm inplar.t tests.

Guidelines to determine if inplant tests are required on tne basis of the plant unique parameters are included in Section L of the recort.

Guidelines for fcrmulating apprcpriate test matrices, establishing tes: pr::edures, sele::ine necessary instrumentation, and reporting test results are also presented in NUREG-0763. -

2r,

.J:.E3-0763 is being issued to provide guidance that the NRC staff believes tracid be 'clicwec in formulating test programs for inplant safety-relief ca".ces :: nest tha repuirements cf General Design Criteria 15 and 29 in 1.:cer.:ix A to 10 CFR Part 50.

NUREG-07E3 is not a substitute for :ne regu-iati ns. and ecm:liance is not a receirement.

However, an apprcach or ne: nod d'fferent frcr the guidance contained herein will be acce;ted if':he substitute a:pecatr or method provides a basis for ceterminin; tha: the a'bove-cited ceguia cry criteria have been met.

cr the Mark I containrent long terr program generit load definition methods l

were developed which are applicable to all Mark I plants.

For these plants an alternate safety relief valve analysis approach to evaluate the effe :s c'~ safety relief valve

• discharge based on inplant tests have been orovided in

.NUREG-0551.

Since we recognize that this program has been un.derway for some time, NUREG-0763 is only intended to urovide additional guidance to those licensees-that have not yet parformed these inplant tests.

All questions. elated to this report should be directed to T. Su at 492-9422.

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2-This application reporting and recordkeeping requirements contained in this Regulation /Bulle. tin /0rder/ Letter /NUREG/ Form /Etc. have been approved by the Office of Managment and Budget; OMB Approval No.

Sincerely, Darrell G. Eis'enhut, Director Division of Licensing

Enclosure:

NUREG-0763

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