NUREG-0763, Forwards List of Questions Re Confirmatory Tests of Safety Relief Valve Torus Attached Piping Loads.Response Requested within 30 Days of Receipt of Ltr

Forwards List of Questions Re Confirmatory Tests of Safety Relief Valve Torus Attached Piping Loads.Response Requested within 30 Days of Receipt of Ltr

ML20151B157
Person / Time
Site:	Fermi
Issue date:	07/13/1988
From:	Quay T Office of Nuclear Reactor Regulation
To:	Sylvia B DETROIT EDISON CO.
References
RTR-NUREG-0661, RTR-NUREG-0763, RTR-NUREG-661, RTR-NUREG-763 TAC-59607, NUDOCS 8807200265
Download: ML20151B157 (4)

Text

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July 13, 1988 Docket No. 50-341 DISTRIBUTION M Docket F.11e BGrimes Mr. 8. Ralph Sylvia NRC & Local PDRs T8arnhart (4)

Group Vice President - Nuclear PD31 Plant Gray Wanda Jones Operations GHolahan EButcher Detroit Edison Company TQuay ACRS (10) 6400 North Dixie Highway RIngram GPA/PA Newport, Michigan 48166 OGC ARM /LFM8 DHagan EJordan

SUBJECT:

FERMI 2 CONFIRMATORY TESTS OF SAFETY RELIEF VALVE TORUS ATTACHED PIPING LOADS (TAC NO. 59607)

Reference:

(1) Letter from Detroit Edison to USNRC dated 9/11/87 (2) Letter from Detroit Edison to USNRC dated 11/13/87 The staff has reviewed the referenced submittals regarding the Fermi-2 torus attached loads and has developed the enclosed list of questions.

The responses to these questions are necessary in order to complete our review. Please respond to the enclosed request for additional information within 30 days of the receipt of this letter.

The request in this letter affects fewer than 10 respondents; therefore OMB clearance is not required under PL 96-511.

Sincerely, Theodore R. Quay, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects

Enclosure:

As stated cc w/ enclosure:

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• • 0" c NUCLEAR REGULATORY COMMISSION f  : WASHINoTON. D. C. 20555 g / July 13, 1988 Docket No. 50-341 Mr. B. Ralph Sylvia Group Vice President - Nuclear Operations Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166

SUBJECT:

FERMI 2 CONFIRMATORY TESTS OF SAFETY RELIEF VALVE TORUS ATTACHED PIPING LOADS (TAC NO. 59607)

Reference:

(1) Letter from Detroit Edison to USNRC dated 9/11/87 (2) Letter from Detroit Edison to USNRC dated 11/13/87 The staff has reviewed the referenced submittals regarding the Fermi-2 torus attached loads and has developed the enclosed list of questions.

The responses to these questions are necessary in order to complete our review. Please respond to the enclosed request for additional information within 30 days of the receipt of this letter.

The request in this letter affects fewer than 10 responder,ts; therefore OMB clearance is not required under PL 96-511.

Sincerely, Theodore R. Quay, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects Enclosuro:

As stated cc w/ enclosure:

See next page

Mr. B. Ralph Sylvia Fermi-2 Facility Detroit Edison Company cc:

Mr. Ronald C. Callen Ms. Lynn Goodman Adv. Planning Review Section Supervisor - Licensing Michigan Public Service Commission Detroit Edison Company 6545 Mercantile Way Fermi Unit 2 P. O. Box 30221 6400 North Dixie-Highway Lansing, Michigan 48909 Newport, Michigan 48166 John Flynn, Esq.

Senior Attorney Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health P. O. Box 30035 Lansing, Michigan 48909 Mr. Thomas Randazzo Director, Regulatory Affairs Detroit Edison Company Fermi Unit 2 6400 North Dixie Highway Newport, Michigan 48166 Mr. Walt Rogers U.S. Nuclear Regulatory Commission Resident Inspector's Office l 6450 W. Dixie Highway l Newport, Michigan 48166 Monroe County Office of Civil Preparedness l 963 South Raisinville

! Monroe, Michigan 48161 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

. ENCLOSURE

1. Testing Procedure for Fermi 2 compared to that reconnended in NUREG-0661 and NUREG-0763:

The above NUREG's have provided guidelines for plant-specific tests (e.g.Section6ofNUREG-0763,"TestProceduresandMatrix"). It is not clear from the test report whether the testing sequence and conditions used for Fermi 2 satisfy the NUREG recommendations (e.g. discharge condi-tions, number of quenchers, thernal mixing, simultaneous actuation of multiple valves).

2. Testing Temperature:

NUREG-0763 recommends discharge under the normal temperature condition.

It is not clear whether this condition has been satisfied for Fermt 2 (Ref. NUTECH report p4-1).

3. 90-90 vs. 95-95 Statistical Results:

The test cata in the report were analyzed for a 90-90 probability value rather than the customary 95-95 estimate. Will the 95-95 results have any impact on the conclusion?

4. Analytical Results used for comparison with the Test Data:

Provide a sun ary comparison of the test results and the original analysis results for several of the most highly stressed points in the structure.

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