ML19317F036

Transfers Lead Responsibility for Surveillance Requirements for Internals Vent Valve Assemblies from IE to Ofc of Nuclear Reactor Regulation

ML19317F036
Person / Time
Site:	Davis Besse, Oconee, Arkansas Nuclear, Rancho Seco, Crane
Issue date:	05/19/1976
From:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Goller K Office of Nuclear Reactor Regulation
Shared Package
ML19317F037	List: ML19317F036 ML19317F050 ML19317F058
References
IE-RID-76-13, NUDOCS 8001080734
Download: ML19317F036 (2)

Text

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9 TRA*iSFER OF LEAD RESrGNSIBILITY I

R:

. R. Collar, Assistant Director for Operating Reactors, NR1 4

Subj ect:

SURVCILIMCE REQUIT:!EliTS FOR INTERNALS VE::T VALVE ASSI2GLIES Facilities: All Labcock and Wilcox (!G) Pressurized Water Reactor Facilities imlding Construction Pernits er Operating Licenacs Witit the Exception of Indian Point, Unit No. 1 (Indian Point, Unit ;;o. 1 does not have the internal vent valve design) hsponsible 3rcuch Chief:

K. V. Seyfrit Description of__Iten Requiring Resolutien:

The internals vent valves are installed to prevent a pressure unbalance betucen the renetor inlet and outlet plent=s, which nignt interferc with core cooling follouing a postulated inlet pipe rupture.

The FS/R states that these valves vill start to open at a differential pressure of 0.15 psig and be fully open at a differential pressure of 0.3 psic.

DW Standard Technical Specification Surveillanco P.equircnent 4.4.10.1.2 requires that each valva be de:onstrated operable by visual inspection i

and cianual operation at least once every 13 nonths.

however, there is no acceptance criteria regarding the force necessary to open the valves.

A review of the technical specificaticus for the 3 W facilities with j

operating license:3 indicates there are no surveillance requircraents for the interr.alsvent valves. These facilities are:

cconee, Unit No. 1 50-269 Oconce, Unic '~o.

2 50-270 Oconee, Unit No. 3 50-237-Three tiile Island, Unit No.1 50-239 Rancho Seco 50-312 l

Arkansas Nuclear One, Unit No. 1 50-313 Reco:raendations and Propoccd Course of_ Action:

1.

The Office of :;uclear Reactor Regulation will determine if openin; force measurc=ents should be included as acceptance criteria during i

valva surycillance.

2.

The Office of Nuclear ivactor Ecm lation M 11 de t e r -inn 1F tech 4eni specification surveillance requirenents should be req 2 ired for the operarinrfmilities I M ca~nbu A.

I eve =ame >

esvu k Penn ABC 318 (Rev. M3) AECM 0240 1lr u. s. oovan=usur enenvene orncas nova.s s. nee 8001080 N k

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K. R. coller

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MAY 19 1976 1

3.

The Office of Inspection and Enforce =ent will provide additional

'information as roquested.

)

4.

Tho Office of Inspection and Enforcement vill verify cdherence to any requirementa Sposed by the Office of Nuclear Reacoor Regulation.

References:

1.

Lic=orandum from R. D. L.

in to R. C. Knop, dated March 23, 1976.

2.

Memor.ndun frca R. C. Knop to K. V. Seyfrit, dated March 29, 1976.

i Concurrence:

1

' Original.igned W n 11. Grier F2 H. Grict, Director, Division of Reactor Inspection Programs, IE Date b K. Uoller, aJET5 rant ulreccTr for vperaclag neaccors, ;.a

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uate 1

cc:

E. Volgenau, IE l

H. Thornburg, IE l

D. Thotpson, IE R. S. Doyd, JAd i

V. Stello, GER G. W. Reinmuth, IE i

K. V. Scyfrit, IE G. W. Roy, IE h

j J. P. O'Reilly, IE:I l

N. C. Mosclay, IE:II 9

J. C. Kopplcr, IE:III E. M. Howard, IE:IV g

R. H. Engelken, IE:V 9

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T. Abell, HIPC i

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H. K. Shapar, ELD 1

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