ML19256D035
| ML19256D035 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Rancho Seco, Crane  |
| Issue date: | 05/12/1976 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Goller K Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19256D037 | List: |
| References | |
| IE-RID-76-13, NUDOCS 7910160763 | |
| Download: ML19256D035 (2) | |
Text
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s Date:
MAY 1 9 1976 I
Scrial No.: IL-RID-76-1",
j T2ANSFER OF LLD RE3rGNSIDILITY lo:
K. R. Goller, Asciscant Director for Operating ncactors NRR o
,Subj ect: SUkVEILLNiCE REQUIn215TS FOR IUTER';ALS VENT VALVE AS3CI5 LIES Facilitics: All I;abcock and N11cox (D&W) Prasaurized Unter Reactor Facilities liolding Construction l'eruits er Operating Licenses ilith the Er.ception of Indian Point, Unit No. 1 (I.vilan Toint, Unit Co.1 does not ! Lave the internal
+
vent valve design)
Responsible Erench Chief:
K. V. Seyfrit 4
Description of Item Requirint; Recolution:
The intemals vent valves are installed to prevent a pressu w unbalance between the reactor inlet and outlet plenu=s, which nignt interferc with core cooling following a postulated inlet pipe rupture.
The FSAR states that these valves vill start to open at a differential pressure of 0.15 vsig and be fully open at a differential pressure cf 0.3 psig.
B&W Standard Technical Specification Surveillance Requirc=cnt 4.4.10.1.2 requires that cacia valve be denonstrated operao~ le by visual inspection l
and saanual operation at least once every 13 conths. HovcVer, there is no acceptance criteria regarding the force necet.sary to open the valves.
A review of the technical specifications for the B&W facilities with j
operating licenses indicates there are no surveillcace requirements for the internalsvent valves. Thcse facilities are:
t I
Oconec, Unit No. 1 50-269 Oconee, Unit No. 2 50-270 j
Oconee, Unit No. 3 50-237 Three Mile Island, Unit No. 1 50-239 j
Rancho Seco 50-312 Arkansas Nuclear One, Unit No.1 50-313 I
Reco==endations and Propoced Course of Action:
1.
The office of Nuclear Reactor Re;;ulation will determine if openinz; force coasurements should be included as acceptance criteria during valve surveillance.
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{#kkb,1 cal 2.
The Office of Nucicar Recetor Remlation s-f11 dete dra -
te specification surveillance requirements si:ould bc req 2 ired for the operarizrg-fa-ilitiw -u =beve.
evam a nes >
DATE >
Fem AEC.)l3 (,Rev. P.))) AECM 0240 W u. s. oovannesent paintino arricas es,4. ass. nee 7910160763 k
L..
R. Coller MAY l 3 1976 i
3.
The Office of In pection and Enforcement will provide additional
~inforration as requested.
4.
The Office of Inspectior. and Enferec=ent vill verify adherence to any requirecent.: imposed by the Office of Nuclear Reacoor Reg'alation.
References:
E 1.
11cuoranduu from R. D.1ktrtin to R. C. Xnop, dated March 23, 1976.
2.
Memorandula frca R. C. Kaop to X. V. Seyfrit, dated March 29, 1976.
i Concurrence:
i g;:inal sM N-i e
B.it W B. E. Grier, Direct;r, Division of Reactor Inspection Progra=s, IE Date s.- r.. voller, assisca ac utrccccr Ior vperaung acaccors, :..a cace cc:
E. Volgenau, IE j}
U. Thornburg, IE l
D.."compson, Ie i
R. S. Loyd, Jfhl V. Stello, IcR G. W. Rein =uth, IE K. V. Scyfrit, IE G. W. Roy, IE l
J. P. O'Reilly, II:I j
N. C. Moscley, IE:II J. C. Ecpplcr, IE:III l
E. M. Ilovard, IE:IV R. H. Engc1 ken, IE:V i
T. Abell, HI?C E. K. Shapar, ELD 446 044 i
l RID:635/F30169H1
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_. 51_.LI.6 Form AIC.31s (Rev. 9 53) AECM 0240 Q u. s. sonnamsar raianae os 'scae ev4.emse I