ML19275A251

Discusses 790823 Meeting W/Nrc Re Purge & Vent Valve Operations & Submits Response to NRC Concerns in Regard to Licensee Compliance W/Stds & Tech Specs

ML19275A251
Person / Time
Site:	Fort Calhoun
Issue date:	09/28/1979
From:	William Jones OMAHA PUBLIC POWER DISTRICT
To:	Reid R Office of Nuclear Reactor Regulation
References
NUDOCS 7910030402
Download: ML19275A251 (5)

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Omaha Public Power District 1623 HARNEY a OMAHA, NEBRASKA 68102 s TELEPHONE 5 36- 4000 AR E A CODE 402 September 28, 1979 Director of :Tuclear Reactor Regulation ATT:i: Mr. Robert W. Reid, Chief Operating Reacters Branch :To. k U. S. Iluelear Regulatory Co==issien Washington, D. C. 20555 Re feren ce : Docket :To. 50-285 Gentlemen:

Cn August 23, 1979, Omaha Public Pcver District representatives met with members of the Cc==issicn's Staff in Bethesda, Maryland, to discuss Fort Calhoun Statien purge and vent valve operations. At this meeting, the District was requested to respond to Staff cencerns in regard to ccepliance with BTP CS3 6 h. Accordingly, a response to these concerns is attached as Enclosure 1. In addition, the District was requested to provide a historical record of duratien of purge valve cpenings during the last few years. This information is at-tached as Enclosure 2.

The District is currently evaluating the cperational character-istics of the Fort Ca.1houn's 42" purge valves according to the guidance provided by the Staff's draft document entitled " Guidelines for Demen-a traticn of Operability of Purge and Vent Valves Under Accident Condi-tiens". Until such time as this evaluation is completed and the Staff has cencurred in resolution to this issue, the District will centinue to limit purging to an absolute minimum, not to exceed 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year, when the reactor coolant system is above 2100F.

Sincerely, a-W. C.' Jones Division Manager Production Ci erations WCJ/KJM/3JH:jnm Enclcsures J, cc: Le3ceuf, Lamb, Leiby 3: MacRae 1333 : lev Hampshire Avenue, :I. W.

Was hin gten , D. C . 20036 7 9109g o Q

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INCLCSLSE 1 Items B. l. d. and e.

Radiatien =onitors (FSAR states that any 1/3 vill isolate) are re-quired to be safety grade.

Respense The containment and stack atmospheric radiation socitors conform to ANSI N 18.2 NNS Standards.

Items B.1.f. and B. 5. a.

Prepose an addition to your Technical Specifications which limits the time required for the purge and vent isolat. ion valves to close. This addition should reflect the actica to be taken if the valves fail to close in the specified time during nor:al cperability tests. Using this =axi-

=u= propcsed closure time , speci^/ the amount of contain=ent at=csphere released through the purge and vent isolaticn valves for a spectrum of break sizes.

Rescense Respense is provided under a respense to Ite= 3 5.c. telow.

Item B.1.2.

Discuss the provisien made to ensure that isolatica valve closure vill not be prevented by debris which could potentially beccre entrained in the escaping air and stea=.

Pa spen se The contain=ent purge system is designed to purge the centainment by passing up to 50,000 CFM of cutside air through the building. In order to prevent the entrainment of debris in the return ductwork, all the ductwork penetratiens in the centain=ent air exhaust system are pro-vided with galvanized carbcn steel return-air grilles and screens.

Item B.5.b.

Is the purge system independent of the pcst-LCCA H2 control system?

Could purge ducting damage the H2 control syste=?

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-p-Reseense The containment purge system is independent of the post-LOCA hydrogen purge system. The hydrogen purge system is designed to provide a safe, independent, monitored, and centrolled means of purging any potential accu =ulation of hydrogen in the centainment. Further details are provided under Secticn 9 10 of the FSAR. It is highly unlikely that the purge ducting could damage the h-inch, SCH 40 A-106 GR 3, piping of the hydro-gen purge system; however, if the piping associated with one hydrogen purge line were damaged, the redundant hydrogen purge line vould provide the intended design functions.

Item 3 5. e.

Provide an analysis of the reduction in the containment pressure resulting from the partial losc-of-containment atscsphere during the accident for ECCS backpressure deter =inatien.

Resnense The containment backpressure analysis and the infor=atica needed under Ite=s B.1. f. and 3 5. a. above are being evaluated by the Dis-trict's reactor vendor. The results of such evaluation will be pro-vided t a the Co==ission.

Item 3.5.d.

Speci.^f the allevable leak rates of the purge and vent isolation valves for the spectrum of design basis pressures and flew against which the valves must close. The allovable leak rates should be specified for each valve, not the sum of the leakages.

Restense The allevable leak rates of each h2-inch purge and vent isolation ve.17e (i.e. , HCV-7h2A, 3, C, D) for various design basis pressures are shown en the attached figure. As shown on the figure, the allevable leakage rate at the ESA pressure equivalent to 60 psig is 18,000 sces.

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ENCLOSUFZ 2 Total Hours That Purge Valves (HCV-7h2 Series) Were Oten Per Year Hot Standby Power Oreratien 1976 21 189 1977 0 0 1978 0 0 1979 (to date) 0 0 o

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