ML20197H827

Discusses Util Request for Exemption & Proposed Tech Spec Changes to Permit Operation of Plant w/non-inerted Containment During Initial Startup Test Program.Salp Input Encl

ML20197H827
Person / Time
Site:	Columbia
Issue date:	07/16/1984
From:	Houston R Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
References
CON-WNP-0762, CON-WNP-762 TAC-54997, NUDOCS 8407240009
Download: ML20197H827 (5)

Text

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[pu%gA UNITED STATES j ,j j NUCLEAR REGULATORY COMMISSION y .y sj- 4 l WASHINGTON, D. C 20553 k[4 /

July 16,1984 MEMORANDUM FOR: T. M. Novak, Assistant Director for Licensing, DL FROM: R. W. Houston, Assistant Director ,

for Reactor Safety, DSI

SUBJECT:

WASHINGTONPUBLICPOWERSUPPLYSYSTEMREQUESiFOR EXEMPTION FROM 10 CFR 50.44 (TAC # 54997)

Plant Name: Washington Public Power Supply System (WNP-2)

Docket No.: 50-397 Region: V Responsible Branch: LB #2 Project Manager: R. Auluck Due Date: July 13, 1984 Review Status: Complete Inerting the containment for the WNP-2 plant is required by 10 CFR 50.44 (revised) and by the plant's Technical Specifications. In 10 CFR 50.44,

. " Standards for Combustible Gas Control S Power Reactors," Section 50.44 (c).(3).(ystem in Light i) states Water in part that,Cooled

" Effective May 4, 1982, or 6 months after initial criticality, whichever is later,'an inerted atmosphere shall be provided for each boiling light-water nuclear power reactor with a Mark I or Mark II type containment."

Additionally, the currently effective Technical Specifications for the WNP-2 plant includes a requirement for the plant to be operated with an inerted containment. However, provision 3.10.5 of these Technical Specifications (special test requirement) suspends the inerting requirement during the performance of the startup test program until six months after initial criticality.

Since WNP-2 achieved its initial criticality on January 19, 1984, the plant is required to be inerted by July 19, 1984, per the 10 CFR 50.44 requirement set forth above. By its letter dated May 11, 1984, the licensee requested a temporary exemption from the requirement of 10 CFR 50.44 so that it may continue-operating-the-plant-with-a non-inerted containment during the balance of the initial startup test program. The licensee proposed a change to the Technical Specifications (Section 3.10,5) so that it may continue operating the plant with a non-inerted containment until either the required 100% rated thermal power trip test has been performed or the reactor has operated for 120 effective full power days.

8307240009 840716 M

{ ADOCK 05000397

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D T. M. Novak .

The licensee stated that the Power Ascension Test Program (PATP) should be completed by September 1984 After completion of the PATP, as defined in the proposed Technical Specifications, the licensee will be in compliance with 10 CFR 50.44 (c) (3).(i), and the exemption should expire.

It is advantageous to operate the reactor without inerting during the PATP as an uninerted containment would per.mit unscheduled inspections or identification of possible problems important to safety during this period. The anticipated high frequency of containment entries during the PATP period and the required deinerting and re-inerting time (about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) would tend to discourage early and frequent containment entries for identifying and correcting any potential safety problems before they become serious safety problems. .

In addition, other advantages due to accessibility associated with non-inerted containment during the testing phase are: the ability to quickly locate, evaluate and isolate system leakages and the ability to minimize unnecessary thermal cycles on the reactor systems due to the capability to solve minor problems which, if left unattended, could develop into major equipment malfunctions and thus jeopardize plant safety. The facility can continue to operate safely during the remainder of the PATP because the inventory of fission products is being created at a lower rate than was originally contemplated. This is due to the reactor being run at.a lower than anticipated power rating, and on an interrupted basis, in order to ensure that the test program is accomplished in a safe manner. The reduced power schedule is the primary reason the absolute time schedule of 6 months will be exceeded.

Inspection personnel entering the containment after it has been deinerted may be in some danger, because of the possibility that non-breathable nitrogen pockets may remain if the operator fails to initiate the mixing system. These risks are minimized during normal plant operation. However, during PATP, the risk is greater due to the large number of personnel entries into the containment.

The inerting requirement resulted from a staff judgement that the safety benefits attributable to having an inerted containment during normal operations outweighed the associated disadvantages. This judgement does not prevail during the PATP because of the need for frequent containment entries for inspection and surveillance purposes.

T. M. Novak Since the average PATP period was 330 days and the last Mark 11 plant to complete the program took 245 days, the licensee's request for exemption and the proposed Technical Specification changes should be approved to permit the operation of the WNP-2 with a non-inerted containment for a longer period of time as provided for in the proposed Technical Specifications, Special Test Requirements 3.10.5.

Enclosure 1 is the SALP input for this review.

Or Hinsioi,7adby P. T" vr e HC'2 3 +0n R. W. Houston, Assistant Director for Reactor Safety, DSI cc: DSI/Dir.

D. Eisenhut DISTRIBUTION:

A. Schwencer R. Auluck CSB R/F CSB TACS File FEl tawila CONTACT: F. Eltawila, CSB: DSI JKudrick x29488 WButler AD/RS/RF

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DSI:C" DSI:CSD DSI: SB/BC DSb,AD/RS-f FEltawila:pw JKudrick WRButler RWHouston 7/10/84 7/ /34 7/ /84 7//g/84 0FFICIAL RECORD COPY

EilCt.050RE 1 . .

SALP .

prepared by the Containment Systenis Brancti WNP-2 Evaluation Criteria Ca teifiry tiarra tive Description Managemesit Iuvolvenent N/A

~ Approach to H.$_liil,lon eso 2 Good understanding of Technical issue, sound approach toward resolving sta ff's con' 's of Technical Issues I.

Responsiveness 2, , Information needed to close this issue was sutanitted in a timely inanner.

Enforcement Ifistory .

N/A Reportable Event.

N/A

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-Sta f fing N/A ,

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