GO2-83-101, Final Deficiency Rept,Condition 216 Re RHR Relief Valve Vents.Initially Reported on 821022.Relief Valves Removed, Eliminating Containment Leakage Path.Const in Progress on Physical Changes & Will Be Complete Prior to Fuel Load

Final Deficiency Rept,Condition 216 Re RHR Relief Valve Vents.Initially Reported on 821022.Relief Valves Removed, Eliminating Containment Leakage Path.Const in Progress on Physical Changes & Will Be Complete Prior to Fuel Load

ML20082D314
Person / Time
Site:	Columbia
Issue date:	11/03/1983
From:	Shannon J WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
10CFR-050.55E, 10CFR-50.55E, 216, GO2-83-1016, NUDOCS 8311220384
Download: ML20082D314 (5)

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Washington Public Power Supply System P.O. Box 968 3000 GeorgeWashingtonWay Richland, Washington 99352 (509)372-5000 November 3, 1983 G02-83-1016 Mr. J. B. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596

Subject:

NUCLEAR PROJECT N0. 2 10CFR50.55(e) REPORTABLE CONDITION #216 RHR RELIEF VALVE VENTS

References:

1. Telecon L.C. Floyd to J. Elin, dated October 22, 1982.

2. Letter BRG0-R0-82-Oll, W.G. Conn, BRI to R.H. Engelken.

3. Letter G02-83-154,~ dated February 18, 1983, R.G. Matlock to R.H. Engelken.

4. Letter G02-83-436, dated May 18, 1983, C.S. Carlisle to J.B. Martin.

5. Letter G02-83-731, dated August 12, 1983, C.S. Carlisle to J.B. Martin.

In accordance with the provisions of 10CFR50.55(e), your office was informed by the references above of the subject condition. The attachment provides the Project's final report on this condition.

If you have any questions regarding this subject, please contact Roger Johnson, WNP-2 Project QA Manager, at (509) 377-2501, extension 2712.

x J. Shannon 0

o jEi Director Power Generation 5 -

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5 3 S JGT/kd 8311220384 831103 y_.

PDR ADOCK 05000397 -

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Attachment:

As stated cc: W.S. Chin, BPA N.D. Lewis, EFSEC A. Toth, NRC Resident Inspector Document Control Desk, NRC i\

340

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h WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR 'ROJECT NO. 2 DOCKET NO. 50-397 LICENSE N0. CPPR-93 10CFR50.55(e) CONDITION #215 RHR REIIEF VALVE VENTS FINAL REPORT Description of Deficiency There are 4 RHR telief valves which have a 2" vent hole on the valve body.

The valves are RHR-V-55A, RHR-V-95A, RHR-V-55B, and RHR-V-95B. These valves are situated such that the failure of a single motor operated valve, RCIC-V-113, would allow an open leakage path from the wetwell (primary containment) directly to the reactor building (secondary containment).

The attached sketch illustrates the situation. Containment penetration X-ll6 is an open path into the wetwell's gaseous volume. In the steam condensing mode, RHR-V-55A (or B) and RHR-V-95A (or B) protect the RHR heat exchanger from over-pressurization. In order to accommodate condensation in the line between these valves and containment, a vacuum breaker has been installed that consists of penetration X-ll6, RCIC-V-ll3, RHR-V-102, RHR-V-101A (or B), RHR-V-103A (or B), and RHR-V-179A (or B).

All of these valves are normally open. Upon a containment isolation signal, the only valve to close would be RCIC-V-ll3. If it failed to close, and a LOCA had occurred, the wetwell would pressurize, and the wetwell atmosphere would vent down this path. Details of the RHR relief valve show that a flow path exists which would allow the wetwell atmosphere to vent directly to second-ary containment.

Safety Implication BurngandRoehasestimatedthegaseousreleasefromthesefourpathsat5.2 x}0 scfm during the first 450 seconds after a LOCA and at a rate of 4.9 x 10 scfm thereafter. The consequences of this release were not evaluated since the configuration does not meet 10CFR Part 50 General Design Criteria (GDC) 54 and 56 concerning piping systems penetrating the primary containment. The condition is considered to be a reportable deficiency under 10CFR50.55(e) ,cri-teria.

Cause of the Deficiency The condition exists because the engineer did not recognize the relief valve had to serve a containment isolation boundary function, besides being a relief valve for RHR system equipment. Vendor drawings were evaluated only for the code related relief valve function without recognizing the hole in the bonnet constituted a containment leakage path.

Corrective Action The Project, after a review of alternate courses of action has chosen to remove the relief valves eliminating the containment leakage path. This results in deactivting the steam condensing mode of the residual heat removal (RHR) system as defined in Amendment 33 of the FSAR.

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. Final Report #216 Page 2 of 4 Corrective Action (Continued)

The deactivation will occur in two phases to minimize impact 6n the Project, i.e., Phase 1, changes required prior to fuel load, and Phase 2, those changes which can be deferred until after fuel load. Project Engineering Directives (PED's) 215-M-X467, 218-E-C286 and G.E. Field Design Deviation Request (FDDR) 1251 have been issued to implement Phasa 1 of the deactivation. Construction is in progress on the physical changes required. Administrative controls will be implemented by Operations for some portions of the deactivation defined in the PED's. This work is scheduled to be completed prior to fuel load.

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