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| {{Adams
| | #REDIRECT [[GO2-83-436, Interim Deficiency Repts 216 & 223 Re Gaseous Release from RHR Relief Valve Vents & Inadequate Standby Liquid Control Sys,Respectively.Final Deficiency Rept 232 Re Improper Installation of RHR Support Pin Receptacle Also Encl]] |
| | number = ML17277A612
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| | issue date = 05/18/1983
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| | title = Interim Deficiency Rept 216 Re RHR Relief Valve Vents. Initially Reported on 821022.Relief Valves Will Be Removed, Containment Leakage Path Will Be Eliminated & Steam Condensing Mode Will Be Deactivated.Next Rept by 830817
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| | author name = Carlisle C
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| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
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| | addressee name = Martin J
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| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
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| | docket = 05000397
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| | license number =
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| | contact person =
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| | document report number = 10CFR-050.55E, 10CFR-50.55E, GO2-83-436, NUDOCS 8306270353
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| | package number = ML17277A611
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| | document type = DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21), TEXT-SAFETY REPORT
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| | page count = 8
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| }}
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| | |
| =Text=
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| {{#Wiki_filter:C!III!~
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| gO Interna1 Oistribution HRC Distribution
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| ~Na)l Ora Attached ZiI E: COPY Docket ilo. 50-397 Mr, J.
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| B. Martin May 18, 1983 Regional Administr ator U.S.
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| Nuc 1 ear Regul atory Commi s si on Region V
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| 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
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| ==Subject:==
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| NUCLEAR PROJECT NO.
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| 2 10CFR50.55(e)
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| POTENTIALLY REPORTABLE CONDITIONS 8216, RHR RELIEF VALVE VENTS; 8223, STANDBY LIQUID CONTROL SYSTEM (SLCS);
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| AHD 8232, LPCS AHD RHR SUPPORT PIH RECEPTACLES
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| ==References:==
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| a) Telecon dated October 22,
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| : 1982, R.T.
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| Johnson to John E 1 in b) Telecon dated January 27,
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| : 1983, L.C. Floyd to R.
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| Dodds (QA2-83-029) c) Telecon dated January 21,
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| : 1983, L.C. Floyd to John Elin (QA2-83-023)
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| In accordance with the provisions of 10CFR50.55(e),
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| your office was informed by telephone, of the above subject conditions.
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| Attachments A and 8 provide the Project's interim reports on Conditions
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| //216, RHR Relief Valve Vents and 8223, Standby Liquid Control System (SLCS).
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| Attachment C provides our final report for Condition //232, LPCS and RHR Support Pin Receptacles.
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| He will continue to provide your office with quarterly updates on Conditions 216 and 223.
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| If you have any questions or desire further information regarding these
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| : subjects, please contact Roger Johnson, llHP-2 Project QA Manager, (509) 377-2501, extension 2712.
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| ha 9 L9ll.
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| 'Original 'Sign'ed Hf G. S.
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| Garlisle'.
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| S. Carlisle Program Director, MHP-2 Attachments:
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| (3)
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| As stated cc:
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| W.S. Chin, BPA A. Forrest, Burns and Roe -
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| HAPO H.D. Lewis, EFSEC
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| ATTACHMENT A g
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| WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO.
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| 2 DOCKET NO. 50-397 LICENSE NO.
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| CPPR-93 10CFR50.55(e)
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| CONDITION II216 RHR RELIEF VALVE VENTS lRTERIM REPORT Descri tion of Deficiency There are 4
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| RHR relief valves which have a 2" vent hole on the valve body.
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| The valves are RHR-V-55A, RHR-V-95A, RHR-V-558, and RHR-V-958.
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| These valves are situated such that the failure of a single motor operated
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| : valve, RCIC-V-113, would allow an open leakage path from the wetwell (primary containment) directly to the reactor building (secondary containment'
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| ~
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| The attached sketch illustrates the situation
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| ~
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| Containment penetration X-116 is an open path into the wetwell's gaseous volume.
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| In the steam con-densing
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| : mode, RHR-V-55A (or 8) and RHR-V-95A (or 8) protect the RHR heat exchanger from over-pressurization.
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| In order to accommodate condensation in the line between these valves and containment, a vacuum breaker has been installed that consists of penetration X-116, RCIC-V-113, RHR-V-102, RHR-V-101A (or 8),
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| RHR-V-103A (or 8),
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| and RHR-V-179A (or 8).
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| All of these valves are.normally open.
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| Upon a containment isolation signal, the only valve to close would be RCIC-V-113.
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| If it failed to close, and a
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| LOCA had occur red, the wetwell would pressurize, and the wetwell atmos-phere would vent down this path.
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| Details of the RHR relief valve show that a flow path exists which would allow the wetwell atmosphere to vent directly to secondary containment.
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| Safety Im 1 icati on m
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| Earns an]
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| Roe has estimated the gaseous release from these four paths at 5,2 x 10 scfm during the first 450 seconds after a
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| LOCA and at a rate of 4.9 x 10 scfm thereafter.
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| This can be compared to the allowable re'lease rate for primary containment of approximately 1.7 scfm.
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| Corrective Action After a review of possible corrective actions, including incorporation of a bellows seal, the Project has decided to remove the relief valves, elimi-nate the containment leakage
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| : path, and deactivate the steam condensing mode of the RHR system.
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| Supply System and Burns and Roe Engineering are prepar-ing the necessary Project Engineering Directives and FSAR changes to imple-ment the corrective action.
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| We will continue to provide your office with quarterly updates on this subject.
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| The next report will be submitted by August 17, 1983.
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