ML20010G271

LER 81-046/03L-0:on 810728,emergency Feedwater Supply to Loop 1 Helium Circular Water Turbines Isolated to Repair Leaking 2-inch Consolidated Safety Relief Valves.Caused by Valve Leakage Downstream of Pressure Control Valve

ML20010G271
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/26/1981
From:	Mcbride M PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20010G265	List: ML20010G264 ML20010G271
References
LER-81-046-03L, LER-81-46-3L, NUDOCS 8109150509
Download: ML20010G271 (1)

Text

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NRC FORM 366 U. S. NUCLEAR REGULATORY COMLISSION (7371 4 .

LICENSEE EVENT REPORT CONTROL BLOCK: l I

l l l l l lh 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l0 l11 7 8 9 lC l0 lF !S lVl1l@l0 l0 l- l0 l0LICENSE LICENSEE LcOE 14 15 l0 l0NUMBER l0 l- l0 l0 l@l25 4 l26 1 l LICENSE 1 l 2 TYPE l 0 JOl@l 57 CAT l l@

58 COWT IOl1l 3o[geg l L hl0 l s 10 l0 10 12 l668l7 hl0 69 17 l2 l8 18 l1 hl0 l 8REPORT 14 75 l2 l6DATEl 8 l180l@

7 8 60 61 VoCKET NUMB ER EVENT DATE EVENT GESCRIPTION AND PROBABLE CONSEQUENCES h Io12l l On July 28. 1981. with the olant coeratine at 30% ocwer and 83 We . the emercency I to13l l feedu guoply to Loop 1 helium circulator water turbines was isolated to repair l

o 141 l leaking relief valves. This is a degraded mode of LCO 4.2.2(a) and is reportable ocr I loisl l Fort St. Vrain Technical Specification AC 7.3.2(b)2. No accompanying occurrence. ]

1016 I l No effect on public health and safety. Similar reports R0 81-019, RO 80-015. and l jol7] l R0 80-02 3. l l

l 0 la l I 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VA LV E CODE CODE SU8 CODE COMPONENT CODJ SU8 CODE SUBCODE 1o191 ln la l@ LsJ@ 181@ I v l A l t i v i s i x l@ Lx_,@ Laj @ 18 19 20 7 8 9 10 11 12 13 SE QUENTI A L OCCURRENCE REPcm' REVISTN EVENTVEAR R EPORT NO. CODE TYPs NO.

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@ .ag,g Islil 1-1 I014161 l/l lo111 1.L_l l-l LO_J

_ 21 22 23 24 26 27 28 29 30 31 32 TAK N AC 0 PL NT VE HOURS SS I P R 8. SLPPLIE MAN FACTURER Lij@lz_J@

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36 101010101

3. 40 Ivl@ INi@ INi@ Icisl617l@

41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS

! i i J l l Relie f valve leakane downstream of oressure control valve necessitated isolation for l lt lt l l rep air. The 2" 1900 series Consolidated Safety Relie f vaives were removed . reb uilt . I ii ;7l l bench tested, and re-ins talled. Eme rgency feedwater to Loon 1 was restored to ser- l l

l i t a l l vi ce .

1il4i ! l 80 7 8 9 ST  % POWER OTHER STATUS i O RY DISCOVERY OESCRIPTION l1 l 5 l dh l 0 l 310 lh! N/A l [1] hl coerator Observation l ACTIV'TY CO TENT RELE ASED OF RELECE AMOUNT OF ACTIVITY LOCATION OF RELEASE l1 l6l 7 8 9 h 10 l N/A 11 44 l l 45 N/A 80 l

PERSONNEL EXPOSURES NUM8ER TYPE DESCRIPTION N/A l l t l 71 l010 l 0 !@l Z l@l PERSONNE L INJU IES NUMSER DESCRIPTION Ii I 8 l [n jf_Ja j@l n/A 80 l

7 8 9 11 12 LOSS OF OR DAM AGE TO FACILITY TYPE CESCRIPTION l i l o l (2.j@l N/A 80 l

7 8 9 10 Issus 12 l a l [y_f@ lDESCRIPTION N/A l llllll1llIl!Ii 7 8 9 10 68 69 80 5 8109150509 810826 PDR ADOCK 05000267 MbWJd /

PH ON E'.

(303) 785-2224 2 S PDR - - - - --

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