ML20044A666

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LER 90-006-00:on 841218.determined That Shutdown Cooling Sys Relief Valve Setpoint Not Set,Per Tech Spec Requirement. Caused by Procedural Inadequacy.Procedure MM-007-006 revised.W/900627 Ltr
ML20044A666
Person / Time
Site: Waterford Entergy icon.png
Issue date: 06/27/1990
From: Mcgaha J, Tanya Smith
ENTERGY CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-006, LER-90-6, W3A90-0169, W3A90-169, NUDOCS 9007020030
Download: ML20044A666 (5)
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W3A90-0169 A4.05 QA June 27,,1990 l U.S.; Nuclear Regulatory Commission ATTENTION: Document Control Desk 

                       ' Washington, D.C. 20555                                                                                ,

I Subjects Waterford 3 SES 1 g Docket No. 50-382 l License No. NPF-38 

                                      - Reporting of Licensee Event Report                                                    I Centlemen:

Attached is Licensee Event Report Number LER-90-006-00 for Waterford Steam Electric Station Unit 3. 'This Licensee Event Report is submitted pursuant to'10CFR50.73(a)(2)(i).  ; Very truly yours, l 

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FiCILITV NAML l1i DOCh t Y NUMOt R (21 FA03 (I' Waterford Steam Electric Station Unit 3 o is l 010 j o I 31812 1\0FI014 init 4. Shutdown Cooling System Relief Valve Setpoint Not Set In Accordance With Technical Specifications Due To Procedural Inadecuacy SVENT DATE t&l Lth NUMBE R 161 REPORY DATE til OTHE R f ACILlittl INVO4VED 14) MONTH DAY vtAR VLAR IIf$ n "If[ MONTH DAY 41AR racatif v hauts DUCE tt NuM9kRtli N/A 0161010101 I I 

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NAME TtttPMONE NUMetR amt A ( 104 T.ll. Smith, Plant Engineering Superintendent 5 j 0,4 4 , 6 , 4, , 3,1, 2,7 COMPLEf t ONE LINT FOR S ACH COMPONINT 9 AiLURE OtSCRIBED IN THis REPORT 113 

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CAJSt Sv81tM COMPONENT t[ "T'O PR s CAUSE SYSTsu COMPONENT M'b[g g "T O PR 1 1 I I I l- 1 I t i i I I I i l i I I I I I I I I I I I EUPPLEMENT AL REPORT E XPECTt0 414' MONTw Day vtam sv6M tS$10N Ytt (19 res to.pete LX9tCTtO SV0Mi$310% OA Tti NO l l l tui R ACT ,u-, R, , a e,-- . . . .-.-- , ,, n ,,. -. ,,,,.~n. *,,o n . On May-31, 1990, a review of technical specification (TS) surveillance procedures revealed that the lift pressure of the shutdown cooling (SDC). system relief valve SI-406A was.438 psia, which exceeded the maximum TS allowable setpoint pressure of 430 psia. A further review of TS surveillance procedures revealed that both SDC system relief valves (SI-406A & SI-406B) had been set above the maximum allowed pressure on two previous occasions. This event is therefore reportable as plant operation prohibited by TS. The root cause of this event was an inadequate maintenance procedure. The allowable lift setpoint tolerance of 12% was incorrectly applied to the maximum allowed setpoint pressure (430 psia) which allowed the TS maximum setpoint to be exceeded. Plant operation with SDC system reliefs set 2% above 430 psia would still have ensured that reactor coolant system (RCS) pressure limits were met during the limiting pressure transient; therefore, this event did not result in an increased risk to the health and safety of the public or plant personnel. 

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                     .       LICENSEE EVENT REPORT (LER) TEXT CONTINUATION                 Amovio out =o sao oioc (XPtRts. S/31/08 PAC 441TV 1s4404 HD                                DOCKET DeVGADER (2) 44R NUMSth fel                   PAQt (31 Waterford Steam                                                     vaan    $a gp,* 6        go,y; Elsctric Station Unit 3
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text ex- w w c % ass 4wnn On May 31, 1990, plant operating in Mode 1, a review of technical specification (TS) surveillances revealed that the setpoint lift pressure for the shutdown cooling (SDC) (EIIS Identifier Bp) system Telief valve SI-406A (EIIS Identifier . RV) was set at 438 psia, exceeding the maximum TS allowable setpoint pressure of 430 psia. TS limiting condition for operation (LCO) 3.4.8.3 requires low temperature overpressure protection be provided by either of the following: 

                       - Both operable SDC relief valves (SI-406A & SI-406B) with a lif t set pressure less than or equal to 430 psia aligned to the reactor coolant system (RCS) (EIIS Identifier AB).
                       - RCS depressurized with a RCS vent path greater than or equal to 5.6 square inches.

TS 3.4.8.3 is applicable in mode 4 (when either RCS cold leg temperature is less than or equal to 285 'F), mode 5, and mode 6 with the reactor vessel head on. A further review of TS surveillances revealed that the following lift pressures were incorrectly set on the dates listed: relief valve- set press (psia) dates 406A 433 07/26/83 406B 435 07/18/83 406A 437 03/15/86 406B 433 03/14/86 406A 438 10/15/89 

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   ""            '            '                                                                             U S CUC4tCQ CEQuLOf 0a0 ComulSS104 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION                             areaono ous =o mo.om (IP*?FS 4'31 W FACitlTY 084A84118 '                                         00CKg1asveADER 04              Lgm tausieBER 161                 PAQt (31 hterford Steam                                                          "*a       "tui."             WJ:

y Electric Station Unit 3 ftXT I# poses apsse e pseuwsd. was owesener sW4C Fann M)/11h o l5 l0 l0 l0 l 3l8 l 2 91 0 Ol Ol 6 - 010 0l3 0' 0l4 The SDC System Relief valves are tested in accordance with Mechanical Maintenance 4 

                      . (MM) procedure (MM-007-006) on a 30 month interval. MM-007-006 revision 0 was l-approved on June 4, 1982 and incorrectly listed the setpoint pressure as 415                                              ;

L psig 12% (407-423 pig) which converts to a band of (422-438) paia. This +2% tolerance allowed the maximum allowed set pressure to be exceeded by as much as 8' psi. The two subsequent revisions to procedure MM-007-006 contained the same error and were approved on December 24, 1985 and January 21, 1987 respectively. l l From December 1984 through February 1990, the plant was operated in violation j of TS LCO 3.4.8.3 on sixteen different occasions for a total of 277 days. I The root cause of this event is an inadequate maintenance procedure. Mh 007-00,6,  ; I Maintenance Procedure Safety Injection Relief Valve Test, incorrectly allowed tr 

                      -lift pressure in excess of TS limits. The 12% setpoint tolerance is established in accordance with ASME performance test code 25.3, but the lift setpoint                                                 ;

tolerance was incorrectly applied to the maximum allowed setpoint pressure (430 psia) as specified by TS LCO 3.4.8.3. I 1 l l Contributing to this event was an inadequate technical review in verifying j conformance of procedure MM-007-006 to TS requirements. Technical reviews are 'f l required by administrative procedure UNT-001-003 for development, revision,  ; \ changes, and bi-annual review of work procedures. UNT-001-003 specifically l requires the technical reviewer to address the following: "Does this procedure, revision, change, or deletion adequately address and/or reference technical l (. specifications and other matters that may affect nuclear cafety?" The l MM-007-006 procedural review and revision process failed to adequately ensure  ! compliance with TS 3.4.8.3, allowing this condition to exist intermittently I since issuance of the operating license (December 18, 1984).  ! l l L 1 l l 6 .e. u.. .m + m ) 

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ExPimES t'3t.3 7ACILITV asaast ggs DOCtt, soutABE A W (gn segnagen ggi pagg (36 lWaterford Steam "'" " N a" D*U E1;ctric Station Unit 3 ' _ _ y YlXT f# sesse apsre e segewed use seh 4AC 7ene W'skith To prevent recurrence of this event, procedure MM-007-006 is being revised to 

                 ' include a lower setpoint pressure tolerance of 415 psig +0% - 2% (421-430 psta).

The. revision will be completed by October 15, 1990. SDC System Relief valve SI-406A vill be adjusted to the correct setpoint pressure within the allowed 7 days after entering TS-3.4.8.3 applicability. A review of other work procedures involving relief valves was conducted to identify any other misapplications of setpoint tolerances. No discrepancies verr. found. A ssmpling of other TS surveillance precedures.will be reviewer' to ensure that acceptance criteria  ; meets TS requirements. This review '.s expected to be complete by October 1  ! i 1990 and will' include any TS sur.eillance procedures not previously reviewed by the plant TS coordination group. l I' 3 The design basis of SI 406A and 406B is to provide overpressure protection of * 

                                                                                                                                                             .l the RCS at low temperatures during heatup, cooldown, and cold shutdown. The limiting pressure transient includes simultaneous, inadvertent operation of                                                                l l

three high pressure safety injection (HPSI) pumps (EIIS Identifier BQ-P), three l

i. charging pumps (EIIS Identifier CB-P), with all pressurizer backup heaters j l

1 l .(EIIS Identifier AB-PZR-EHTR) in operation. A-20% margin is realized because- l L only two HPSI pumps are started by Safety Injection Actuation Signal (SIAS) (EIIS' Identifier JE). Plant operation-with both setpoints for the SDC system reliefs set 2% above the maximum set pressure would not have allowed any plant l pressure limits to be exceeded during the limiting pressure transient; there- -) 

      '            fore, this event did not result in an incre m d risk to the health and safety of the public or plant personnel.

Similar Events None Plant Contact T.H.-Smith, Plant Engineering Superintendent, 504/464-3127. mm . . _ _ _ . _ ._ .u.e. m :m e m -}}

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