05000029/LER-1984-011, Forwards LER 84-011-02

Forwards LER 84-011-02

ML20129G849
Person / Time
Site:	Yankee Rowe
Issue date:	05/06/1985
From:	St Laurent N YANKEE ATOMIC ELECTRIC CO.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8506070383
Download: ML20129G849 (1)

LER-2084-011, Forwards LER 84-011-02

Event date:
Report date:
0292084011R00 - NRC Website

text

r YANKEE ATOMIC ELECTRIC COMPANY weo:wnwimsw

' l, -

?- e .,*'6 Star Route, Rowe, Massachusetts 01367 K *$ )

. D.igliE May 6, 1985 U.S. Nutlear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Purley, Regional Administrator

Subject:

Licensee Event Report 50-29/84-11/Rev. 2 Pressurizer Code Safety Valve PR-SV-182 Setpoint Tolerance Error

Dear Sir:

In accordance with 10 CFR 50.73(a)(2)(1), the attached Licensee Event Report is hereby submitted.

Very truly yours.

lh+Wk f(f0f/ti Normand N. St. Laurent Plant Superintendent DWE/nm Enclosure cc: T NSARC Chairman (YAEC) 1 Manager of Operational Quality Assurance (YAEC) l1.l Institute of Nuclear Power Operations (INP0) 8506070383 850506 PDR 8 ADDCM 05000029 PDR '1T 41 N If

r m.mC Fe,m att U S. NUCLt4316 EluLAf tXY COhedl5480N

~ '30 APPROWto Oue NO 3:50-4104 LICENSEE EVi!NT REPORT (LER) '""'

F ActLiTV NA.85 til Doca ti NUMet a (21 ' AGE 63i Yankee Nuclear Power Station o ls lo lo lol0l2 19 1 lor l01 3 TifLE I46 Pressurizer Code Safety Valve PR-SV-182 Setpoint Tolerance Error EVENT DATE Ill LER NUMeER 10) REPORT DATE 171 OTHER F ACILiTies INvolvtD 181 MONTH DAY YEAR vtAR * *LiU '," "*

, ,* % MONTM OAv VEAR .acitif e mauts DOCntT NUMetRill 015101010 1 I I 0l7 0 l3 8 4 8 l4 0l1l1 0l2 0l5 0l6 8l5 0 1 5 1 0 1 0:0 1 I I

,,,,,,,,,, THis naPont is sueuiff to PunsuAmt to TMs maouantM Nis or to Crn ( ,ca.<e ea er na.,. .e ,*. ,eu. ane siin a'oaa m 1 = mi.i no .o.a. ni.H H i n.ri +.

g a mi.HiHis mi.His ni.H:H.i n rii.i n., 1 i 00 i i.HiH.i maH,,

nieHan... _ gagsgg.,g,,,,

20.4061.H1 Hel 80 73i.'(2Hil .0 731.H2HealiHAl JKfAJ N 4061.lliHivl 80 73i.H2Het Oo.73l.H2Hv6hl101 N eoSt.lliH.I to 73i.H2 Haul to 731.ll2Hal LICENSEE CONTACT FOR TMit LE A (itt Naut TELEPHONE NUMSER Douglas W. Ellis Plant Engineer ' ' ' ' ' '

41,3 424 3i5 i 26;l i COMPLtit ONE LINE FOR E ACM COMPONENT P AILunt DESCRiSED IN TMis apront tisi CAust sv$ttu 4AAN AC. oat "' #0'

• COMPONENT y o kpmo'f CAUSE systiu COMPONENT "'y'O NPmoh I, I l l I I I I t i I I I I -

I l l l l l

• 1  ! I l l l l 1

$U.PLEMENTAL mEPom? EXPECIED Hei MONTH DAv vgA4 ses tre v .n. e.nw.en expttrio susuissiont DA rts

& ko l l l A..T A C T a -.. . . , e . ,.. .... , .,. . , n .i On July 3, 1984 while operating at 100 percent power the lift setting (s~etpoint) of PR-SV-182, the high set Pressurizer Code Safety Valve (Safety Valve), was determined to be 2567 psi? which exceeded the Technical Specifications (TS) setpoint tolerance of (2560 psig) + 0%, -3%. The determination was made during review of final Design Change documentation for the Safety Valves that replaced the original Safety Valves during the Spring 1984 refueling outage. Telephone notification to the USNRC was made; a subsequent telephone conference of NRC, plant, and corporate personnel determined that continued plant operation to be acceptable and that a written report (LER) and a Proposed Change to TS for Safety Valves setpoint tolerance was required. Further Corrective Actions involve review and revision of the procedures used to develop specifications, issuance of a report for nonconformance, and training of engineers developing specifications and correction of specifications. Each of the Safety Valves is capable of providing the relief capacity necessary to prevent the Main Coolant System pressure exceitding 2735 psig, therefore there is no danger to the public health and safety.

._ .~ . n + ~

ju s ' ~

~.)

"".*i' " "

7 NRC Feem 366A U $_ NUCLECl RECULATOAY COMMIS$lON LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROvio oMa No 3 iso-om E XPirES. 8/31/E5 F ACILITY NAME HD DOCKET NUM8ER (2) LER NUM8ER (6) PAGE (3) n aa "St%^'  ;'##:

Yankee Nuclear Power Station oF 01510101o l0 l2 l9 8l4 -

0l111 -

0 12 012 0 13 TEXT 92 more space a requnet use exeonet hMC form 366Ks) Uh On July 3, 1984 while operating at 100 percent power the lift setting (setpoint) of PR-SV-182, one of two new Pressurizer Code Safety Valves (Safety Valves), was determined to exceed the Technical Specifications (TS) setpoint tolerance. The determination was made during review of final Design Change documentation for the Safety Valves tFat replaced the original Safety Valves during the Spring 1984 refueling outage.

Telephone notification to the USNRC was made regarding this condition. A subsequent telephone conference of NRC, plant, and corporate personnel determined that continued plant operation to be acceptable and that a written report (LER) and submittal of a Proposed Change to TS for the Safety Valves setpoint tolerance would be required.

Further Corrective Actions included: review of this Desi review of procedures for Specification (s), Design Changes),(gn Change activity; Procurement (s),

and Receipt Inspections (s); review of review activities for Design Change (s);

and issuance of a report for nonconformance of this activity to the requirements of the Quality Assurance Program.

The original Safety Valves were designed in accordance with the ASME Boiler and Pressure Vessel Code (Code) Section VIII. The TS setpoint tolerance of

+0%, -3% originates from the 3% tolerance of Section VIII; however, the +3%

tolerance was deleted due to Transient Analysis assumptions that utilized nominal +0% setpoints for the Safety Valves in the Loss of Load transient design case. The Proposed Change for Safety Valves setpoint tolerance establishes the basis for the new setpoint tolerance.

Resulting from NUREG 0578 Section 2.1.2 requirements, later qualified by NUREG-0737 Item II.D.1, and Licensing correspondence, new Safety Valves were installed at YNPS. The new Safety Valves were manufactured in accordance with Code Section III requirements but did not require an "N" stamp, since the Pressurizer is not a Section III vessel. Code Section III, subsection NB-7512.2 (0pening Pressure Tolerance), requires that the setpoint tolerance

"... shall not exceed ... ( ) 1% of the set pressure for pressures over 1,000 psi ... " unless a greater set pressure tolerance can be justified. This change to a 1% setpoint tolerance versus the TS setpoint tolerance of +0%,

-3% is contrary to 10 CFR 50.59 since the change of tolerance was neither identified in the Design Change nor in a Proposed Change (to TS) for the replacement of the Safety Valves. The Design Change and Proposed Change did identify the change for the Safety Valve's relief capacity.

A supplemental Purchase Order was issued to the manufacturer which included the TS setpoints and tolerance of +0%, -3%; however, the manufacturer test data indicate the "As Left" set pressure of PR-SV-182, the high set pressure Safety Valve, was 2567 psig. Thus, PR-SV-182 was within the Code Section III tolerance of 2560 psig 1% but exceeded the TS tolerance of 2560 psig +0%,

-3%. This condition was reported by utility personnel upon discovery. The ge ,on. .

w e a 29C Form 354A U S. NUCLEAR T.EGULATOXY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ueRovEo oM8 No. 3 iso-oio4 EXPtRES 8/31/85 FACILITY NAME (i) DOCKET NUM8ER 12)

LER NUMBER (6) PAGE131 viaa " $',L* ' .

3*,0 Yankee Nuclear Power Station TEXT f#more space as reguned, vae addoonsINRCForm 356NsJ (171 o ls l0 l0 lo l0 l2 l9 8l 4 -

0 l 1l1 -

0[2 0l3 OF 0 l3 set pressure of PR-SV-181, the low set pressure Safety Valve, is 2480 psig and within the TS setpoint and tolerance of 2485 psig +0%, -3% and Code Section III tolerance of 1%. During receipt inspection of the new Safety Valves the TS setpoints and tolerance of 2485 psig +0%, -3% and 2560 psig +0%,-3% was not detected.

The cause of this condition was personnel failure to identify the TS setpoint tolerance.

Corrective Action (s) to prevent recurrence hcve included revision to procedures for Specification (s) and Receipt Inspection (s); revision to the procedure for Procurement (s) is being evaluated, but is currently considered acceptable. The procedures for Design Change (s) are considered adequate to prevent recurrence; the other noted procedures are considered to have contributed to this unusual condition. In addition, emphasis will be provided to engineers and review organization (s) personnel directly responsible for Design Change activities regarding the requirements of 10 CFR 50.59 and the contents of this report. The Proposed Change to TS for Safety Valves setpoint tolerance has been submitted. Full compliance with the Corrective Actions is anticipated by the startup date following the 1985 refueling outage.

W Each of the Safety Valves is capable of providing the relief capacity necessary to prevent the Main Coolant System pressure exceeding 2735 psig, therefore there is no danger to the public health and safety.

9 FORu 366A