05000315/LER-1999-009, :on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation

:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation

ML17325B547
Person / Time
Site:	Cook
Issue date:	04/12/1999
From:	Orourke B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17325B546	List: 05000315/LER-1999-009, :on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
References
LER-99-009, LER-99-9, NUDOCS 9904210035
Download: ML17325B547 (2)

LER-1999-009, on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x)
3151999009R00 - NRC Website

text

C Form 366 U.S. NUCLEAR REGULAT Y COMMISSION (6-1 998)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY MB NO. 3160%104 EXPIRES 06/30/2001 ESTPAATEO IKIRDEN PER

RESPONSE

TO COMPLY WITH THIS MANDATORY INFORMATIONCOLLECTION REOUESTI'BOO HRS. REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE UCENSINO PROCESS AND FED BACK TO INDUSTRY FORWARD COMMENTS REOARDINC BURDEN ESTRIATE TO THE INFORMATION AND RECORDS MANAOEMENT BRANCH IT4I FSTL U S NUCLEAR RECUIATORv COAPJISSNN. WASHINGTON. DC DNSSCQOI, AND TO THE PAPERWORK REDUCTKIN PROJECT ISISDCIOJL OFFICE OF MANAGEMENT AND BUDGET. WASHINOTON DC 2OKO FACIUTYNAMEII)

TITLE(4)

Cook Nuclear Plant Unit 1 DOCKET NUMBERI2) 05000-315 PAD E (3) 1 of1 As-Found Residual Heat Removal Safety Relief Valve LiftSetpoint Greater than Technical Specification Limit EVENT DATE (6)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIESINVOLVED(8)

MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REVISION NUMBER MONTH DAY YEAR FACILITYNAM DC Cook, Unit 2 AGILITYNAME DOCKET NUMB R 05000-316 DOCKET NUMB R 03.

04 1999 1999

009

00 04 12 1999 OPERATING MODE (8)

THIS REPORT IS SUBMITTEDPURSUANT TO THE REQUIREMENTS OF 10 CFR Ii: (Check one or more) (11) 50.73(a)(2)(viir) 50.73(a)(2)(i) 20.2203(a)(2)(v) 20.2201 (b)

POWER LEVEL(10) 00 20.2203(a)(1) 202203(a)(2)(i) 20.2203(a)(2)(li) 20.2203(a)(2)(iii) 20.2203(a)(2)(lv) 20.2203(a)(3)(i) 20.2203(a)(3)(Il) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)

UCENSEE CONTACTFOR THIS LER (12) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(x) 73.71 OTHER Specrr In ABSUect below or nNRC Form 36EA Ms. Brenda O'ourke, Compliance Engineer TELEPHONE NUMBER 0norude Area Code) 616/465-5901, x2604 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX

CAUSE

COMPONENT MANUFACTURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED 14 X

YES IfYes, corn late EXPECTED SUBMISSION DATE NO EXPECTED SUBMISSION DATE 15 MONTH 06 DAY YEAR 18 1999 Abstract (Umitto 1400 spaces, I.e., approximately 15 s)ngl~paced typewritten lines) (16)

On March 4, 1999, during the Expanded System Readiness Review of the Residual Heat Removal (RHR) system, several concerns were identified regarding the RHR shutdown cooling relief valve (SV-103) liftsetpoints for Reactor Coolant System (RCS) Low Temperature Overpressurization Protection (LTOP). Technical Specification (TS) 3.4.9.3 requires the RHR safety valves to have a liftsetting of less than or equal to 450 pounds per square inch gage (psig). A preliminary review of recent In-Service Testing data identiTied that the as-found liftsetpoints forthe 1-and 2-SV-103 were 455 and 452 psig, respectively.

These values are greater than the TS limitof 450 psig, and as a result, the valves were declared inoperable on March 10, 1999. On March 11, 1999 it was determined that 1-SV-1 03 had been taken credit for in October and November 1998 to satisfy LTOP requirements when a Unit 1 Power Operated Relief Valve (PORV) was inoperable.

Preliminary investigation indicates the cause was incorre'ct implementation ofTS surveillance requirements.

The ASME Operations and Maintenance Standards Code-1995 allows the application of a 3 percent setpoint tolerance to valve lift settings during valve testing and requires a temperature correction factor to be incorporated into the liftsetting. However, the TS limit is a strict value that, does not take into account allowable Code tolerances or the use of a temperature correction factor when determining the setpoint. As immediate corrective action both unit's safety valves were declared inoperable. Engineering evaluation results indicate that the reactor vessel and the RHR system piping were always adequately protected against ovefpressure, and there was no safety significance associated with the inoperable valves.

The RHR system is currently operable and the LTOP TS requirements are being met. The root cause investigation forthis condition has not been completed.

As part ofthe investigation, instances where credit was taken for either SV-103 being operable with a PORV inoperable willalso be reviewed.

Upon completion ofthe investigation an update to this LER willbe submitted, including any additional corrective and preventive actions.

9904210035 9904i2 PDR ADQCK 050003i5 8

PDR