05000285/LER-1998-001, :on 980202,TS Violation Occurred Due to Inadequate Inservice Testing.Caused by Lack of Attention to Detail When FCS ISI Program Plan for 3rd ten-year Interval Was Put Together in 1992.Changes Will Be Made
| ML20217N927 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/03/1998 |
| From: | Bloyd C, Gambhir S OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-98-001, LER-98-1, LIC-98-0028, LIC-98-28, NUDOCS 9803090335 | |
| Download: ML20217N927 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) |
| 2851998001R00 - NRC Website | |
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8998 OnahnP&PemwDen:t 444 Soush folh Swer Maf Onahe, Nebranks 661MD47 March 3, 1998 LIC-98-0028 U.
S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station F1-137 Washington, DC 20555
Reference:
Docket No. 50-285 1
Subject:
Licensee Event Report 1998-001 Revision 0 for the Fort Calhoun Station Please find attached Licensee Event Report 1998-001 Revision 0 dated March 3, 1998. This report is being submitted pursuant to i
10CFR50.73 (a) (2) (i) (B). If you should have any questions, please contact me.
- Sycerely, S.
K. Gambhir Division Manager Engineering & Operations Support 71 EPM / epm Attachment c:
E. W. Merschoff, NRC Regional Administrator, Region IV L. R. Wharton, NRC Project Manager W.
C. Walker, NRC Senior Resident Inspector INPO Records Center Winston and Strawn 9003090335 900303 ADOCK0500g5 DR
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1 25 5124 Employment with Equa! Opportunity
NRC FORJ 366 U.S. NUCLEAR RE%ULATORY COMMISSION APPAOVED BY OMB NO. 3150-0104 W6)
EXP!RES 4/30/98 NFENEEo0$tte"CNE [$u7s"T'!00HR POR7 DL "S O D
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PAGE (3)
Fort Calhoun Station Unit No.1 05000285 i OF 3 flT LE (4)
Technical Specification Violation Due to Inadequate Inservice Testing
~
EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
F ACILITY NAME DOCKET NUMBER 8 U L
8'"
MONTH DAY YEAR YEAR MONTH DAY YEAR 05000 UMBER N RER F ACILITY NAME DOCKET NUMBER 02 02 1998 1998
-- 0 01 -- 01 03 03 1998 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR61 (Check one or more l(11)
MODE (9) 1 20.2201(b) 20.2203(aX2Xv)
X 50.73(a)(2Xi) 50.73(aX2)(viii)
POWER 20.2203(a)(1) 20.2203(aX3XI) 50.73(aX2Xil) 50.73(aX2)(x)
LEVEL (10) 100 20.2203(aX2X6) 20 2203(aX3Xii) 50 73(aX2)(m) 73.71 20.2203(a)(2)(ll) 20.2203(aW4) 50.73(aK2Xiv)
OTHER 20.2203(aX2Xiii) 50.36(cK1) 50.73(a)(2)(v)
Specify in Abstract below r in NRC Form 366A 20 2203(aX2Xiv) 50.36(c)(2) 50.73(aX2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (include Area Code)
Charles N. Bloyd, Supervisor Component Testing 402-533-6921 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
^
CAUSE
SYSTEM COMPONENT MANUFACTUREN
CAUSE
SYSTEM COMPONENT MANUFA;TURER O gp T EP l
SUPPLEMENTAL REPORT EXPECTED L14)
EXPECTED MONTH DAY YEAR YEs SUBMISSION (if yes, complete EXPECTED SUBMISSION DATE)
X NO DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
While conducting a Self Assessment of the In-Service Testing (IFT) and In-Service Inspection (ISI) program at the Fort Calhoun Station (FCS) a portion of the program was found not to be in compliance with the appropriate version of the American Society of Mechanical Engineers (ASME) code as required by Technical Specifications. Specifically, the FCS IST Program does not identify the Safety Injection Tank Discharge Isolation Valves (HCV-2914, HCV-2934, HCV-2954 and HCV-2974) as safety related passive valves and does not specifically identify a test that verifies satisfactory operation of the remote position indication function of these valves at least every two years. Nuclear safety is not considered to be impacted by this condition because FCS uses other means (other than relying on remote position indicating lights) to control the position of passive safety related valves.
The primary cause for this condition goes back to lack of attention to detail when the FCS ISI Program Plan for the third ten-year interval was put together during 1992.
FCS will review the safety system draw?ngs and identify the passive safety related valves as defined by the AFME Cmde. FCS will make the required changes to the ISI Program Plan and procedurt.9 c.mnged as appropriate.
NRC FORM 366 (445)
NRC FOiM 366A U.S. NUCLEAR REGULATORY COMMISSION P*H l
LICENSEE EVENT REPORT (LER) l TEXT CONTINUATION i
- - Facti fTY NAMF li)
DOCKET
[ FR NUMRFR f 6)
PAGE f 3)
SEQUENTIAL REVISON l
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NUMBER NUMBER Fort Calhoun Station Un't No. 1 05000285 2 OF 3 1998 001 -
00 TEKT (6 more space is,ennsred, use ad@toonal copses of NRC Form 366A)(11)
BACKGROUND Fort Calhoun Station (FCS) started its third ten-year In-Service Inspection (ISI) interval on September 26, 1993. The applicable code for In-Service Testing (IST) activities in the second ten-year interval at FCS was the 1980 Edition, Winter 1980 Addendum (80W80) of American Society of Mechanical Engineers (ASME)
Section XI. Subsection IWV of ASME XI, 80W80, which defines the ISI valve testing requirements, did not require remote position indication verification testing for passive valves (see Table IWV-3700-1 " Inservice Test Requirements",
Note 1).
l The applicable code for IST activities in the third ten year interval at FCS is the 1989 Edition (No Addendum) of ASME Section XI. The valve test section (IWV) of ASME XI, 1989 Edition states that valve testing shall be done according to (American National Standards Institute (ANSI)) ASME/ ANSI OM " Operation and Maintenance of Nuclear Power Plants" (Part 10). 10 CFR 50.55a, paragraph (b) (2) (viii), states that the specified Edition of ASME/ ANSI OM part 10 shall be the OMa-1988 Addenda to the OM-1987 Edition (OMa 88). Table 1 " Inservice Test Requirements," of OMa 88, Part 10, requires that safety related passive valves that have remote position indication capability have a test in place to verify remote position indication at least every two years.
j
EVENT DESCRIPTION
During the week of January 19, 1998, a self assessment was performed on FCS's ISI/IST Program. One aspect of this self assessment was to review the code compliance of the ISI/IST Program. The assessment team determined that the FCS IST Program may not be in compliance with the testing requirements for remote position indication of safety related passive valves found in Table 1 of OMa 88.
Specifically, the FCS IST Program does not identify the Safety Injection Tank Discharge Isolation Valves (HCV-2914, HCV-2934, HCV-2954 and HCV-2974) as safety related passive valves and does not specifically identify a test that verifies satisfactory operation of the remote position indication function of these valves at least every two years.
A review was conducted to determine compliance with ASME code standards and reportability under 10 CFR 50.73 guidance. On February 2, 1998, it was determined that FCS had not complied with ASME code testing requirements and that this situation was reportable. This report is being submitted pursuant to 10CFR50.73 (a) (2) (1) (B).
SAFETY SIGNIFICANCE
The reported condition is not considered to be safety significant and is not considered to represent an operability concern. Nuclear safety is not considered to be impacted by this condition because FCS uses other means (other than relying on remote position indicating lights) to control the position of passive safety related valves. FCS Operators rely on administratis. controls, such as procedurally verifying valve lineups prior to changing the plant operating mode
NGC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION
$346)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION Facif fTY NAME fil DOCKET IFP NUMRFRfG)
PAGE f 3)
SEQUENTIAL REVISION GR NUMBER NUMBER Fort Calhoun Station Unit No. 1 05000285 3 OF 3 4
1998 - 001 -
00 1
TEX 1 pf mtwo spece en required, use addMenal econes of NRC Form 366A)(17}
l or locking certain passive safety related valves in their safety position, to I
ensure that passive valves important to safety at FCS are in the proper position. In addition, a review of identified valves indicates that at least some of the valves positions had been verified by other plant procedures.
However, those procedures did not reference the ISI/IST program. Based on these considerations, this event has minimal safety significance.
CONCLUSION The primary cause for this condition is a lack of attention to detail when the FCS ISI Program Plan for the third ten-year interval was developed during 1992.
When the ISI Program Plan was developed for the third ten-year interval, the responsible FCS personnel interpreted the code to only require remote position indication verification testing for position indicators that were used in stroke timing valves defined as active valves in the ISI Program. That is, the requirement in Table 1
- Inservice Test Requirements," of OMa 88, Part 10, requiring that safety related passive valves that have remote position indication capability have a tent in place to verify remote position indication at least every two years, was overlooked. This oversight allowed the ISI Program to
- default" back to the earlier Code that did not require position indication testing of passive valves.
A contributing cause for this condition is that no self assessment had been performed on the ISI/IST Program since the beginning of the third ten year interval.
This issue is of generic concern in that there are several other valves within FCS's safety systems that are passive safety related valves that are not identified or tested under the FCS IST Program.
CORRECTIVE ACTIONS
1.
FCS shall review safety system drawings and identify passive safety related valves as defined by the code and determine which of these valves have remote position indication. This action is expected to be completed by September 1,
1998.
2.
FCS will make appropriate changes to the ISI Program Plan. These changes will include identifying safety related passive valves, with remote position indication and ensuring they function properly at least every two years and/or request code relief from this requirement, if such relief is justified. This will be completed by December 31, 1998.
PREVIOUS SIMILAR EVENTS
There have not been any previous events where ASME Code misinterpretation resulted in a violation of ASME XI requirements.
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