05000316/LER-2002-001, Containment Isolation Valve Alignment Error During Local Leak Rate Testing
| ML020910218 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/28/2002 |
| From: | Joseph E Pollock Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 02-001-00 | |
| Download: ML020910218 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3162002001R00 - NRC Website | |
text
Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1395 INDIANA MICHIGAN POWER March 28, 2002 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-74 Docket Nos. 50-316 Document Control Manager:
In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Report System, the following report is being submitted:
LER 316/2002-001-00: "Containment Isolation Valve Alignment Error during Local Leak Rate Testing" No new commitments are identified in this submittal.
Should you have any questions regarding this correspondence, please contact Mr. Gordon P. Arent, Manager, Regulatory Affairs, at 616/697-5553.
Sincerely, Joseph E. Pollock Site Vice President JM/pae Attachment A/
C:
G. P.
Arent A. C.
Bakken L.
Brandon J. E.
Dyer, Region III R. W. Gaston S. A.
Greenlee T. P.
Noonan R. P.
Powers M. W.
Rencheck R.
Whale NRC Resident Inspector Records Center, INPO
Abstract
On January 26, 2002, during refueling outage 13, 10 CFR 50 Appendix J, Type B and C leak rate testing was being performed in accordance with procedure 02-EHP-4030-234-203, "Unit 2 B & C Leak Rate." This procedure requires root shutoff valve 2-GPX-301-V1 [EIIS:LK:SHV] from the nitrogen supply manifold to be in the closed position for testing.
When core alterations commenced, valve 2-GPX-301-V1 was thought to be tagged "Do Not Operate" in the closed position as required by procedure 02-OHP-4030-STP-041, "Refueling Integrity". Upon successful completion of the leak rate testing, an auxiliary equipment operator (AEO) found the root shutoff valve 2-GPX-301-V1 in the open position during the valve lineup restoration. This resulted in refueling integrity being lost while fuel movement was in progress. The control room was notified and core alterations were suspended. Based on investigation of this incident, the valve was mispositioned for approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. This breach of refueling integrity is prohibited by Technical Specification (TS) and is therefore reportable in accordance with 50.73(a)(2)(i)(B).
The cause of this event was failure to follow procedures. The AEO performing the initial valve lineup for testing opened valve 2-GPX-301-Vl and inappropriately pulled the "Do Not Operate" tag from the valve contrary to the requirements of plant procedures 02-EHP-4030-234-203 and 02-OHP-4030.STP.041.
Operations restored valve 2-GPX-301-VI to the closed position, thereby re-establishing refueling integrity. A review of the completed B & C test lineups impacting refueling integrity was conducted and verified that no other loss of containment integrity had occurred during core alteration. A lessons learned memo was published and distributed to the auxiliary equipment operators. The human performance and personal accountability aspects of this issue have been appropriately addressed.
NRC FORM 366 (7-2001)
a.
_wS AA a s s A
NRC FORM 356A U.5. NUGLLAK KLUULAIUKT L.UMMI0IUN (7-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
- 6. LER NUMBER
- 3. PAGE YEAR SEQUENTIAL REVISION Donald C. Cook Nuclear Plant Unit 2 05000-316 NUMBER NUMBER 3 of 3 2002 01 00
- 17. TEXT (If more space is required, use additional copies of NRC Form (366A)
Conditions Prior to Event
Unit 1 - 100 percent power Unit 2 - MODE 6
Description of Event
On January 26, 2002, during reactor core offload for refueling outage 13, 10 CFR 50 Appendix J, Type B and C leak rate testing was being performed in accordance with procedure 02-EHP-4030-234-203, "Unit 2 B & C Leak Rate." Step 53 of the procedure provided valve lineup instructions for Type C leak rate testing of the nitrogen to pressurizer relief tank check valve 2-N-159. The auxiliary equipment operator (AEO) who preformed the valve lineup for testing signed off the procedure step indicating that the root shutoff valve 2-GPX-301-Vl from the nitrogen supply manifold was "closed" as required by procedure. Upon successful completion of the test, the procedure requires a valve restoration lineup. The test was not impacted by the mispositioned valve. A different AEO who performed the restoration for the valve lineup noticed that valve 2-GPX-301-Vl was in the "open" position, thereby creating a potential direct access from the containment atmosphere to the outside atmosphere. Upon discovery, the control room was notified and core alteration was suspended A post event investigation of this incident revealed that the AEO who performed the initial valve line up for testing observed that valve 2-GPX-301 -V1 was tagged "Do Not Operate Without SRO CA Permission" as required by procedure 02-OHP-4030-STP-041 for refueling integrity purposes. This AEO had been involved with previous testing that required the lifting of STP-041 tags. On January 26, 2002, the AEO performed the lineup which required valve 2-GPX-301-V1 to remain closed.
He had a mind set from the previous day's activities that he needed to remove the STP 41 tag and open the valve. The AEO inappropriately removed the tag and opened the valve without verifying the required position of the valve for testing.
Technical Specification (TS) requirement 3.9.4.c requires that each containment penetration providing direct access from the containment atmosphere to the outside atmosphere be either closed by an isolation valve, blind flange, manual valve, or equivalent. The failure to verify valve 2-GPX-301-V1 closed during core alteration resulted in a breach of refueling containment integrity. This breach of refueling integrity is prohibited by TS and is therefore reportable in accordance with 50.73(a)(2)(i)(B).
Cause of Event
The cause of this event was failure to follow procedures. The AEO who performed the lineup for B & C leak rate testing opened valve 2-GPX-301-VI and inappropriately pulled the "Do Not Operate" tag from the valve contrary to the requirements of plant procedures 02-EHP-4030-234-203 and 02-OHP-4030.STP.041.
Analysis of Event
The Bases for TS 3.9.4.c states that the requirements on containment building penetration closure and operability ensure that a release of radioactive material within the containment will be restricted from leakage to the environment. The operability and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in refueling mode.
Based on investigation of this incident the valve was mispositioned for approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. There was no impact on the health and safety of the public as a result of this event.
Corrective Actions
Upon discovery Operations restored valve 2-GPX-301-V1 to the closed position thereby re-establishing refueling integrity.
A review of the completed B & C testing lineups impacting refueling integrity was conducted and verified that no other loss of containment integrity had occurred during previous refueling operations.
NRC FURM 365A (7-2001)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION
- 1. FACILITY NAME Donald C. Cook Nuclear Plant Unit 2
- 17. TEXT (if more space is required, use additional copies of NRC Form (366A)
The human performance and personnel accountability aspect of this issue have been appropriately addressed.
A lessons learned memo was published and distributed to the auxiliary equipment operators.
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