05000423/LER-2004-001-01, Re Technical Specification Action Statement Not Met

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Re Technical Specification Action Statement Not Met
ML051040328
Person / Time
Site: Millstone Dominion icon.png
Issue date: 04/01/2005
From: Price A
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
04-390A, MPS Lic/BAK RO LER 04-001-01
Download: ML051040328 (6)


LER-2004-001, Re Technical Specification Action Statement Not Met
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition

10 CFR 50.73(a)(2)(ix)(A)

10 CFR 50.73(a)(2)(iii)

10 CFR 50.73(a)(2)(x)

10 CFR 50.73(a)(2)(iv)(A), System Actuation

10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor

10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat

10 CFR 50.73(a)(2)(v), Loss of Safety Function

10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
4232004001R01 - NRC Website

text

XA C Dominions Dominion Nuclear Connecticut, Inc.

Millstone Power Station Rope Ferry Road W'aterford, CT 06385 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 APR - 1 2005 Serial No.

MPS Lic/BAK Docket Nos.

License Nos.

04-390A RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION, UNIT 3 LICENSEE EVENT REPORT 2004-001-01 TECHNICAL SPECIFICATION ACTION STATEMENT NOT MET This letter forwards a supplement to Licensee Event Report (LER) 2004-001-01, documenting an event that occurred at the Millstone Power Station, Unit 3, on April 30, 2004. This supplemental LER reflects information developed after the original submittal of the LER.

If you have any questions or require additional information, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.

Very truly yours, tep Sai for J. Alan Price Site Vice President - Millstone

Serial No. 04-390A LER 2004-001-01 Page 2 of 2 Attachments: 1 Commitments made in this letter: None.

cc:

U.S. Nuclear Regulatory Commission (2 copies)

Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. G. F. Wunder Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08-B-1A Rockville, MD 20852-2738 Mr. M. Schneider NRC Senior Resident Inspector Millstone Power Station

Serial No. 04-390A Millstone Power Station, Unit 3 LER 2004-001-01 Millstone Power Station, Unit 3 Dominion Nuclear Connecticut, Inc. (DNC)

NRC FORM 366 APPROVED BY OMB NO. 3150-0104 Estimated burden per response to comply with this mandatory information collection request:

(7-2001)

COMMISSION 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are incorporated Into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records Management Branch (T-6 E6). U.S. Nuclear Regulatory Commission Washington. DC 20555-000I. or by Internet e-mail to blsl nrc.gov, and to the Desk Officer. Office of Information and Regulatory Affairs, LICENSEE EVENT REPORT (LER)

Neans0 usedto5p0-4nOfiienof Mlaencagenmdeont antd Budget. Washington. DC 20503. I a meanCuseStom seVENTatinEcllecTondoesnotdisplay a currently valid 0MB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, tsAA roverVn fnr rniomired mimhAr nf diit nihar eari Mnr oAnh htnkl the Information collection.

FACILITY NAME (1)

DOCKET NUMBER (2)

PAGE (3)

Millstone Power Station - Unit 3 05000423 1 OF3 TITLE (4)

Technical Specification Action Statement Not Met EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8) i FACILITY NAME DOCKETNUMBER MO DAY YEAR YEAR SEQUENTIAL REV MO DAY YEAR INUMBER I NO.

DAY YER 05000

_FACILITY NAME DOCKET NUMBER 04 30 2004 2004 - 001 - 01 04 01 2005 05000 OPERATING THIS REPORT IS SU'BMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR i: (Check all that apply) (11)

MODE (9) 20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)

POWER 000 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LEVEL (10) 20.2203(a)(1) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A)

_ 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)

OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)

Specify In Abstract below or 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) in (If more space Is required, use additional copies of NRC Formn 3664) (17)

When Inverter #INV-4 failed, the crew believed that the Technical Specification requirements were being met by two means: the fact that the Inverter was still energized and the belief that the "A" train electrical distribution could be credited. The ARP that would have prompted further consideration of the Technical Specification implications was not completed.

3.

Assessment of Safety Conseauences This event is of very low safety significance. The Operability of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that: (1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status. Inverter #INV-4 was still energized, although the alternate source is not credited for Operability. Even with Bus #VIAC-4 not supplied from the Technical Specification required source, the "B" train remained capable of providing power to the structures, systems and components credited with detecting and mitigating the following events: loss of residual heat removal, loss of offsite power, loss of reactor inventory and loss of refueling cavity level control.

At the time of this event, the "A" train onsite power distribution system was available (although not Operable since the "A" emergency diesel generator was out of service). The plant experienced a minor increase in positive reactivity, less than 15 PCM (percent millirho), for a period of about three hours.

4.

Corrective Action

The individuals involved have been coached and counseled on the human performance issues associated with this event. The Operations Manager provided lessons learned on this event to all operations personnel emphasizing the need to enter Technical Specification Action Statements when warranted by plant conditions.

The Operations Manager reinforced the expectation that Alarm Response Procedures be reviewed completely when used. Nuclear Training will provide a new Technical Specification worksheet to be used during training related to this event. Additional corrective actions are being addressed within the Millstone Corrective Action Program, (CR-04-08469, CR-04-08935, CR-04-10628).

5.

Previous Occurrences

No previous similar events or conditions were identified.

Energy Industry Identification System (EIIS) codes are identified in the text as [XX].