05000348/LER-2003-002, Reactor Pressure Vessel Head Set in Place with Technical Specification 3.4.12 Not Met
| ML031700016 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/16/2003 |
| From: | Beasley J Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-03-1272 LER 03-002-00 | |
| Download: ML031700016 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3482003002R00 - NRC Website | |
text
J. Bamie Beasley, Jr., P.E.
Vice President Southem Nuclear Operating Company, Inc.
40 Invemess Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7110 Fax 205.992.0341 June 16, 2003 Docket No.: 50-348 SOUTHERNA COMPANY Energy to Serve Your Worl' NL-03-1272 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit I Licensee Event Report 2003-002-00 Reactor Pressure Vessel Head Set in Place with Technical Specification 3.4.12 Not Met Ladies and Gentlemen:
Joseph M. Farley Nuclear Plant - Licensee Event Report (LER) No. 2003-002-00 is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B).
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, JBB/WAS/sdl Enclosure: Licensee Event Report 2003-002-00 cc:
Southern Nuclear Operating Company Mr. J. D. Woodard, Executive Vice President Mr. D. E. Grissette, General Manager - Plant Farley Document Services RTYPE: CFA04.054; LC# 13797 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. F. Rinaldi, NRR Project Manager - Farley Mr. T. P. Johnson, Senior Resident Inspector - Farley
NRC FORM 366 U.S. NUCLEAR REGULATORY
~~~APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-204 NRC FORM 366 U.S. NUCLEAR REGULATORY Estimated bturden per response to comply wih this mandatory information collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
(7-2001)
COMMISSION Reported lessons learned are incorporated into the icensing process and fed back to industry. Send comments regarding bu rden estimate to the Records Management Branch (T-6 E6), U S. Nudear Regulatory Commission, Washington, DC 20555-001 or by internet eeail to bjsl@nrc.gov, and to the LICENSEE EVENT REPORT (LER)
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FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Joseph M. Farley Nuclear Plant - Unit1 05000 348 l
1 OF 3
TITLE (4)
Reactor Pressure Vessel Head Set in Place with Technical Specification 3.4.12 Not Met EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MO DAY YEAR YEAR NUMBER NO MO DAY YEAR 05000 04 22 2003 2003 002 0
06 16 2003 FACILITY NAME DOCKET NUMBER OPERATING 6
THIS REPORT IS SUBMITTE PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) (1 1)
MODE (9) 6 120.2201(b) 20.2203(a)(3xi,)
50.73(a2XXB) 50.73(a2Xix)(A)
POWER 20.2201(d) 20.2203(aX4) 50.73(aX2Xiii) 50.73(aX2)(x)
LEVEL (10) 0 20.2203(aXl) 50-36(cX1)(i)(A) 50.73(aX2)(ivXA) 73.71(aX4) 20.2203(aX2Xi) 50.36(c)(1 XiiXA) 50.73(aX2XvXA) 73.71(aX5) 20.2203(a)(2XU) 50.36(c)(2) 0.73(a)(2XvXB)
OTHER 20.2203(a)(2Xiii) 50-46(aX3ii) 150.73(aX2)(v)(C)
Specify in Abstract below or in 20.2203(aX2)(iv) 50.73(aX2XiXA) 150.73(aX2XvXD)
(If more space is required, use additional copies of NRC Fonn 366A) (17)
Westinghouse -- Pressurized Water Reactor Energy Industry Identification Codes are identified in the text as [XX]
Description of Event
On April 22, 2003, at 1745, during routine shift monitoring activities, it was determined that Farley Nuclear Plant Unit I had been operated contrary to Technical Specification 3.4.12, Low Temperature Overpressure Protection System, since 1244 on April 22, 2003 in that the reactor vessel head had been set with three charging pumps capable of injecting into the RCS. Technical Specification 3.4.12 requires that a maximum of one charging pump be operable in Modes 5 and 6 when the reactor vessel head is in place and one or more RCS cold legs is < 1 80°F.
On April 21, 2003, Unit I was in a refueling outage with the RCS [AB] drained to the reactor vessel flange and the plant in Mode 6. Night shift initiated, but did not issue, a tag order to tag out 2 of 3 available charging pumps in anticipation of setting the reactor vessel head. Per the nornal shift surveillance procedure, a maximum of one charging pump shall be operable whenever the temperature of one or more RCS cold legs is < 1 80°F and the Reactor Vessel Head is installed. However, since the reactor head was not set, the procedure step to tag out 2 of the 3 charging pumps was marked not applicable for night shift. At 1244 on dayshift April 22, the reactor head was set. The tag order was in the tagging office ready to implement at the time of the event (setting the reactor head). At 1745 that same evening, while completing the normal shift monitoring activities, the discovery was made that greater than one charging pump was available. The tag order was implemented, and two of the three charging pumps were made incapable of injection into the RCS as required by Technical Specifications by 1821 on April 22, 2003.
Cause of Event
This event was caused by inadequate procedure in that the Unit Operating Procedure for setting the reactor vessel head did not address the limitation on the number of charging pumps available prior to setting the head. A contributing cause was cognitive personnel error in that equipment alignment was insufficiently reviewed prior to setting the head.
Safety Assessment
No overpressure condition occurred during this event. During this event, the reactor vessel head, although set in place on the vessel, was not bolted. In the event that a mass injection transient occurred, such as start of all three charging pumps, the head would have lifted off its seating surface thereby preventing an overpressure condition.
Therefore, the health and safety of the public were unaffected by this event.
This event does not represent a Safety System Functional Failure.
(f more space is required, use additional copies of NRC Form 366A) (17)
Corrective Action
The applicable Unit Operating Procedures on both units have been revised to add appropriate inforrnation from Technical Specification 3.4.12.
Personnel involved have been coached.
A Training Advisory Notice on this procedure change was sent to Operations personnel. This event has been discussed with Operations personnel in shift briefings.
Additional Inforrnation The following LERs were submitted in the last two years concerning inadequate procedure, standards, or other guidance:
LER 2002-003-00 Unit 1 Technical Specification Violation due to section of Condensate Storage Tank Missile Barrier Not in Place LER 2002-001-00 Unit I Reactor Trip Due to Inadvertent Electrical Contact During Recorder Maintenance LER 2001-001-00 Unit 2 Reactor Trip due to Main Generator Neutral Connecting Bolt Failure