05000354/LER-2007-003, Regarding Grab Samples Not Performed as Required by Technical Specification 3.3.7.1
| ML072490205 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/30/2007 |
| From: | Jamila Perry Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N07-0220 LER 07-003-00 | |
| Download: ML072490205 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3542007003R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 V
PSEG Nuclear LLC 10CFR50.73 AUG 3 0,2007 LR-N07-0220 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Hope Creek Generating Station Unit 1 Facility Operating License No. NPF-57 Docket No. 50-354
Subject:
Licensee Event Report 2007-003-00 In accordance with 10 CFR 50.73(a)(2)(i)(B), PSEG Nuclear LLC, is submitting Licensee Event Report Number 2007-003-00, Docket No. 50-354.
Should you have any questions concerning this letter, please contact Mr. Francis D. Possessky at (856) 339-1160.
Sincerely, John F. Perry Plant Manager Hope Creek Generating Station
Attachment:
Licensee Event Report 95-2168 REV. 7/99
A LR-N07-0220 Page 2 cc:
Mr. S. Collins, Administrator - Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager - Hope Creek U.S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555-0001 USNRC Resident Inspector office - Hope Creek (X24)
Mr. P. Mulligan, Manager IV (Acting)
Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625
kt NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the digits/characters for each block) information collection.
- 3. PAGE Hope Creek Generating Station 05000354 1 OF 3
- 4. TITLE Grab Samples Not Performed As Required By Technical Specification 3.3.7.1
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEUMENILREVO MONTH DAY YEAR N/A NUMBER NO.N/
FACILITY NAME DOCKET NUMBER 07 01 2007 2007 003 -
00 08 30 2007 N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[] 20.2201(b)
[1 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 1 0l 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
[] 50.73(a)(2)(viii)(A) 0l 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
E-50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
[] 20.2203(a)(2)(ii)
ED 50.36(c)(1)(ii)(A)
[I 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
E] 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
[1 73.71(a)(5) 100
[] 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
[
50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
Francis D. Possessky, Compliance Engineer 856-339-1160CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION [E YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 0 NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On July 01, 2007, offgas flow started rising. In anticipation of offgas flow approaching its upper limit of 75 standard cubic feet per minute (scfm) for instrument operability, Operations directed Radiation Protection (RP) to enter correction factor changes into the Offgas Pretreatment Radiation Monitoring System (RMS) as directed by Note 4 of the Main Condenser Vacuum abnormal operating procedure (AOP). Offgas Pretreatment RMS must be declared inoperable when offgas flow increases to 75scfm, and can be declared operable once the required correction factor changes are entered into the RMS.
On July 04, 2007, when offgas flow decreased below 75 scfm, Operations requested RP to remove the correction factors that had been entered into the Offgas Pretreatment RMS on July 01, 2007. RP communicated to Operations that no correction factors were entered into the Offgas Pretreatment RMS, instead, alert setpoint changes had been made. Operations then declared the Offgas Pretreatment RMS inoperable, and had been inoperable since Offgas Flow went above 75 scfm on July 01, 2007.
Tech Spec 3.3.7.1 required grab samples were not performed during the period of inoperability.
The root cause of this event was inadequate procedural direction to guide the RP technicians to perform the action as required by the Operations AOP.
The RP procedure, 'Control of Radiation Monitoring System Setpoints,' will be revised to include guidance to make temporary correction factor changes to the RMS when required.
NRC FORM 366 (6-2004)U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME
- 2. DOCKET
- 6. LER NUMBER
- 3. PAGE Y SEQUENTIAL REVISION Hope Creek Generating Station 05000354 NUMBER NUMBER 2 OF 3 2007 003 00
- 17. TEXT (If more space is required, use additional copies of NRC Form 366A)
PLANT AND SYSTEM IDENTIFICATION
General Electric-Boiling Water Reactor (BWR/4)
Radiation Monitoring System - {IL}
Offgas System - {WF}
- Energy Industry Identification System {EIIS} codes and component function identifier codes appear as
{SS/cCc}
IDENTIFICATION OF OCCURRENCE Event Date/Time: July 01, 2007 - 06:02 Discovery Date/Time: July 04, 2007 - 03:00 CONDITIONS PRIOR TO OCCURRENCE Hope Creek was in Operational Condition 1 with reactor power at 100%. No other structures, systems, or components were inoperable that contributed to the event.
DESCRIPTION OF OCCURRENCE On June 30, 2007, offgas flow {WL/-} began rising from 34 scfm. The operating shift entered the Main Condenser Vacuum abnormal operating procedure (AOP), in anticipation of offgas flow rising to 75 scfm.
The Shift Manager contacted the on-shift Radiation Protection (RP) technicians to inform them of the requirements in the AOP to change the correction factor of the Offgas Preteatment Radiation Monitoring System (RMS) {WF/-}. An RP supervisor was called in to support the RP technicians in performing the actions.
On July 01, at approximately 0330, offgas flow continued to rise to 70 scfm, and the Shift Manager (SM) directed RP to make the changes to Offgas Pretreatment RMS in accordance with the AOP. RP communicated to the SM that the RP procedure referenced in the AOP provides no guidance on changing RMS correction factors. Additionally, the RP procedure makes no reference to the calculation used to change the correction factor as mentioned in the AOP. The on shift Control Room Supervisor (CRS) developed the correction factor using calculation HA-0053 and provided this to RP. Through discussions with the RP Supervisor, RP determined that Form 3 of Control of Radiation Monitoring Setpoints should be used to incorporate the correction factor into alert setpoint changes. RP then informed the on shift CRS that they were prepared to make the required changes to the Offgas Pretreatment RMS. The CRS provided this information to the Shift Manager. At 0602 on July 1, offgas flow rose above 75 scfm and Operations declared the RMS inoperable in accordance with Technical Specification (TS) 3.3.7.1. At 0655, RP reported that the changes required to the Offgas Pretreatment RMS were completed. At 0700, Operations declared the Offgas Pretreatment RMS operable.
On July 04, 2007, offgas flow lowered below 75 scfm and Operations directed RP to remove the correction factor. RP reported to the shift that no correction factor was ever entered and that the changes made to the Offgas Pretreatment RMS were changes to the alert setpoints. As a result, the Offgas Pretreatment RMS was inoperable from July 01 to July 04, 2007. With the Offgas Pretreatment RMS inoperable, TS 3.3.7.1 requires the performance of periodic grab samples that were not performed. Therefore the event is reportable under 10CFR50.73 (a)(2)(i)(B) as a TS prohibited condition.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
- 1. FACILITY NAME
- 2. DOCKET
- 6. LER NUMBER
- 3. PAGE SEQUENTIAL REVISION
- 1.
ACLIT NME2.
OCET ERNUMBER 3.UPAGE Hope Creek Generating Station 05000354 NUMBER NUMBER 3 OF 3 2007 003 00
- 17. TEXT (If more space is required, use additional copies of NRC Form 366A)
CAUSE OF OCCURRENCE The root cause of this event was inadequate procedural direction to guide the RP technicians to perform the action as required by the Operations AOP.
PREVIOUS OCCURRENCES
A review of previous reportable events at Hope Creek was performed to determine if a similar event had occurred. No similar events were identified.
SAFETY CONSEQUENCES
The safety consequences of this event are minimal. This event resulted in no nuclear, radiological, or industrial safety consequences. Reactor analysis performed showed no increase in fission product activity during the period of the Offgas Pretreatment RMS inoperability, and the offgas samples obtained following the incident were as expected.
A review of this event determined that a Safety System Functional Failure (SSFF) has not occurred as defined in Nuclear Energy Institute (NEI) 99-02.
CORRECTIVE ACTIONS
The RP procedure, 'Control of Radiation Monitoring System Setpoints,' will be revised to include guidance to make temporary correction factor changes to RMS when required.
COMMITMENTS
This LER contains no commitments.