05000387/LER-2008-001, Regarding Irradiated Fuel Movement Without All Required Radiation Monitoring Operable
| ML080990622 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/31/2008 |
| From: | Gannon C Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-6337 LER 08-001-00 | |
| Download: ML080990622 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(i)(B), Prohibited by Technical Specifications |
| 3872008001R00 - NRC Website | |
text
W.
C. J. Gannon Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3050 Fax 570.542.1504 cjgannon@pplweb.com 10 6 P
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MAR 3 12008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OPl-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387/2008-001-00 LICENSE NO. NPF-14 PLA-6337 Docket Nos. 50-387 50-388 Attached is Licensee Event Report (LER) 50-387/2008-001-00. This event was determined to be a loss of Safety Function and reportable under 10 CFR 50.73(a)(2)(v)(C) in that the high exhaust radiation monitors in both Units 1 and 2 were disabled during irradiated fuel moves. The disabled monitors would not have initiated automatic re-alignment of the Reactor Building Ventilation System and the Control Room Emergency Outside Air Supply (CREOAS) System in response to an actual high radiation condition. Jumpers that had defeated the radiation monitor actuation capability have since been removed.
There were no actual consequences to the health and safety of the public as a result of this event.
No commitments are associated with this LER.
- - Nuclear Operations Attachment Document Control Desk PLA-6337 cc:
Mr. S. Collins Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. F. Jaxheimer Sr. Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35 Berwick, PA 18603-0035 Mr. R. Osborne Allegheny Electric Cooperative P. 0. Box 1266 Harrisburg, PA 17108-1266 Mr. R. R. Janati Bureau of Radiation Protection Rachel Carson State Office Building P. 0. Box 8469 Harrisburg, PA 17105-8469
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)
, the NRC may (See reverse for required number of not conduct or sponsor, and a person is not required to respond to, the diqits/characters for each block) information collection.
- 3. PAGE NAME Susquehanna Steam Electric Station Unit 1 05000 387 1
OF 3
- 4. TITLE Irradiated fuel movement without all required radiation monitoring operable.
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIALý REV MONTH I
YEAR FACILITY NAME DOCKET NUMBER MN DA YA YEAR SUE RENO.
NTH DAY YEAR Susquehanna SES - Unit 2 05000 388 I
FACILITY NAME DOCKET NUMBER 02 05 2008 2008 1
0 03 31 2008 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 F] 20.2201(b)
Q 20.2203(a)(3)(i)
F] 50.73(a)(2)(i)(C)
[] 50.73(a)(2)(vii)
El 20.2201(d)
[J 20.2203(a)(3)(ii)
Q 50.73(a)(2)(ii)(A)
[
50.73(a)(2)(viii)(A)
[= 20.2203(a)(1) "l 20.2203(a)(4)
[] 50.73(a)(2)(ii)(B)
Q 50.73(a)(2)(viii)(B)
_ 20.2203(a)(2)(i)
E 50.36(c)(1)(i)(A) 5 50.73(a)(2)(iii) 5 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 20.2203(a)(2)(ii)
[J 50.36(c)(1)(ii)(A) 5 50.73(a)(2)(iv)(A) 5 50.73(a)(2)(x) 1] 20.2203(a)(2)(iii) 5 50.36(c)(2) fl 50.73(a)(2)(v)(A)
E] 73.71 (a)(4) 100%
20.2203(a)(2)(iv) 5 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 5 73.71 (a)(5)
E] 20.2203(a)(2)(v) 5 50.73(a)(2)(i)(A)
- J 50.73(a)(2)(v)(C) 5 OTHER [J 20.2203(a)(2)(vi) jJ 50.73(a)(2)(i)(B)
[
50.73(a)(2)(v)(D)
Specify in Abstract below or in
CORRECTIVE ACTIONS
The following corrective actions have been completed:
" Temporarily increased management oversight to re-enforce operator fundamentals.
" Individual performance deficiencies relative to this event were addressed.
" Revised the Fuel Handling procedure to include a system status file operability check, LCO/TRO & potential LCO/TRO log review, Ul & U2 Unit Supervisor verification, and Shift Manager Review.
The following corrective actions are planned:
" Develop methodology for scheduling risk significant equipment/systems out of service that span more than one week.
" Review and revise Work Management (WM) procedures. Provide training to WM personnel on guidance for risk identification, assessment and management to ensure consistency.
" Review the standards for procedure adherence with WM personnel and include this event in the discussion.
" Update terminology in the revised Fuel Handling procedure relative to 'independent review' to coincide with established station standards.
ADDITIONAL INFORMATION
Failed Component Information:
None
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