05000280/LER-1917-001, Regarding Shutdown Due to an Unisolable Leak in Reactor Coolant Pressure Boundary
| ML17297A457 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/06/2017 |
| From: | Mladen F Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 17-001-00 | |
| Download: ML17297A457 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 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)(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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 2801917001R00 - NRC Website | |
text
October 6, 2017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001
Dear Sir or Madam:
10CFR50.73 Virginia Electric and Power Company Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 Serial No.:
17-366 SPS:
TSC Docket No.: 50-280 License No.: DPR-32 Pursuant to 10CFR50.73, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Unit 1.
Report No. 50-280 / 2017-001-00 This report has been reviewed by the Station Facility Safety Review Committee and will be forwarded to the Management Safety Review Committee for its review.
Enclosure Commitment contained in this letter: None Very truly yours, F. Mladen, Site Vice President Surry Power Station cc:
U.S. Nuclear Regulatory Commission, Region II Marquis One Tower, Suite 1200 245 Peachtree Center Ave., NE Atlanta, GA 30303-1257 NRC Senior Resident Inspector Surry Power Station
.",.i NRG FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017)
!J.llp://www.nrc.gov/rn.f!ding-rm/doc-cgllections/nL!@.9slsJ.afflfil1022/r3/l the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection;
- 3. PAGE Surry Power Station, Unit 1 05000 280 I
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- 4. TITLE Unit 1 Shutdown due to an Unisolable Leak in Reactor Coolant Pressure Boundary
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 08 09 2017 2017 -
001 -
00 10 11 2017 05000
- 9. OPERATING MODE 11: THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201 (b)
D 20.2203(a)(3)(i)
[{] 50.73(a)(2)(ii){A)
D 50.73(a)(2)(viii)(A)
N D
20.2201 (d).
- D 20.2203(aj(3)(ii)
D*.so. 73(a)(2}(ii)(B)
. o* 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D so.73(a~(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A).
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D
- 20.2203(a){2){ii)
D 50.36(c){1)(ii)(A)
D 50.73(a){2)(v)(A) _
- - D 73.71(<!)(4)
D 20.2203(a)(2)(iii)
D so.3a(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(s)
D 20.2203(a)(2)(iv)
Q 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1) 32 D
20.2203(a)(2)(v)
[{] 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii) 17;; --* -
D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in
5.0 ADDITIONAL CORRECTIVE ACTIONS
YEAR 2017 -
SEQUENTIAL NUMBER 001 REV NO.
00 An American Society of Mechanical Engineers (ASME) Code repair will be completed, and the tubing and the RCS hot leg sample system valve will be restored to design specifications and functionality during the next Unit 1 refueling outage.
6.0 ACTIONS TO PREVENT RECURRENCE Corrective actions determined by the apparent cause evaluation will be implemented in accordance with the corrective action program.
7.0 SIMILAR EVENTS
None 8.0 MANUFACTURER/MODEL NUMBER NUPRO SS-6UG-TN3-:4C
9.0 ADDITIONAL INFORMATION
Unit 2 was at 100 percent power at the time of this event and was unaffected by the Unit 1 shutdown. There were no other structures, systems, or components that were inoperable at the start of the event that contributed to the event. Page 3
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