05000397/LER-1917-005, Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure

Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure

ML17313A741
Person / Time
Site:	Columbia
Issue date:	11/09/2017
From:	Hettel W Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-17-183 LER 17-005-00
Download: ML17313A741 (4)

LER-1917-005, Regarding Valve Closure Results in Momentary Increase in Secondary Containment Pressure

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x)
3971917005R00 - NRC Website

text

ENERGY NORTHWEST G02-17-183 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 William G. Hettel Columbia Generating Station P.O. Box 968, PE23 Richland, WA 99352-0968 Ph. 509-377-8311jF.509-377-4150 wghettel@energy-northwest.com 10 CFR 50.73

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 LICENSEE EVENT REPORT NO. 2017-005-00

Dear Sir or Madam:

Transmitted herewith is Licensee Event Report No. 2017-005-00 for Columbia Generating Station. This report is submitted pursuant to 10 CFR 50.73(a)(2)(v)(C) and 1 O CFR

50. 73(a)(2)(v)(D).

There are no commitments being made to the Nuclear Regulatory Commission herein. If you have any questions, or require additional information, please contact Ms. D. M.

Wolfgramm, Regulatory Compliance Supervisor, at (509) 377-4792.

Executed on this q-r"' day of November, 2017 Respectfully, W. G. Hettel Vice President, Operations : Licensee Event Report 2017-005-00 cc: NRC Region IV Administrator NRC NRA Project Manager NRC Senior Resident lnspector/988C CD Sonoda-BPA/1399 WA Horin -Winston & Strawn November 9, 2017

LICENSEE EVENT REPORT (LER)

NRC FORM 366 (04-2017)

U.S. NUCLEAR REGULATORY COMMISSION the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (See Page 2 for required number of digits/characters for each block) 1 OF

3. PAGE 05000

4. TITLE

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR SEQUENTIAL NUMBER REV NO.

FACILITY NAME 05000 DOCKET NUMBER FACILITY NAME 05000 DOCKET NUMBER

9. OPERATING MODE

10. POWER LEVEL

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT TELEPHONE NUMBER (Include Area Code) CAUSE SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX

CAUSE

SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX

14. SUPPLEMENTAL REPORT EXPECTED YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

NO

15. EXPECTED SUBMISSION DATE YEAR DAY MONTH ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

NRC FORM 366 (04-2017)

YEAR YEAR DAY MONTH 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(vii) 20.2203(a)(2)(ii) 20.2203(a)(2)(i) 20.2203(a)(1) 20.2201(d) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1)(i)(A) 50.36(c)(1)(ii)(A) 50.36(c)(2) 50.46(a)(3)(ii) 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71(a)(4) 73.71(a)(5)

OTHER Specify in Abstract below or in 3

3 Columbia Generating Station 397 2017 005 00