GO2-17-027, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and (SR) 3.4.4.1 Safety/Relief Valves Setpoint Lower Tolerance

Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and (SR) 3.4.4.1 Safety/Relief Valves Setpoint Lower Tolerance

ML17031A450
Person / Time
Site:	Columbia
Issue date:	01/31/2017
From:	Javorik A Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-17-027
Download: ML17031A450 (10)

Text

Alex L. Javorik Vice President, Engineering P.O. Box 968, Mail Drop PE023 Richland, WA 99352-0968 Ph. 509-377-2354 F. 509-377-8555 aljavorik@energy-northwest.com January 31, 2017 10 CFR 50.90 GO2-17-027 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 SUPPLEMENT TO LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT (SR) 3.4.3.1 AND SR 3.4.4.1 SAFETY/RELIEF VALVES (SRVs) SETPOINT LOWER TOLERANCE

Reference:

1. Letter GO2-16-046 from A. L. Javorik (Energy Northwest) to NRC:

"License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (SRVs) Setpoint Lower Tolerance," dated May 10, 2016 (ADAMS Accession No. ML16131A891)

2. Letter from L. John Klos (NRC) to M. E. Reddemann (Energy Northwest):

"Columbia Generating Station - Issuance of Amendment RE: Adoption of Technical Specification Task Force traveler TSTF-425, Revision 3 (CAC No. MF6042)," dated November 3, 2016 (ADAMS Accession No. ML16253A025)

Dear Sir or Madam:

By letter dated May 10, 2016 (Reference 1), Energy Northwest submitted a license amendment request (LAR), to modify Technical Specification (TS) Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (SRVs) Setpoint Lower Tolerance. Subsequent to submitting this LAR, Energy Northwest received amendment 238 (Reference 2) to Columbia's operating license and TS which moved certain surveillance requirement (SR) frequencies to an owner controlled Surveillance Frequency Control Program (SFCP).

Amendment 238 (Reference 2) has affected the TS pages which contain SR 3.4.3.1 and 3.4.4.1. This supplement provides the markups and clean pages for SR 3.4.3.1 and 3.4.4.1 in Attachments 1 and 2 respectively.

G02-17-027 Page 2of2 The No Significant Hazards Consideration Determination (NSHCD) provided in the original submittal is not altered by this submittal.

This letter and its attachments contain no regulatory commitments. If you should have any questions regarding this submittal, please contact Mr. R. M. Garcia, (509) 377-8463.

I declare ynder penalty of perjury that the foregoing is true and correct. Executed on 3/s[

day of.~~"<>tj

, 2017.

Respectfully, I

Vice President, Engineering Attachments: As stated.

cc:

NRG Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector - 988C CD Sonoda - BPA/1399 (email)

WA Horin - Winston & Strawn (email)

RR Cowley - WDOH (email)

EFSEC @utc.wa.gov (email)

GO2-17-027 PROPOSED TECHNICAL SPECIFICATIONS CHANGES (MARK-UPS)

Page 3.4.3-1 Page 3.4.3-2 Page 3.4.4-2

SRVs - 25% RTP 3.4.3 Columbia Generating Station 3.4.3-1 Amendment No. 149,169 225 238 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (SRVs) - 25% RTP LCO 3.4.3 The safety function of 12 SRVs shall be OPERABLE, with two SRVs in the lowest two lift setpoint groups OPERABLE.

APPLICABILITY:

THERMAL POWER 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required SRVs inoperable.

A.1 Reduce THERMAL POWER to < 25% RTP.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the required SRVs are as follows:

Number of Setpoint SRVs (psig) 2 1165 +/-+ 34.9

- 58.2 4

1175 +/-+ 35.2

- 58.7 4

1185 +/-+ 35.5

- 59.2 4

1195 +/-+ 35.8

- 59.7 4

1205 +/-+ 36.1

- 60.2 Following testing, lift settings shall be within +/-3%.

In accordance with the Inservice Testing Program

SRVs - 25% RTP 3.4.3 Columbia Generating Station 3.4.3-2 Amendment No.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.2 Verify each required SRV opens when manually actuated.

In accordance with the Surveillance Frequency Control Program

SRVs - < 25% RTP 3.4.4 Columbia Generating Station 3.4.4-2 Amendment No. 149,169,225,236,238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify the safety function lift setpoints of the required SRVs are as follows:

Number of Setpoint SRVs (psig) 2 1165 +/-+ 34.9

- 58.2 4

1175 ++/- 35.2

- 58.7 4

1185 ++/- 35.5

- 59.2 4

1195 ++/- 35.8

- 59.7 4

1205 ++/- 36.1

- 60.2 Following testing, lift settings shall be within +/-3%.

In accordance with the Inservice Testing Program SR 3.4.4.2

---

NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify each required SRV opens when manually actuated.

In accordance with the Surveillance Frequency Control Program

GO2-17-027 PROPOSED TECHNICAL SPECIFICATION PAGES (CLEAN)

Page 3.4.3-1 Page 3.4.3-2 Page 3.4.4-2

SRVs - 25% RTP 3.4.3 Columbia Generating Station 3.4.3-1 Amendment No. 149,169 225 238 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (SRVs) - 25% RTP LCO 3.4.3 The safety function of 12 SRVs shall be OPERABLE, with two SRVs in the lowest two lift setpoint groups OPERABLE.

APPLICABILITY:

THERMAL POWER 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required SRVs inoperable.

A.1 Reduce THERMAL POWER to < 25% RTP.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the required SRVs are as follows:

Number of Setpoint SRVs (psig) 2 1165 + 34.9

- 58.2 4

1175 + 35.2

- 58.7 4

1185 + 35.5

- 59.2 4

1195 + 35.8

- 59.7 4

1205 + 36.1

- 60.2 Following testing, lift settings shall be within +/-3%.

In accordance with the Inservice Testing Program

SRVs - < 25% RTP 3.4.4 Columbia Generating Station 3.4.4-2 Amendment No. 149,169,225,236,238 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify the safety function lift setpoints of the required SRVs are as follows:

Number of Setpoint SRVs (psig) 2 1165 + 34.9

- 58.2 4

1175 + 35.2

- 58.7 4

1185 + 35.5

- 59.2 4

1195 + 35.8

- 59.7 4

1205 + 36.1

- 60.2 Following testing, lift settings shall be within +/-3%.

In accordance with the Inservice Testing Program SR 3.4.4.2

---

NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify each required SRV opens when manually actuated.

In accordance with the Surveillance Frequency Control Program

SRVs - 25% RTP 3.4.3 Columbia Generating Station 3.4.3-2 Amendment No.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.2 Verify each required SRV opens when manually actuated.

In accordance with the Surveillance Frequency Control Program