ML21106A286

Correction to Amendment Nos. 188 and 175 Regarding Relocation of Surveillance Test Intervals to Licensee-Controlled Program (Risk-Informed Initiative 5b)

ML21106A286
Person / Time
Site:	South Texas
Issue date:	05/06/2021
From:	Dennis Galvin Plant Licensing Branch IV
To:	Gerry Powell South Texas
Galvin D
References
TAC MD7058, TAC MD7059
Download: ML21106A286 (4)

Text

May 6, 2021 Mr. G. T. Powell President and Chief Executive Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483

SUBJECT:

SOUTH TEXAS PROJECT, UNITS 1 AND 2 - CORRECTION TO AMENDMENT NOS. 188 AND 175 REGARDING RELOCATION OF SURVEILLANCE TEST INTERVALS TO LICENSEE-CONTROLLED PROGRAM (RISK-INFORMED INITIATIVE 5b) (TAC NOS. MD7058 AND MD7059)

Dear Mr. Powell:

By letter dated October 31, 2008 (Agencywide Documents Access System (ADAMS) Accession No. ML082830220), the U.S. Nuclear Regulatory Commission (NRC, the Commission) issued, in part, Amendment No. 188 to Facility Operating License No. NPF-76 and Amendment No. 175 to Facility Operating License No. NPF-80 for the South Texas Project, Units 1 and 2, respectively. The amendments revised the technical specifications (TSs) to relocate surveillance frequencies of most surveillance tests from the TS to a licensee-controlled surveillance frequency control program.

The amendments contained, in part, Technical Specification Page 3/4 4-6 that included a typographical error in the fifth line of Limiting Condition for Operation (LCO) 3.4.1.4.2, Action c.

Specifically, the word closed was misspelled as losed. There were no changes to LCO 3.4.1.4.2, Action c issued with the amendments. The enclosure to this letter provides a corrected copy of Technical Specification Page 3/4 4-6 to replace the page sent in our October 31, 2008, letter.

If you have any questions, please contact me at 301-415-6256 or Dennis.Galvin@nrc.gov.

Sincerely,

/RA/

Dennis J. Galvin, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499

Enclosure:

Correction to Technical Specification Page 3/4 4-6 cc: Listserv

ENCLOSURE CORRECTION TO TECHNICAL SPECIFICATION PAGE 3/4 4-6 TO AMENDMENT NOS. 188 AND 175 STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499

REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.2

a. At least two residual heat removal (RHR) loops shall be OPERABLE* and at least one RHR loop shall be in operation**, and

b. Each valve or mechanical joint used to isolate unborated water sources shall be secured in the closed position.

APPLICABILITY: MODE 5 with reactor coolant loops not filled.

ACTION:

a. With less than the above required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.

b. With no RHR loop in operation, suspend all operations that would cause introduction into the RCS of coolant with boron concentration less than required to meet SHUTDOWN MARGIN of LCO 3.1.1 and immediately initiate corrective action to return the required RHR loop to operation.

c. With a valve or mechanical joint used to isolate unborated water sources not secured in the closed position, immediately suspend all operations that would cause introduction into the RCS of coolant with boron concentration less than required to meet SHUTDOWN MARGIN specified in the Core Operating Limits Report (COLR) and initiate action to secure the valve(s) or joint(s) in the closed position and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> verify the SHUTDOWN MARGIN is within limits specified in the COLR. The required action to verify the SHUTDOWN MARGIN within limits must be completed whenever ACTION c is entered. A separate ACTION entry is allowed for each unsecured valve or mechanical joint.

SURVEILLANCE REQUIREMENTS 4.4.1.4.2.1 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at a frequency in accordance with the Surveillance Frequency Control Program.

4.4.1.4.2.2 Each valve or mechanical joint used to isolate unborated water sources shall be verified closed and secured in position at a frequency in accordance with the Surveillance Frequency Control Program.

• Two RHR loops may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other RHR loop is OPERABLE and in operation.

• • The RHR pump may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided: (1) no operations are permitted that would cause introduction into the RCS of coolant with boron concentration less than that required to meet SHUTDOWN MARGIN of LCO 3.1.1, and (2) core outlet temperature is maintained at least 10°F below saturation temperature.

SOUTH TEXAS - UNITS 1 & 2 3/4 4-6 Unit 1 - Amendment No. 128, 149, 175, 187 188 Unit 2 - Amendment No. 117, 137, 163, 174 175

ML21106A286 *via e-mail OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA* NRR/DORL/LPL4/BC*

NAME DGalvin PBlechman JDixon-Herrity DATE 04/20/2021 04/20/2021 05/06/2021 OFFICE NRR/DORL/LPL4/PM*

NAME DGalvin DATE 05/06/2021