ML19052A008

Correction to Technical Specifications Page 3.3-45 (Unit 1) and Page 3.6-11 (Unit 2) for Administrative Errors Introduced During the Issuance of Amendment Nos. 271 and 253

ML19052A008
Person / Time
Site:	Susquehanna
Issue date:	03/05/2019
From:	Jennifer Tobin Plant Licensing Branch 1
To:	Cimorelli K Susquehanna
Tobin J, NRR/DORL/LPL1
References
Download: ML19052A008 (7)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 5, 2019 Mr. Kevin Cimorelli Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2-CORRECTION TO TECHNICAL SPECIFICATIONS PAGE 3.3-45 (UNIT 1) AND PAGE 3.6-11 (UNIT 2) FOR ADMINISTRATIVE ERRORS INTRODUCED IN THE ISSUANCE OF AMENDMENT NOS. 271 AND 253

Dear Mr. Cimorelli:

On September 26, 2018 (Agencywide Documents Access and Management System Package Accession No. ML18222A203), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 271 and 253 to Renewed Facility Operating License Nos. NPF-14 and NPF-22 for the Susquehanna Steam Electric Station (Susquehanna), Units 1 and 2, respectively. The amendments revised the Susquehanna Technical Specifications (TSs) to adopt the NRG-approved Technical Specifications Task Force Traveler (TSTF)-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control."

Subsequent to the issuance of these amendments, the licensee notified the NRC by telephone on February 13, 2019, that administrative errors were made on Susquehanna, Unit 1, TS page 3.3-45, and Unit 2, TS page 3.6-11, as follows:

• For Unit 1, TS page 3.3-45, Amendment No. 254 was added to the bottom right of the page in the list of stricken amendment numbers. Number 254 should not have been added and is now removed in the attached corrected page.

• For Unit 2, TS page 3.6-11, a separating line between paragraphs D. and E. was omitted and is now added in the attached corrected page.

The NRC staff has determined that these errors were made inadvertently. The corrections do not change any of the conclusions associated with the issuance of Amendment Nos. 271 and 253, and do not affect the associated notice to the public. The inadvertent changes were neither addressed in the notice for the amendments nor reviewed as part of the license amendment request.

K. Cimorelli If you have any questions regarding this matter, I may be reached at 301-415-2328 or Jennifer.Tobin@nrc.gov.

Sincerely,

JJAIWH-;Jo(r,;f()

Jennifer C. Tobin, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Corrected Unit 1 TS page 3.3-45

2. Corrected Unit 2 TS page 3.6-11 cc: Listserv

ENCLOSURE 1 Corrected Unit 1 TS page 3.3-45 for Amendment No. 271 issued September 26, 2018 Susquehanna Steam Electric Station, Unit 1

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODESOR REFERENCED OTtER REQUIRED FROM SPECFIED CHANNELS PER REQUl~ED SURVEILLANCE ALLONASLE FUNCTION CONDITIONS FUNCTION ACTIONA1 REQUIREMENTS VALUE

3. HPCISystem (continued)

e. Manual Initiation 1, C SR 3.3.5.1.5 NA 21'°. 3(ff/

4. Automatic Depressurtzation System (ADS) Trip SystemA

a. Reactor Vessel 1, 2 E SR 3.3.5.1.1 2! -136 inches Waler L.evei-low 2(ffj,3(d) SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.U SR 3.3.5.1.5

b. Drywell Pressure- 1, 2 E SR 3.3.5.1.2 s 1.88 psig High 2°* Jldl SR 3.3.5.1.3 SR 3.3.5.1.5 C. Automatic 1. 1 .F SR 3.3.5.1.2 s 114 seconds Depressunzation 21d), 3(d) SR 3.3.5.1.3 System Initiation SR 3.3.5.1.5 Tlmer

d. Reactor Vessel 1, 1 E SR 3.3.5.1.1 .? 11.5 inr.hes Water Level-low, 2°. 3Cdl SR 3.3.5.1.2 Level3 SR 3.3.5.1.4 (ConllnnatOI)') SR 3.3.5.1.5

e. Core Spr8'f P\mp 1. 2 F SR 3.3.5.1.2 2! 125psig Discharge id), 3(d) SR 3.3.5.1.3 and Pressure-High SR 3.3.5.1.5 s 165 psig (continued)

(d) VI.4th reactor steam dome pressure> 150 pslg.

SUSQUEHANNA - UNIT 1 3.3-45 Amendment 1-3, ~ . 271

ENCLOSURE 2 Corrected Unit 2 TS page 3.6-11 for Amendment No. 253 issued September 26, 2018 Susquehanna Steam Electric Station, Unit 2

PCIVs 3.6.1.3 ACTIONS CONDITION

• REQUIRED ACTION COMPLETION TIME D. -------~~--NOTE---~-------~ D.1 Isolate the affected 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Only applicable to the H202 penetration flow path by Analyzer penetrations. the use of at least one

---

closed and de-activated One or more H2 02 automatic valve, closed Analyzer penetrations with manual valve or blind one or two PCIVs flange.

inoperable. AND D.2 Verify the affected Once per 31 days penetration flow path is isolated.

E. Secondary containment E.1 Restore leakage rate to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> bypass leakage rate within limit.

not within limit.

F. One or more penetration F.1 Restore the valve leakage 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> flow paths with one or more to within valve leakage containment purge valves limit.

not within purge valve leakage limit.

G. Required Action and G.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A, B, C, AND D, E, or F not met.

G.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SUSQUEHANNA - UNIT 2 3.6-11 Amendment 484, 4-7-Q, 253

ML19052A008 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DORL/LPL 1/BC NRR/DORL/LPL 1/PM NAME JTobin LRonewicz JDanna JTobin DATE 02/26/2019 02/25/2019 03/05/2019 03/05/2019