ML18324A685

Correction to Amendment No. 321 Revising Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control

ML18324A685
Person / Time
Site:	FitzPatrick
Issue date:	11/26/2018
From:	Booma Venkataraman Plant Licensing Branch 1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Venkataraman B, NRR/DORL/LPL1
References
EPID L-2017-PMP-0010
Download: ML18324A685 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 26, 2018 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - CORRECTION TO AMENDMENT NO. 321 REVISING TECHNICAL SPECIFICATIONS TO ADOPT TSTF-542, REVISION 2, "REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL" (EPID L-2017-PMP-0010)

Dear Mr. Hanson:

By letter dated August 24, 2018, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 321 to Renewed Facility Operating License No. DPR-59 for the James A.

FitzPatrick Nuclear Power Plant (FitzPatrick). The amendment was in response to your application dated October 2, 2017, 1 as supplemented by letters dated January 22, 2018, and April 19, 2018. 2 The amendment revised existing FitzPatrick Technical Specification (TS) requirements related to "operations with a potential for draining the reactor vessel," with new requirements on reactor pressure vessel water inventory control to protect the FitzPatrick TS Safety Limit 2.1.1.3, which stated, "Reactor vessel water level shall be greater than the top of active irradiated fuel."

Subsequent to issuance of the amendment, the NRC staff was notified by Exelon Generation Company, LLC (the licensee) of a typographical error that was introduced in its submission of revised TS pages 3.3.5.1-10 and 3.3.5.1-12 with the amendment request. The licensee's submittal stated the following for note (c) at the bottom of each of these two pages:

c. With reactor steam dose pressure > 150 psig.

1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML17275A520.

2 ADAMS Accession Nos. ML18022A829 and ML18109A371, respectively.

B. Hanson The word "dose" should have been "dome" in the licensee's revised TS pages 3.3.5.1-10 and 3.3.5.1-12 in its submittal. This error was inadvertently carried over by NRC staff to Amendment No. 321. The NRC staff has determined that this typographical error was made inadvertently and is entirely editorial in nature. This correction does not change any of the conclusions in the safety evaluation associated with the issuance of Amendment No. 321 and does not affect the associated notice to the public. Enclosed are the two replacement TS pages.

If you have any questions, please contact me at 301-415-2934 or Booma.Venkataraman@nrc.gov.

Sincerely,

~.~

Booma Venkataraman, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

Corrected pages 3.3.5.1-10 and 3.3.5.1-12 cc: Listserv

Enclosure Corrected pages 3.3.5.1-10 and 3.3.5.1-12

ECCS Instrumentation 3.3.5.l Table 3.3.5.1-1 (page 3 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR , REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTIONA.1 REQUIREMENTS VALUE

2. LPCI System (continued)

g. Low Pressure 1,2,3 1 per E SR 3.3.5.1.5 ~ 1040gpm Coolant Injection Pump subsystem SR 3.3.5.1.6 and Discharge Flow- Low s 1665 gpm (Bypass)

h. Containment 1, 2, 3 B SR 3.3.5.1.3 ~ 1 psig and Pressure - High SR 3.3.5.1.6 s 2.7 psig

3. High Pressure Coolant Injection (HPCI) System

a. Reactor Vessel Water 1, 4 B SR 3.3.5.1.1 ~ 126.5 Level - Low Low 2<*>, 3'*1 SR 3.3.5.1.2 inches (Level 2) SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6

b. Drywell 1, 4 B SR 3.3.5.1.1 s 2.7 psig Pressure - High 2<*1, 3'*) SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6

c. Reador Vessel Water 1, 2 C SR 3.3.5.1.1 s 222.5 Level - High (Level 8) :z<*>, 31,1 SR 3.3.5.1.2 inches SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6

d. Condensate Storage 1, 4 D SR 3.3.5.1.3 ~ 59.5 inches Tank Level - Low 2* 3 SR 3.3.5.1.6

e. Suppression Pool Water 1, 2 D SR 3.3.5.1.3 s 14.5 ft Level-High 2<*1, 3<*1 SR 3.3.5.1.6

f. High Pressure Coolant 1, E SR 3.3.5.1.5 ~ 475gpm Injection Pump 21' 1, 3"'1 SR 3.3.5.1.6 and Discharge Flow - Low s 800gpm (Bypass)

g. High Pressure Coolant 1, E SR 3.3.5.1.3 ~ 25 psig Injection Pump 2<*1, 3<*1 SR 3.3.5.1.6 and Discharge s 80 psig Pressure - High (Bypass)

(continued)

(c) With reactor steam dome pressure> 150 psig.

JAFNPP 3.3.5.1-10 Amendment 321

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTIONA.1 REQUIREMENTS VALUE

5. ADS Trip System B (continued)

C. Reactor Vessel Water 1, F SR 3.3.5.1.1 ~ 177 inches Level - Low (Level 3) 2M, 3<cl SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6

d. Core Spray Pump 1. 2 G SR 3.3.5.1.3 ~ 90 psig Discharge 2cc>, 3<c) SR 3.3.5.1.6 and Pressure - High s 110 psig

e. Low Pressure Coolant 1, 4 G SR 3.3.5.1.3 ~ 105pslg Injection Pump 2<*1, 3<c) SR 3.3.5.1.6 and Discharge s 145 psig Pressure - High (c) With reactor steam dome pressure> 150 psig.

JAFNPP 3.3.5.1-12 Amendment 321

ML18324A685 OFFICE NRR/DORULPL 1/PM NRR/DORULPL 1/LA NRR/DORULPL 1/BC NRR/DORULPL 1/PM NAME BVenkataraman LRonewicz JDanna BVenkataraman DATE 11/23/2018 11/23/2018 11/26/2018 11/26/2018