ML21166A366
| ML21166A366 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/17/2021 |
| From: | Justin Poole Plant Licensing Branch 1 |
| To: | Rhoades D Exelon Generation Co, Exelon Nuclear |
| Poole J | |
| References | |
| EPID L-2021-LLA-0110 | |
| Download: ML21166A366 (11) | |
Text
June 17, 2021 Mr. David P. Rhoades 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 342 ISSUED JUNE 14, 2021, RE: ONE TIME EXTENSION TO TECHNICAL SPECIFICATIONS 3.5.1, 3.6.1.9, AND 3.6.4.1 COMPLETION TIMES TO SUPPORT RESIDUAL HEAT REMOVAL PUMP MOTOR REPLACEMENT (EMERGENCY CIRCUMSTANCES) (EPID L-2021-LLA-0110)
Dear Mr. Rhoades:
By "JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid. (RHR) Pump Motor Replacement|letter dated June 14, 2021]], the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 342 to Renewed Facility Operating License No. DPR-59 for the James A.
FitzPatrick Nuclear Power Plant. The amendment was in response to your application dated June 12, 2021, as supplemented by two letters dated June 13, 2021, and a "JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid. (RHR) Pump Motor Replacement|letter dated June 14, 2021]], which superseded all previous letters. The amendment modifies TS 3.5.1, ECCS
[Emergency Core Cooling System] - Operating Condition A, TS 3.6.4.1, Secondary Containment, Condition A, and TS 3.6.1.9 RHR [Residual Heat Removal] Containment Spray System, as well as certain Surveillance Requirements (SR) to support emergent repair of the A residual heat removal pump motor.
Subsequent to issuance of the amendment, the licensee informed the NRC that in its creation of the clean technical specification pages, administrative errors were introduced. All the errors were in different sections than those changed by the license amendment. On page 3.5.1-3, condition H.1 was erroneously changed to B.1. On page 3.5.1-4, in SR 3.5.1.3, the and were erroneously changed to < and >, respectively. On page 3.3.6.1-5, in SR 3.3.6.1.8 an O was erroneously removed from INSTRUMENTATION. On pages 3.5.3-2 and 3.6.1.3-8, continued was erroneously removed from the bottom of the table. On page 3.5.1-1, the vertically lines of the table erroneously extended beyond the bottom of the table. On page 3.8.5-2, the dashed lines for the note associated with SR 3.8.5.1 were erroneously changed to solid lines. The attached TS pages correct these unintended changes. These corrections do not change any of the conclusions in the safety evaluation associated with the issuance of the amendment.
If you have any questions, please contact me at 301-415-2048 or Justin.Poole@nrc.gov.
Sincerely,
/RA/
Justin C. Poole, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
Corrected TS pages cc: Listserv
ENCLOSURE JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORRECTED TS PAGES FOR AMENDMENT NO. 342
Primary Containment Isolation Instrumentation 3.3.6.1 JAFNPP 3.3.6.1-5 Amendment 342 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.6.1.4 Calibrate the trip units.
In accordance with the Surveillance Frequency Control Program*
SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Program*
SR 3.3.6.1.6 Calibrate the radiation detectors.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.8
- - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - -
n equals 2 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
Verify the ISOLATION INSTRUMENTATION RESPONSE TIME is within limits.
In accordance with the Surveillance Frequency Control Program
- This Surveillance for ISP-150B is not required to be performed for functions 4.a, 4.b, 4.d, 4.e and 4.f of table 3.3.6.1-1 until following the return of the A RHR pump to OPERABLE.
This past due Surveillance will be completed as stated in Section 3.5 of letter JAFP-21-0053, dated June 14, 2021.
ECCS - Operating 3.5.1 JAFNPP 3.5.1-1 Amendment 342 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
APPLICABILITY:
MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
ACTIONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
LCO 3.0.4.b is not applicable to HPCI.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One low pressure ECCS injection/spray subsystem inoperable.
OR One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.
A.1 Restore low pressure ECCS injection/spray subsystem(s) to OPERABLE status.
7 days*
B.
Required Action and associated Completion Time of Condition A not met.
B.1 Be in MODE 3.
AND B.2 Be in Mode 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours (continued)
- The Completion Time to return the A RHR pump to OPERALE is extended to 34 days, contingent on implementation of Compensatory Actions stated in Section 3.4 of letter JAFP-21-0053, dated June 14, 2021, as a one-time only change ending upon restoration the A RHR pump to OPERABLE, or on July 11, 2021 at 20:00 hours.
ECCS - Operating 3.5.1 JAFNPP 3.5.1-3 Amendment 342 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME G.
Required Action and associated Completion Time of Condition C, D, E, or F not met.
OR Two or more required ADS valves inoperable.
G.1 Be in Mode 3.
AND G.2 Reduce reactor steam dome pressure to 150 psig.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours H.
Two or more low pressure ECCS injection/spray subsystems inoperable for reasons other than Condition A.
OR HPCI System and one or more required ADS valves inoperable.
H.1 Enter LCO 3.0.3.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.
In accordance with the Surveillance Frequency Control Program*
(continued)
- This Surveillance for ST-4B is not required to be performed until following the return of the A RHR pump to OPERABLE. This past due Surveillance will be completed as stated in Section 3.5 of letter JAFP-21-0053, dated June 14, 2021.
ECCS - Operating 3.5.1 JAFNPP 3.5.1-4 Amendment 342 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.2 Verify each ECCS injection/spray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program*
SR 3.5.1.3 Verify ADS pneumatic supply header pressure is 95 psig.
In accordance with the Surveillance Frequency Control Program SR 3.5.1.4 Verify the RHR System cross tie valves are closed and power is removed from the electrical valve operator.
In accordance with the Surveillance Frequency Control Program SR 3.5.1.5 Cycle open and closed each LPCI motor operated valve independent power supply battery charger AC input breaker and verify each LPCI inverter output voltage is 576 V and 624 V while supplying the respective bus.
In accordance with the Surveillance Frequency Control Program (continued)
- This Surveillance for ST-4B is not required to be performed until following the return of the A RHR pump to OPERABLE. This past due Surveillance will be completed as stated in Section 3.5 of letter JAFP-21-0053, dated June 14, 2021.
RCIC SYSTEM 3.5.3 JAFNPP 3.5.3-2 Amendment 342 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled with water from the pump discharge valve to the injection valve.
In accordance with the Surveillance Frequency Control Program*
SR 3.5.3.2 Verify each RCIC System manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program*
- - - - - - - - - - - - - - - - - - - - - - - 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, with reactor pressure 1040 psig and 970 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.
In accordance with the Surveillance Frequency Control Program*
- - - - - - - - - - - - - - - - - - - - - - - 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, with reactor pressure 165 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.
In accordance with the Surveillance Frequency Control Program*
(continued)
- This Surveillance for ST-24J is not required to be performed until following the return of the A RHR pump to OPERABLE. This past due Surveillance will be completed as stated in Section 3.5 letter JAFP-21-0053, dated June 14, 2021.
PCIVs 3.6.1.3 JAFNPP 3.6.1.3-8 Amendment 342 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.3
- - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - -
- 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
- 2. Not required to be met for PCIVs that are open under administrative controls.
Verify each primary containment manual isolation valve and blind flange that is located inside primary containment and not locked, sealed or otherwise secured and is required to be closed during accident conditions is closed.
Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) shear isolation valve explosive charge.
In accordance with the Surveillance Frequency Control Program SR 3.6.1.3.5 Verify the isolation time of each power operated, automatic PCIV, except for MSIVs, is within limits.
In accordance with the Inservice Testing Program*
SR 3.6.1.3.6 Verify the isolation time of each MSIV is 3 seconds and 5 seconds.
In accordance with the Inservice Testing Program (continued)
- This Surveillance for ST-24J is not required to be performed until following the return of the A RHR pump to OPERABLE. This past due Surveillance will be completed as stated in Section 3.5 of letter JAFP-21-0053, dated June 14, 2021.
DC Sources - Shutdown 3.8.5 JAFNPP 3.8.5-2 Amendment 342 ACTIONS CONDITIONS REQUIRED ACTION COMPLETION TIME A. (continued)
A.2.3 Initiate action to restore required DC electrical power subsystem to OPERABLE status.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1
- - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - -
The following SRs are not required to be performed: SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.
For DC electrical power subsystem required to be OPERABLE the following SRs are applicable:
SR 3.8.4.1, SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.
In accordance with applicable SRs*
- This Surveillance for MST-071.12 is not required to be performed following the return of the A RHR pump to OPERABLE. This past due Surveillance will be completed as stated in Section 3.5 of letter JAFP-21-0053, dated June 14, 2021.
ML21166A366 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LAiT NRR/DORL/LPL3/LA NAME JPoole KZeleznock JBurkhardt (KGoldstein for)
DATE 06/17/2021 06/17/2021 06/17/2021 OFFICE NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME JDanna JPoole DATE 06/17/2021 06/17/2021