NMP2L2664, Supplemental Information No. 2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
| ML18012A361 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/12/2018 |
| From: | Jim Barstow Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMP2L2664 | |
| Download: ML18012A361 (7) | |
Text
Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www exeloncorp.com 10 CFR 50.90 NMP2L2664 January 12, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410
Subject:
Supplemental Information No.2 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control," Revision 2
References:
- 1. Letter from J. Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "License Amendment Request-Revise Technical Specifications to Adopt TSTF-542, 'Reactor Pressure Vessel Water Inventory Control,' Revision 2," dated February 28, 2017
- 2. Letter from M. Marshall (Senior Project Manager, U.S Nuclear Regulatory Commission) to Mr. 8. Hanson (Exelon Generation Company, LLC), "Nine Mile Point Nuclear Station, Unit 2-Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control (CAC No. MF9357}," dated October 10, 2017
- 3. Letter from J. Barstow (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control," dated November 3, 2017
- 4. Public Meeting Announcement, "Meeting with Technical Specifications Task Force (TSTF) RE: TSTF-542, 'Reactor Pressure Vessel Water Inventory Control,'" dated October 27, 2017
- 5. Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, "Reactor Pressure Vessel Water Inventory Control,"
Revision 2, dated December 27, 2017
Supplemental Information No.2 TSTF-542, Reactor Pressure Vessel Water Inventory Control Docket No. 50-41 O Page2 By letter dated February 28, 2017 (Reference 1 ), Exelon Generation Company, LLC (Exelon) requested to change the Nine Mile Point Nuclear Station, Unit 2 (NMP2) Technical Specifications (TS). The proposed amendment request would revise NMP2 TS by replacing the existing specifications related to Operations with a Potential for Draining the Reactor Vessel with revised requirements for Reactor Pressure Vessel Water Inventory Control to protect Safety Limit 2.1.1.3.
On October 10, 2017, the U.S. Nuclear Regulatory Commission (NRC) provided a Request for Additional Information (RAI) (Reference 2). On November 3, 2017, Exelon submitted to the NRC the RAI response (Reference 3).
On October 27, 2017, a public meeting was held by the NRC and the Boiling Water Reactor Owners Group (BWROG) to discuss a proposed TSTF-542 variation affecting BWR/5 and 6 plants. As noted in the NRC Public Meeting Announcement (Reference 4), the details of the proposed variation were provided in ADAMS Accession Number ML17289A902.
By letter dated December 27, 2017 (Reference 5), Exelon submitted supplemental information to address the proposed variation provided in ADAMS Accession Number ML17289A902. to this letter provides the proposed TS marked-up pages that clarifies specific information previously provided in References 1, 3, and 4. This supplement supersedes the markup TS page 3.3.5.2-2 from Reference 1. Also, this supplement supersedes TS markup page 3.3.5.2-4 provided in RAI responses to Questions RAl-3 and RAl-4 provided in Reference 3. Finally, this supplement superseded TS page 3.3.5.2-5 provided in Reference 5.
Exelon has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1. The supplemental information provided in this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. Furthermore, the supplemental information provided in this letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
With the supplemental information provided in Attachment 1 to this letter, Exelon requests approval of the proposed amendment by March 1, 2018. The requested approval date supports the implementation of TSTF-542 prior to the start of the refueling outage. Once approved, the amendment shall be implemented no later than the start of NMP2 2018 refueling outage.
There are no commitments contained in this response.
If you should have any questions regarding this submittal, please contact Ron Reynolds at 610-765-5247.
Supplemental Information No.2 TSTF-542, Reactor Pressure Vessel Water Inventory Control Page 3 Docket No. 50-410 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 12th day of January 2018.
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James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC : Proposed Technical Specification Marked-Up Pages cc:
USNRC Region I Regional Administrator USN RC Senior Resident Inspector - NMP USNRC Project Manager, NRR - NMP A L. Peterson, NYSERDA w/attachments II II II
ATTACHMENT 1 Supplemental Information No.2 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License NPF-69 Docket No. 50-410 PROPOSED TECHNICAL SPECIFICATION MARKED-UP PAGES TS Pages 3.3.5.2-2 3.3.5.2-4 3.3.5.2-5
Supplement No. 2 ACTIONS continued CONDITION D.
As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
RCIC Syster=RRPV Water Inventory Control Instrumentation 3.3.5.2 D.1 OR D.2 REQUIRED ACTION Declare HPCS system inoperable.
Align the HPCS pump suction to the suppression pool.
COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Delete per Supplement No. 2 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
~ As required by Required
- -+
Declare HPCS system inoperable.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action A.1 and referenced in Table 3.3.5.2 1.
As required by Required Action A.1 and referenced in Table 3.3.5.2-1.
Required Action and associated Completion Time of Condition C, D,,
._.....,........,,~
or F not met.
Restore channel to OPER/\\BLE status.
Restore channel to OPERABLE status.
Declare associated ECCS injection/spray subsystem inoperable.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours Immediately Revise per Supplement No. 2 Delete per Supplement No. 2 Revise per Supplement No. 2 NMP2 3.3.5.2-2 Amendment
Supplement No. 2 FUNCTION Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
Subsystems a
LPCS Differential Pressure-Low (Injection Permissive) b LPCI A Differential Pressure-Low (Injection Permissive) c LPCS Pump Discharge Flow-Low (Bypass) d LPCI Pump A Discharge Flow-low (Bypass) e Manual Initiation 2
LPCI Band C Differential Pressure-low (ln1ecllon Permissive) b LPCI Pump Band LPCI Pump c Discharge Flow-Low (Bypass) c Manual lniliat1on RCIC SystemRPV Water Inventory Control Instrumentation 3.3.5.2 Table 3 3 5 2* 1 (page 1 of 2)
RPV Waler Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 4, 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 REQUIRED CHANNELS PER FUNCTION 1 (a) l(a) 1 per pump (a) 1 per pump (a) 1 per subsystem CONDITIONS REFERENCED FROM REQUIRED ACTION A 1 c
c c
SURVEILLANCE REQUIREMENTS SR 3 3 5 21 SR 3 3 5 2 2 SR 3 3 5 21 SR 3 3 5 2 2 ALLOWABLE VALUE
- i
- 40 ps1d and s 98 ps1d
- i
- 70 ps1d and s 150 psid Revise per Supplement No. 2 SR 3 3 5 21 SR 3 3 5 2 2 c: 1000 gpm and s 1440 gpm
- i
- 770 gpm and s 930 gpm N/A
- i
- 70 ps1d and s 150 ps1d
- i
- 770 gpm and s 930 gpm NIA (continued)
(a)
Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Waler lnvenlory Control "
NMP2 3.3.5.2-4 Revise per Supplement No. 2 Amendment
Supplement No. 2 RCIC ~ystemRPV Water Inventory Control Instrumentation 3.3.5.2 FUNCTION 3
HPCS Pump Discharge Pressure-High Table 3 3 5 2*1 (page 2 of 2)
RPV Water Inventory Control Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 4, 5 CONDITIONS REFERENCED REQUIRED FROM CHANNELS PER REQUIRED FUNCTION ACTION A 1 Delete 1 per pump (a)
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
~
SR d.:U.2.2 IR6lles l!! 220 ps1g
~
(Bypass) (d)
HPCS System Flow 4 5 1 per pump
> 580gpm and (a)
(b)
(C)
(d) 4 5
NMP2 Rate-Low (Bypass) s 720gpm NIA Siiesystem Ea)
RHR System Isolation a
Reactor Vessel (c) 2 in one B
SR 3 3 5 2 1 l!! 157 8 inches Water Level-Low Tnp system SR 3 3 5 2 2 Level3 Reactor Water Cleanup (RWCU) System Isolation a
Reactor Vessel (c) 2 In one B
SR 3 3 5 2 1 l!! 101 8 mches Water Level-Low Tnp system SR 3 3 5 2 2 Low Level 2 Associated with an ECCS subsystem required lo be OPERABLE by LCO 3 5 2 'Reactor Pressure Vessel Water Inventory Control "
When HPCS is OPERABLE for compliance with LCO 3 5 2 "RPV Water Inventory Control." and ahgned to the condensate storage tank When automatic isolation of the associated penetration flow path(s) Is credited m calculating DRAIN TIME The Injection functions of Drywell Pressure
- High
~
not required to be OPERABLE with reactor steam dome pressur ess than 600 pslg,...-----.
Delete is Delete 3.3.5.2-5 Amendment