ML13136A143

Nucelar Power Plant, Unit 1 - Re-Issuance of Amendment Regarding Adoption of TSTF-275 and TSTF-300

ML13136A143
Person / Time
Site:	Perry
Issue date:	05/16/2013
From:	Blake Purnell Plant Licensing Branch III
To:	Kaminskas V FirstEnergy Nuclear Operating Co
Purnell B NRR/DORL/LPL3-2
References
TAC ME9521
Download: ML13136A143 (11)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 16, 2013 Mr. Vito A. Kaminskas Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A290 P.O. Box 97,10 Center Road Perry,OH 44081-0097 SUB,JECT: PERRY NUCLEAR POWER PLANT, UNIT NO.1 - RE-ISSUANCE OF AMENDMENT REGARDING ADOPTION OF TSTF-275, "CLARIFY REQUIREMENT FOR EDG START SIGNAL ON RPV LEVEL - LOW, LOW, LOW DURING RPV CAVITY FLOOD-UP," AND TSTF-300, "ELIMINATE DG LOCA-START SRs WHILE IN SID WHEN NO ECCS IS REQUIRED" (TAC NO.

ME9521)

Dear Mr. Kaminskas:

By letter1 dated May 6, 2013, the U.S. Nuclear Regulatory Commission (NRC) issued the subject amendment to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit NO.1. However, this amendment was incorrectly numbered as Amendment No. 163 when it should have been numbered as Amendment No. 164.

With this letter, we are re-issuing this amendment as Amendment No. 164. Enclosed are the corrected amendment and TS pages. This change is administrative in nature and does not change the NRC staff's conclusions. A copy of the NRC staffs safety evaluation was provided with the May 6, 2013, letter. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440

Enclosure:

Amendment No. 164 to NPF-58 cc w/encl: Listserv 1 Agencywide Documents Access and Management System Accession No. ML130518144

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION, LLC.

OHIO EDISON COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. NPF-58

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for license filed by FirstEnergy Nuclear Operating Company, et al. (the licensee, FENOC), dated September 5, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 164 are hereby incorporated into the license.

FENOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeremy S. Bowen, Acting Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating License Date of Issuance: May 16, 2013

ATTACHMENT TO LICENSE AMENDMENT NO. 164 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Facility Operating License Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert Page 4 Page 4 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3.3-39 3.3-39 3.3-40 3.3-40 3.3-41 3.3-41 3.3-42 3.3-42 3.8-20 3.8-20

4 renewal. Such sale and leaseback transactions are subject to the representations and conditions set forth in the above mentioned application of January 23, 1987, as supplemented on March 3, 1987, as well as the letter of the Director of the Office of Nuclear Reactor Regulation dated March 16, 1987, consenting to such transactions. Specifically, a lessor and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over the licenses of PNPP Unit 1. For purposes of this condition the limitations of 10 CFR 50.81, as now in effect and as may be subsequently amended, are fully applicable to the lessor and any successor in interest to that lessor as long as the license for PNPP Unit 1 remains in effect; these financial transactions shall have no effect on the license for the Perry Nuclear facility throughout the term of the license.

(b) Further, the licensees are also required to notify the NRC in writing prior to any change in: (i) the terms or conditions of any lease agreements executed as part of these transactions; (ii) the PNPP Operating Agreement; (iii) the existing property insurance coverage for PNPP Unit 1; and (iv) any action by a lessor or others that may have an adverse effect on the safe operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now and hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level FENOC is authorized to operate the facility at reactor core power levels not in excess of 3758 megawatts thermal (100% power) in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 164, are hereby incorporated into the license. FENOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Antitrust Conditions

a. FirstEnergy Nuclear Generation, LLC and Ohio Edison Company Amendment No. 164

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

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

1. low Pressure CooLant Injection-A (LPCI) and low Pressure Core Spray (LPCS)

Subsystems

a. Reactor Vessel Water 1,2,3, 2(b) B SR 3.3.5.1.1 ;;:: 14.3 inches Level - Low Low Low, SR 3.3.5.1.2 Level 1 4(a)(f) , SR 3.3.5.1.3 SR 3.3.5.1.5 5(a)(f) SR 3.3.5.1.6

b. Drywell Pressure . High 1,2,3 2(b) B SR 3.3.5.1.1 :s: 1.88 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

c. LPCI PU!!IP A 1,2,3, C SR 3.3.5.1.2 ~ 5.25 Start - TIme Delay SR 3.3.5.1.4 seconds Relay 4(a) ,5(a) SR 3.3.5.1.6

d. Reactor Vessel 1,2,3 C SR 3.3.5.1.1 :<!! 482.7 psig Pressure - Low (LPCS SR 3.3.5.1.2 and .

Injection Valve SR 3.3.5.1.3 ~ 607.7 psig Perm; ss i ve) SR 3.3.5.1.5 SR 3.3.5.1.6 4(a),5(a) B SR 3.3.5.1.1 :<!! 482.7 psig SR 3.3.5.1.2 and SR 3.3.5.1.3 :s: 607.7 psig SR 3.3.5.1.5 SR 3.3.5.1.6

e. Reactor Vessel 1,2,3 C SR 3.3.5.1.1 :!: 490.0 psig Pressure-Low (LPCI SR 3.3.5.1.2 and Injection Valve SR 3.3.5.1.3 :s: 537.1 psig Permissive) SR 3.3.5.1.5 SR 3.3.5.1.6 4(a), 5(a) B SR 3.3.5.1.1 :?; 490.0 psig SR 3.3.5.1.2 and SR 3.3.5.1.3 SR 3.3.5.1.5 ~537.1 psig SR 3.3.5.1.6

f. lPCS Pump Dischar~e 1,2,3, E SR 3.3.5.1.1 :!: 1200 gpm Flow - low (Bypass SR 3.3.5.1.2 4(a),5(a) SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 (continued)

(a) When associated ECCS subsystem(s) are required to be OPERABLE per lCO 3.5.2, ECCS-Shutdown.

(b) Also required to initiate the associated diesel generator and AEGT subsystem.

Cf) When associated AEGT subsystems are required to be OPERABLE per LCO 3.6.4.3, Annulus Exhaust Gas Treatment (AEGT) System.

PERRY UNIT 1 3.3-39 Amendment No. 164

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 1 Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core spray (LPCS)

Subsystems (continued)

g. LPCI Pump A Discharge 1,2,3, E SR 3.3.5.1.1 :<': 1450 gpm Flow - Low (Bypass) SR 3.3.5.1.2 4(a) ,5(a) SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

h. Manual Initiation 1,2,3, C SR 3.3.5.1.6 NA 4(a),5(a)

2. LPCI B and LPCI C Subsystems

a. Reactor Vessel Water ',2,3, 2(b} B SR 3.3.5.1.1 <:: 14.3 inches Level - Low Low LOW, SR 3.3.5.1.2 Level 1 4(a)(f) SR 3.3.5.1.3 5(a)(f}' SR 3.3.5.1.5 SR 3.3.5.1.6

b. Drywell Pressure - High 1,2,3 2(b) B SR 3.3.5.1.1 :$; 1.88 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

c. LPCI Pump B Start- 1,2,3, C SR 3.3.5.1.2  :$; 5.25 Time Delay Relay SR 3.3.5.1.4 seconds 4(a),5(a} SR 3.3.5.1.6

d. Reactor Vessel 1,2,3 1 per C SR 3.3.5.1.1 :?; 490.0 psig Pressure - Low (LPCI subsystem SR 3.3.5.1.2 and Injection Valve SR 3.3.5.1.3 :!': 537.1 psig Permissive) SR 3.3.5.1.5 for LPCI B; SR 3.3.5.1.6 and

<!: 490.0 psig and S 537.1 ~sig for LPC C 4(a) ,sea} 1 per B SR 3.3.5.1.1 ~ 490.0 psig subsystem SR 3.3.5.1.2 and SR 3.3.5.1.3 :$;537.1 psig SR 3.3.5.1.5 for LPCI B; SR 3.3.5.1.6 and

<!: 490.0 psig and

s: 537.1 rig for LPC C (continued)

(a) When associated ECCS subsystem(s} are required to be OPERABLE per LCO 3.5.2, ECCS-Shutdown.

(b) Also required to initiate the associated diesel generator and AEGT subsystem.

(1) When associated AEGT subsystems are required to be OPERABLE per LCO 3.6.4.3, Annulus Exhaust Gas Treatment (AEGT) System.

PERRY - UNIT 1 3.3-40 Amendment No. 164

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

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECI FlED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACT ION A.1 REQUIREMENTS VALUE

2. LPCI B and LPCI C Subsystems (continued)

e. LPCI Pump B 1,2,3, 1 per pump E SR 3.3.5.1.1 ~ 1450 gpm and LPCI Pump C SR 3.3.5.1.2 Discharge 4(a),5(a} SR 3.3.5.1.3 Flow - Low SR 3.3.5.1.5 (Bypass) SR 3.3.5.1.6

f. Manual Initiation 1,2,3, C SR 3.3.5.1.6 NA 4(a),5(a}

3. High Pressure Core Spray (HPCS) System

a. Reactor Vessel 1,2,3, 4(e) B SR 3.3.5.1.1 ~ 127.6 inches Water LeveL - Low SR 3.3.5.1.2 Low, Level 2 4(a),5(a} SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

b. DryweL L 1,2,3 4(e) B SR 3.3.5.1.1 :s; 1.88 psig Pressure - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

c. Reactor Vessel 1,2,3, 4 B SR 3.3.5.1.1 :s; 221.7 inches Water SR 3.3.5.1.2 LeveL - High, 4(a),5(a) SR 3.3.5.1.3 Level 8 SR 3.3.5.1.5 SR 3.3.5.1.6

d. Condensate 1,2,3, 2 0 SR 3.3.5.1.1 ~ 90,300 gallons Storage Tanl< SR 3.3.5.1.2 LeveL - Low 4(c),5(c) SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

e. Suppression Pool 1,2,3 2 0 SR 3.3.5.1.1 ~ 18 ft 6 inches Water Level - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.6 (continued)

(a) When associated ECCS subsystem(s) are required to be OPERABLE per LCD 3.5.2, ECCS-Shutdown.

(c) When HPes is OPERABLE for compl iance with LCO 3.5.2~ "ECCS - Shutdown," and aL igned to the condensate storage tank while tanl< water level is not within t e limits of SR 3.5.2.2.

(e) Also required to initiate the associated diesel generator.

PERRY - UNIT 1 3.3-41 Amendment No. 164

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE AUOIJABlE FUNCTION CONDIT IONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

3. High Pressure Core Spray (HPCS) System (continued)

f. HPCSPump 1,2,3, E SR 3.3.5.1.1 :1: 120 psig Discharge SR 3.3.5.1.2 Pressure* High 4(a),5(a) SR 3.3.5.1.3 (Bypass) SR 3.3.5.1.5 SR 3.3.5.1.6

g. HPCS srstem Flow 1,2,3, E SR 3.3.5.1.1 :1: 600 gpm Rate ow SR 3.3.5.1.2 (Bypass) 4(a),5(a) SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

h. ManuaL Initiation 1,2,3, C SR 3.3.5.1.6 NA 4(a) ,5(a)

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel 1,2(d) ,3(d) 2 F SR 3.3.5.1.1  ;;:: 14.3 inches Water level - Low SR 3.3.5.1.2 low Low, level 1 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

b. ADS Initiation 1,2(d),3(d) G SR 3.3.5.1.2 :1: 100.5 seconds Timer SR 3.3.5.1.4 and SR 3.3.5.1.6  :>: 109.5 seconds

c. Reactor Vessel 1,2(d) ,3(d) SR 3.3.5.1.1 ~ 177.1 inches Water level, Low, SR 3.3.5.1.2 level 3 SR 3.3.5.1.3 (Confirmatory) SR 3.3.5.1.5 SR 3.3.5.1.6

d. lPCS Pump 1,Z(d) ,3(d) 2 G SR 3.3.5.1.1 ~ 125 psig Discharge SR 3.3.5.1.2 Pressure* High SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

e. lPCI Pump A 1,2(d) ,3 Cd ) 2 G SR 3.3.5.1.1 ~ 115 psig Discharge SR 3.3.5.1.2 Pressure - High SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

f. Manual Initiation 1,2(d) ,3(d) 2 G SR 3.3.5.1.6 NA (continued)

(a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS*Shutdown.

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

PERRY UNIT 1 3.3-42 Amendment No. 164

AC Sources-Shutdown 3.8.2 SURVEILLANCE REMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 ------- --NOTES--- ------- -- --

1. The fo 11 owi ng SRs are not requ'j red to be performed: SR 3.8.1.3, SR 3.8.1.B through SR 3.B.1.16, SR 3.B.1.1B, and SR 3. B.1. 19 .

2. SR 3.B.1.12 and SR 3.B.1.19 are not required to be met when the associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2. "ECCS Shutdown."

In accordance For AC sources required to be OPERABLE. the with applicable following SRs are applicable: SRs SR 3.B.1.1 SR 3.B.1. 7 SR 3.B.1.14 SR 3.B.1.2 SR 3.B.1. 9 SR 3.B.1.15 SR 3.B.1.3 SR 3.B.1.10 SR 3.B.1.16 SR 3.B.1.4 SR 3.B.1.11 SR 3.B.1.1B SR 3.B.1.5 SR 3.B.1.12 SR 3.B.l.19 SR 3.B.1.6 SR 3.B.1.13 PERRY - UNIT 1 3.B-20 Amendment No. 164

May 16, 2013 Mr. Vito A. Kaminskas Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY -A290 P.O. Box 97, 10 Center Road Perry,OH 44081-0097

SUBJECT:

PERRY NUCLEAR POWER PLANT, UNIT NO.1 - RE-ISSUANCE OF AMENDMENT REGARDING ADOPTION OF TSTF-275, "CLARIFY REQUIREMENT FOR EDG START SIGNAL ON RPV LEVEL - LOW, LOW, LOW DURING RPV CAVITY FLOOD-UP," AND TSTF-300, "ELIMINATE DG LOCA-START SRs WHILE IN SID WHEN NO ECCS IS REQUIRED" (TAC NO.

ME9521)

Dear Mr. Kaminskas:

By lette~ dated May 6, 2013, the U.S. Nuclear Regulatory Commission (NRC) issued the subject amendment to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit NO.1. However, this amendment was incorrectly numbered as Amendment No. 163 when it should have been numbered as Amendment No. 164.

With this letter, we are re-issuing this amendment as Amendment No. 164. Enclosed are the corrected amendment and TS pages. This change is administrative in nature and does not change the NRC staff's conclusions. A copy of the NRC staffs safety evaluation was provided with the May 6, 2013, letter. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, IRA!

Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440

Enclosure:

Amendment No. 164 to NPF-58 cc w/encl: Listserv DISTRIBUTION:

PUBLIC LPL3-2 RlF RidsAcrsAcnw_MailCTR Resource RidsNrrDeEeeb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl3-2 Resource RidsNrrDraApla Resource RidsNrrDssSrxb Resource RidsNrrDssStsb Resource RidsNrrLASRohrer Resource RidsNrrPMPerry Resource RidsRgn3MailCenter Resource ADAMS Accession No.: ML13136A143 OFFICE NRR/DORULPL3-2/PM NRR/DORULPL3-2/LA NRR/DORULPL3-2/BC NRRlDORULPL3-2/PM NAME BPumell SRohrer JBowen BPumell DATE 05/16/13 05/16/13 05/16/13 05/16/13 OFFICIAL RECORD COpy 2 Agencywide Documents Access and Management System Accession No. ML13051B144