|
---|
Category:Letter
MONTHYEARIR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20243012023-05-15015 May 2023 Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves IR 05000400/20220052022-08-24024 August 2022 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2022005) IR 05000400/20224032022-08-23023 August 2022 Security Baseline Inspection Report 05000400/2022403 ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 IR 05000400/20220022022-08-0505 August 2022 Integrated Inspection Report 05000400/2022002 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation IR 05000400/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000400 2022011 IR 05000400/20224022022-06-30030 June 2022 Material Control and Accounting Program Inspection Report 05000400/2022402 (OUO Removed) IR 05000400/20220102022-06-13013 June 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000400/2022010 ML22138A4012022-05-26026 May 2022 Project Manager Reassignment ML22101A2822022-05-0606 May 2022 Regulatory Audit Summary Related to the Review of License Amendment Regarding Revising the Flood Hazard Protection Scheme IR 05000400/20220012022-05-0404 May 2022 Integrated Inspection Report 05000400/2022001 IR 05000400/20224012022-03-24024 March 2022 Security Baseline Inspection Report 05000400/2022401 ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 IR 05000400/20210062022-03-0202 March 2022 Annual Assessment Letter for Shearon Harris Nuclear Power Plant (Report No. 05000400/2021006) ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency IR 05000400/20210042022-02-0404 February 2022 Integrated Inspection Report 05000400/2021004 ML22034A5352022-02-0202 February 2022 Notification of Licensed Operator Initial Examination 05000400/2022301 2024-01-30
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 25, 2019 Mr. David B. Hamilton Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - CORRECTION TO AMENDMENT NO. 168 TO FACILITY OPERATING LICENSE CONCERNING CHANGES TO PRESSURE AND TEMPERATURE CURVES
Dear Mr. Hamilton:
On June 12, 2015, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 168 to Facility Operating License No. NPF-58 for Perry Nuclear Power Plant, Unit No. 1 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15141A482).
On January 15, 2019, the NRC staff identified an error on Technical Specification (TS) pages 3.4.-31, 3.4-31a, and 3.4-31b issued with Amendment No. 168. Specifically, on each pressure and temperature figure (Figures 3.4.11-1(a), 3.4.11-1(b), and 3.4.11-1(c)), the note box regarding the heatup/cooldown rate specified the rate as a temperature per hour. However, the license amendment request, dated June 23, 2014, specified the heatup/cooldown rate as a temperature limit "in any one hour period."
The NRC staff concludes that the error was inadvertently introduced during the preparation of the license amendment and is editorial in nature. The correction does not change any of the conclusions in the safety evaluation associated with the amendment and does not affect the associated notice to the public. Enclosed, please find the corrected replacement TS pages.
Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Corrected TS pages cc w/encl: ListServ
ENCLOSURE PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET 50-440 FACILITY OPERATING LICENSE NO. NPF-58 CORRECTED PAGES TO LICENSE AMENDMENT NO. 168 Technical Specification pages 3.4-31, 3.4-31 a, and 3.4-31 b
RCS P/T LIMITS 3.4.11 F, 1400 PSIG I
~145.0 186.3 F, 1400 PSIG~
1400 . HEATUP/COOLDOWN RATE I
I I MAXIMUM IS 20 DEGREES FIN ANY 6
( I) I J
ONE HOUR PERIOD Q..
1200 I
I I
C I
<[
LL.I I 70 F, 1110 PSIG I
- c I Q..
0 I-1000 I
I MINIMUM METAL I
I TEMPERATURE AT GIVE N LLI TOP HEAD PRESSURE:
(I) I (I)
LL.I I ~UPPER VESSEL &
> 800 . BEL TUNE CURVE a: I I ***BOTTOM HEAD CURV E 0
~
I- I u
<[ I 100.0 F, 740.3 PSIGI LL.I I a: 600 I
z LLI a:
I I
I
- J (I) 400 :
(I)
LLI I a: I70 F, 312.5 PSIG 1
100.0 F, 312.5 PSIG I Q..
200 IFLANGEI REGION I
A70 F, 0 PSIG I 0 * - - -- - -
H4.7l 20 40 60
~+-~--
\80 100 120 140 160 170 F, (-14.7> PSIGI REACTOR VESSEL METAL TEMPERATURE <DEGREES F>
FIGURE 3.4.11-tca>: PRESSURE TEST CURVES CVALID UP TO 32 EFPY>
PERRY - UNIT 1 3.4-31 Amendment No.168
RCS P/T LIMITS 3.4.11 173.3 F, 1400 PSIG 104.8 F, 1400 PSIG 1400 HEATUP/COOLOOWN RATE MAXIMUM IS a
( I)
- ,I 100 DEGREES FIN ANY ONE HOUR PERIOD C
D..
<[
1200 I
I I
I.LI I
- c I D..
0 1000 1- I MINIMUM METAL TEMPERATURE AT GIVEN
...J I TOP HEAD PRESSURE:
I.LI I (I) ~UPPER VESSEL &
(I) I I.LI I BEL TLINE CURVE
> 800 * --BOTTOM HEAD CURVE a:
0 t-u
<[
I.LI 0:: 600-------+-------+----+---+-------l z
I.LI a:
130.0 F, 548.2 PSIG
~ 400 106.0 F, 312.5 PSIG I.LI a: 130.0 F, 312.5 PSIG D..
FLANGE 200 - - - - - - + - - - - - - - + - - REGION - - + - - - - - - i 70 F, 116.4 PSIG 0
(-14.7)--....---r---r---,---+--,-~--r---r---+----,----,----,----,---!--,--,----r---.---l 50 100 150 200 PSIG REACTOR VESSEL METAL TEMPERATURE <DEGREES F>
FIGURE 3.4.11-Hb>: NON-NUCLEAR HEATUP/COOLDOWN CURVES <VALID UP TO 32 EFPY>
PERRY - UNIT 1 3.4-31e Amendment. No. 168
RCS P/T LIMITS 3.4.11
!144.8 F, 1400 PSIG~ 213.3 F, 1400 PSIG 1400 I
I HEATUP/COOLDOWN RATE I
6
( I)
~ 1200 I I
I
- MAXIMUM IS 100 DEGREES FIN ANY ONE HOUR PERIOD C
<[
I' LIJ I
- c I Q. I 1000
....0 I
...J MINIMUM METAL I TEMPERATURE AT GIVEN LIJ (I) I TOP HEAD PRESSURE:
(I) I LIJ ---UPPER VESSEL &
> 800 BEL TUNE CURVE a: ***BOTTOM HEAD CURVE
....u0 I
<[ I LIJ I a: 600 I
....z I 170.0 F, 548.3 PSIG LIJ a:
(I)
(I) 400 LIJ a: 146.0 F, 312.5 PSIG 170.0 F, 312.5 PSIG Q.
I 200 FLANGE1~~~~-
REGI0N F,0PSIG 0
(-14.7)+-..--,-~-,---l--,----\--,--..--ii---r-,--,--,.---+--,--,--,,..........-+--,--..--,---.---l 50 100 150 200 250 70 F, -14.7 PSIG REACTOR VESSEL METAL TEMPERATURE <DEGREES F>
FIGURE 3.4.11-l<c>: CORE CRITICAL OPERATION CURVES <VALID UP TO 32 EFPY>
PERRY - UNIT 1 3.4-31b Amendment No. 168
ML19016A008 OFFICE NRR/D0RL/LPL3/PM NRR/D0RL/LPL3/LA NRR/D0RL/LPL3/BC NRR/DORL/LPL3/PM NAME KGreen SRohrer DWrona KGreen DATE 01/16/19 01/16/19 02/22/19 02/25/19