ML15243A153: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(5 intermediate revisions by the same user not shown)
Line 2: Line 2:
| number = ML15243A153
| number = ML15243A153
| issue date = 09/02/2015
| issue date = 09/02/2015
| title = Perry Nuclear Power Plant, Unit 1 - Correction of Typographical Error Incurred During Prior License Amendment No. 162
| title = Correction of Typographical Error Incurred During Prior License Amendment No. 162
| author name = Green K J
| author name = Green K
| author affiliation = NRC/NRR/DORL/LPLIII-1
| author affiliation = NRC/NRR/DORL/LPLIII-1
| addressee name = Harkness E J
| addressee name = Harkness E
| addressee affiliation = FirstEnergy Nuclear Operating Co
| addressee affiliation = FirstEnergy Nuclear Operating Co
| docket = 05000440
| docket = 05000440
| license number = NPF-058
| license number = NPF-058
| contact person = Green K J
| contact person = Green K
| document type = Letter, Technical Specifications
| document type = Letter, Technical Specifications
| page count = 5
| page count = 5
| project =
| stage = Other
}}
}}


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Ernest J. Harkness Site Vice President September 2, 2015 FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 2, 2015 Mr. Ernest J. Harkness Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097


==SUBJECT:==
==SUBJECT:==
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 -CORRECTION OF TYPOGRAPHICAL ERROR INCURRED DURING PRIOR LICENSE AMENDMENT NO. 162  
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - CORRECTION OF TYPOGRAPHICAL ERROR INCURRED DURING PRIOR LICENSE AMENDMENT NO. 162


==Dear Mr. Harkness:==
==Dear Mr. Harkness:==


By letter dated March 3, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13052A706), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 162 to Facility Operating License No. NPF-58 for Perry Nuclear Power Plant, Unit No. 1. The amendment revised surveillance requirements (SRs) in technical specification (TS) 3.8.1, "AC Sources -Operating," by excluding Division 3 from current mode restrictions.
By letter dated March 3, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13052A706), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 162 to Facility Operating License No. NPF-58 for Perry Nuclear Power Plant, Unit No. 1. The amendment revised surveillance requirements (SRs) in technical specification (TS) 3.8.1, "AC Sources - Operating," by excluding Division 3 from current mode restrictions.
During its review of a separate amendment request to adopt Technical Specifications Task Force (TSTF)-425, "Relocate Surveillance Frequencies to Licensee Control -RITSTF Initiative 5b," the NRC staff identified an error in SR 3.8.1.10 that was inadvertently introduced during the issuance of Amendment No. 162. Specifically, the Note in SR 3.8.1.10 should have read, "This Surveillance shall not be performed in MODE 1 or 2 (not applicable to Division 3). However, credit may be taken for unplanned events that satisfy this SR." The term "DG" was inadvertently added to the parenthetical " ... (not applicable to Division 3 DG) ... " during the issuance of the amendment.
During its review of a separate amendment request to adopt Technical Specifications Task Force (TSTF)-425, "Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b," the NRC staff identified an error in SR 3.8.1.10 that was inadvertently introduced during the issuance of Amendment No. 162. Specifically, the Note in SR 3.8.1.10 should have read, "This Surveillance shall not be performed in MODE 1 or 2 (not applicable to Division 3). However, credit may be taken for unplanned events that satisfy this SR." The term "DG" was inadvertently added to the parenthetical " ... (not applicable to Division 3 DG) ... " during the issuance of the amendment.
The purpose of this letter is to issue a correction to TS Page 3.8-8 to reflect the correct wording originally requested by FirstEnergy Nuclear Operating Company in its license amendment request dated July 3, 2012 (ADAMS Accession No. ML 12188A001).
The purpose of this letter is to issue a correction to TS Page 3.8-8 to reflect the correct wording originally requested by FirstEnergy Nuclear Operating Company in its license amendment request dated July 3, 2012 (ADAMS Accession No. ML12188A001). Enclosed please find corrected TS Page 3.8-8 for Amendment No. 162 to Facility Operating License NPF-58 for Perry Nuclear Power Plant, Unit No. 1.
Enclosed please find corrected TS Page 3.8-8 for Amendment No. 162 to Facility Operating License NPF-58 for Perry Nuclear Power Plant, Unit No. 1. The NRC staff has determined that the error was introduced during the preparation of the license amendment and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the safety evaluation associated with Amendment No. 162 and does not affect the associated notice to the public.
The NRC staff has determined that the error was introduced during the preparation of the license amendment and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the safety evaluation associated with Amendment No. 162 and does not affect the associated notice to the public.
E. Harkness If you have any questions regarding this matter, please contact me at (301) 415-1627.
 
Docket No. 50-440  
E. Harkness                                   If you have any questions regarding this matter, please contact me at (301) 415-1627.
Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440


==Enclosure:==
==Enclosure:==


Corrected TS Page 3.8-8 issued with Amendment No. 162 cc w/encl: Distribution via Listserv Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ENCLOSURE PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 CORRECTED PAGE TO LICENSE AMENDMENT NO. 162 FACILITY OPERATING LICENSE NO. NPF-58 TECHNICAL SPECIFICATION PAGE 3.8-8 AC Sources-Operating
Corrected TS Page 3.8-8 issued with Amendment No. 162 cc w/encl: Distribution via Listserv


====3.8.1 SURVEILLANCE====
ENCLOSURE PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 CORRECTED PAGE TO LICENSE AMENDMENT NO. 162 FACILITY OPERATING LICENSE NO. NPF-58 TECHNICAL SPECIFICATION PAGE 3.8-8


REQUIREMENTS (continued)
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SR 3.8.1. 9 SURVEILLANCE
SURVEILLANCE                              FREQUENCY SR 3.8.1. 9   -------------~---NOTES--------------------
: 1. This Surveillance shall not be performed in MODE 1 or 2 (not applicable to Division 3). However. credit may be taken for unplanned events that satisfy this SR. 2. If performed with DG synchronized with offsite power. it shall be performed at a power factor 0.9. FREQUENCY Verify each DG rejects a load greater *than 24 months or equal to its associated single largest post-accident load.
: 1. This Surveillance shall not be performed in MODE 1 or 2 (not applicable to Division 3). However.
load rejection.
credit may be taken for unplanned events that satisfy this SR.
engine speed is maintained less than nominal plus 75% of the difference between nomi-na 1 speed and the overspeed trip setpoint.
: 2. If performed with DG synchronized with offsite power. it shall be performed at a power factor ~ 0.9.
or 15% above nominal. whichever is less. SR 3.8.1.10 This Surveillance shall not be performed in MODE*l or 2 (not applicable to Division 3). However. credit may be taken for unplanned events that satisfy this SR. Verify each DG operating at a power factor 24 months 0.9 does not trip and voltage is maintained 4784 V for Division 1 and 2 OGs and 5000 V for Division 3 OG during and following a load rejection of a load 5600 kW for Division 1 and 2 DGs and 2600 kW for Division 3 DG. (continued)
Verify each DG rejects a load greater *than     24 months or equal to its associated single largest post-accident load. Followin~ load rejection. engine speed is maintained less than nominal plus 75% of the difference between nomi-na 1 speed and the overspeed trip setpoint. or 15% above nominal.
PERRY -UN IT 1 3.8-8 Amendment No. 162 E. Harkness If you have any questions regarding this matter, please contact me at (301) 415-1627.
whichever is less.
Docket No. 50-440
SR 3.8.1.10   -----------------NOTE---------------------
 
This Surveillance shall not be performed in MODE*l or 2 (not applicable to Division 3).
==Enclosure:==
However. credit may be taken for unplanned events that satisfy this SR.
Verify each DG operating at a power factor     24 months
                ~  0.9 does not trip and voltage is maintained ~ 4784 V for Division 1 and 2 OGs and ~ 5000 V for Division 3 OG during and following a load rejection of a load
                ~ 5600 kW for Division 1 and 2 DGs and
                ~ 2600 kW for Division 3 DG.
(continued)
PERRY - UN IT 1                       3.8-8                 Amendment No.     162 Corrected by letter dated September 2, 2015


Corrected TS Page 3.8-8 issued with Amendment No. 162 cc w/encl: Distribution via Listserv DISTRIBUTION:
ML15243A153 OFFICE DORL/LPL3-1 /PM           DORL/LPL3-1 /LA     DORL/LPL3-1 /BC     DORL/LPL3-1/PM NAME           KGreen             MHenderson             DPelton             KGreen DATE         9/02/2015           9/01/2015           9/02/2015           9/02/2015}}
PUBLIC LPL3-1 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorllpl3-1 Resource Sincerely, IRA/ Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrPMPerry Resource RidsNrrLAMHenderson Resource RidsRgn3MailCenter Resource RecordsAmend Resource ADAMS Accession No.: ML15243A153 OFFICE DORL/LPL3-1  
/PM DORL/LPL3-1  
/LA DORL/LPL3-1  
/BC DORL/LPL3-1/PM NAME KGreen MHenderson DPelton KGreen DATE 9/02/2015 9/01/2015 9/02/2015 9/02/2015 OFFICIAL RECORD COPY}}

Latest revision as of 07:11, 31 October 2019

Correction of Typographical Error Incurred During Prior License Amendment No. 162
ML15243A153
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 09/02/2015
From: Kimberly Green
Plant Licensing Branch III
To: Harkness E
FirstEnergy Nuclear Operating Co
Green K
References
Download: ML15243A153 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 2, 2015 Mr. Ernest J. Harkness 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 OF TYPOGRAPHICAL ERROR INCURRED DURING PRIOR LICENSE AMENDMENT NO. 162

Dear Mr. Harkness:

By letter dated March 3, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13052A706), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 162 to Facility Operating License No. NPF-58 for Perry Nuclear Power Plant, Unit No. 1. The amendment revised surveillance requirements (SRs) in technical specification (TS) 3.8.1, "AC Sources - Operating," by excluding Division 3 from current mode restrictions.

During its review of a separate amendment request to adopt Technical Specifications Task Force (TSTF)-425, "Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b," the NRC staff identified an error in SR 3.8.1.10 that was inadvertently introduced during the issuance of Amendment No. 162. Specifically, the Note in SR 3.8.1.10 should have read, "This Surveillance shall not be performed in MODE 1 or 2 (not applicable to Division 3). However, credit may be taken for unplanned events that satisfy this SR." The term "DG" was inadvertently added to the parenthetical " ... (not applicable to Division 3 DG) ... " during the issuance of the amendment.

The purpose of this letter is to issue a correction to TS Page 3.8-8 to reflect the correct wording originally requested by FirstEnergy Nuclear Operating Company in its license amendment request dated July 3, 2012 (ADAMS Accession No. ML12188A001). Enclosed please find corrected TS Page 3.8-8 for Amendment No. 162 to Facility Operating License NPF-58 for Perry Nuclear Power Plant, Unit No. 1.

The NRC staff has determined that the error was introduced during the preparation of the license amendment and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the safety evaluation associated with Amendment No. 162 and does not affect the associated notice to the public.

E. Harkness If you have any questions regarding this matter, please contact me at (301) 415-1627.

Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440

Enclosure:

Corrected TS Page 3.8-8 issued with Amendment No. 162 cc w/encl: Distribution via Listserv

ENCLOSURE PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 CORRECTED PAGE TO LICENSE AMENDMENT NO. 162 FACILITY OPERATING LICENSE NO. NPF-58 TECHNICAL SPECIFICATION PAGE 3.8-8

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1. 9 -------------~---NOTES--------------------

1. This Surveillance shall not be performed in MODE 1 or 2 (not applicable to Division 3). However.

credit may be taken for unplanned events that satisfy this SR.

2. If performed with DG synchronized with offsite power. it shall be performed at a power factor ~ 0.9.

Verify each DG rejects a load greater *than 24 months or equal to its associated single largest post-accident load. Followin~ load rejection. engine speed is maintained less than nominal plus 75% of the difference between nomi-na 1 speed and the overspeed trip setpoint. or 15% above nominal.

whichever is less.

SR 3.8.1.10 -----------------NOTE---------------------

This Surveillance shall not be performed in MODE*l or 2 (not applicable to Division 3).

However. credit may be taken for unplanned events that satisfy this SR.

Verify each DG operating at a power factor 24 months

~ 0.9 does not trip and voltage is maintained ~ 4784 V for Division 1 and 2 OGs and ~ 5000 V for Division 3 OG during and following a load rejection of a load

~ 5600 kW for Division 1 and 2 DGs and

~ 2600 kW for Division 3 DG.

(continued)

PERRY - UN IT 1 3.8-8 Amendment No. 162 Corrected by letter dated September 2, 2015

ML15243A153 OFFICE DORL/LPL3-1 /PM DORL/LPL3-1 /LA DORL/LPL3-1 /BC DORL/LPL3-1/PM NAME KGreen MHenderson DPelton KGreen DATE 9/02/2015 9/01/2015 9/02/2015 9/02/2015

Retrieved from "https://kanterella.com/w/index.php?title=ML15243A153&oldid=2029529"