Letter Sequence Supplement |
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MONTHYEARML0326510472003-09-11011 September 2003
Supplement to License Amendment Request No. 306 for Revision to Technical Specifications Regarding DC Electrical Power Sources Based on TSTF-360
Project stage: Supplement
ML0329405542003-10-21021 October 2003
Draft RAI for Discussion
Project stage: Draft RAI
ML0405704792004-02-25025 February 2004
Draft RAI on Proposed Amendment to Use TSTF-360
Project stage: Draft RAI
ML0408400322004-03-24024 March 2004
Request for Additional Information, Proposed Amendment Concerning Electrical Power Sources
Project stage: RAI
ML0411302652004-03-29029 March 2004
License Amendment Request No. 306
Project stage: Request
ML0409702322004-03-31031 March 2004
Supplement to License Amendment Request No. 306, DC Electrical Power Sources Based on TSTF-360
Project stage: Supplement
ML0411304162004-04-16016 April 2004
Supplement to Oyster Creek License Amendment Request No. 306-DC Electrical Power Sources Based on TSTF-360
Project stage: Supplement
ML0419804762004-07-30030 July 2004
License Amendment, Revised the Technical Specifications, Sections 3.7 and 4.7, Auxiliary Electrical Power, and Added a New Section 6.8.5, Station Battery Monitoring and Maintenance Program
Project stage: Acceptance Review
ML0421904482004-08-12012 August 2004
Letter, Correction of Amendment No. 245 Re.: Electrical Power Sources
Project stage: Other
ML0429505442004-10-15015 October 2004
Correction of Amendment No. 245 to Technical Specification Pages Electrical Power Sources
Project stage: Other
ML0428900822004-10-15015 October 2004
Correction of Amendment No. 245 Electrical Power Sources
Project stage: Other
2004-03-24
[Table View] |
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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML21075A3372021-03-16016 March 2021
License Amendment Request to Revise Oyster Creek Nuclear Generating Station Permanently Defueled Technical Specificat Ions to Reflect Perm Anent Removal of Spent Fuel from Spent Fuel Pool
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License Amendment Request to Approve Independent Spent Fuel Storage Installation Only Emergency Plan
RA-18-080, License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements2018-11-12012 November 2018
License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements
RA-18-098, License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-11-0606 November 2018
License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme
RA-18-092, License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-10-22022 October 2018
License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme
RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2017-11-16016 November 2017
License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RA-17-055, License Amendment Request to Implement BWRVIP-18, Revision 2-A2017-08-30030 August 2017
License Amendment Request to Implement BWRVIP-18, Revision 2-A
RA-17-049, License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2017-08-29029 August 2017
License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme
ML17100A8442017-04-10010 April 2017
License Amendment Request Regarding Revision to Cyber Security Plan Milestone 8 Completion Date
RA-17-012, License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Condition2017-02-28028 February 2017
License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Condition
NMP1L3095, License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-032016-08-0101 August 2016
License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03
RA-16-021, License Amendment Request for Proposed Changes to Technical Specifications Section 6.0 Administrative Controls for Permanently Defueled Condition2016-05-17017 May 2016
License Amendment Request for Proposed Changes to Technical Specifications Section 6.0 Administrative Controls for Permanently Defueled Condition
RA-14-057, License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 82014-08-29029 August 2014
License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8
ML14164A0542014-05-30030 May 2014
License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.
NEI 99-01, License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2014-05-30030 May 2014
License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.
RA-14-032, License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2014-05-30030 May 2014
License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.
RA-14-046, Request for Amendment to Revise Oyster Creek Nuclear Generating Station Under Snubber Surveillance Requirements2014-04-30030 April 2014
Request for Amendment to Revise Oyster Creek Nuclear Generating Station Under Snubber Surveillance Requirements
RA-13-101, License Amendment Request Related to Building Vital Area Access Control2013-12-19019 December 2013
License Amendment Request Related to Building Vital Area Access Control
RA-13-077, Company License Amendment Request to Revise the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel2013-10-30030 October 2013
Company License Amendment Request to Revise the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel
RS-13-070, Application to Revise Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs2013-08-0202 August 2013
Application to Revise Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs
RA-10-027, Technical Specification Change Request No. 356, Elimination of Daily Testing of an Operable Emergency Diesel Generator (EDG) When the Other EDG Is Declared Inoperable2010-06-25025 June 2010
Technical Specification Change Request No. 356, Elimination of Daily Testing of an Operable Emergency Diesel Generator (EDG) When the Other EDG Is Declared Inoperable
RA-10-050, Technical Specification Change Request No. 340, Proposed Revision to Appendix B Environmental Technical Specifications of the Facility Operating License2010-06-11011 June 2010
Technical Specification Change Request No. 340, Proposed Revision to Appendix B Environmental Technical Specifications of the Facility Operating License
RA-10-009, Oyster Creek, License Amendment Request, Changes to Trunnion Room Secondary Containment Boundary2010-02-25025 February 2010
Oyster Creek, License Amendment Request, Changes to Trunnion Room Secondary Containment Boundary
ML1006200112010-02-25025 February 2010
Oyster Creek, License Amendment Request, Changes to Trunnion Room Secondary Containment Boundary
ML0932802342009-11-23023 November 2009
Request for Approval of the Exelon Cyber Security Plan
RA-09-065, Application for Technical Specifications Change Regarding Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (Adoption of TSTF-425, Rev 3)2009-10-30030 October 2009
Application for Technical Specifications Change Regarding Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (Adoption of TSTF-425, Rev 3)
RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I2008-06-0909 June 2008
Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item Im
RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008
Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.
RA-08-004, Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)2008-03-10010 March 2008
Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)
RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008
Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications
ML0732400402007-11-13013 November 2007
Technical Specification Request No. 336 and Three Mile Island Technical Specification Change Request No. 330 Deletion of Technical Specification Requirements for Review and Audit, and Additional Administrative Changes
RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators2007-07-19019 July 2007
Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators
RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-12012 April 2007
Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
ML0633201962006-11-27027 November 2006
Technical Specification Change Request No. 341 - Revision to Required Submittal Date for Annual Radioactive Effluent Release Report
ML0615703332006-06-0202 June 2006
2006/06/02-Oyster Creek Generating Station, Supplemental Information Related to Oyster Creek Generating Station License Renewal Application
ML0615103502006-05-25025 May 2006
Technical Specification Change Request No. 328 - Response to Request for Additional Information Concerning a Revision to Surveillance Requirements for Testing of Main Steam Line Electromatic Relief Valve
ML0534302552005-12-0202 December 2005
License Amendment Request Increase Safety Valve As-Found Setpoint Tolerance from 1% to 3%
ML0534302562005-12-0202 December 2005
GE-NE-0000-0046-3343-NP, Rev 1, Oyster Creek, License Amendment Request Increase Safety Valve As-Found Setpoint Tolerance from 1% to 3%, Attachment 5
ML0529701902005-10-18018 October 2005
Technical Specification Change Request No. 328 - Modify Surveillance Requirements for Testing of Main Steam Line Electromatic Relief Valves
ML0607902732005-09-0808 September 2005
2005/09/08-Oyster Creek License Renewal Scoping and Screening Procedures ((Form CD-Rom) (PA)
ML0530504772005-07-22022 July 2005
Oyster Creek - Application for Renewed Operating License No. DPR-16
ML0520800482005-07-22022 July 2005
Oyster Creek Generating Station, Application for Renewed Operating License
ML0513704932005-05-10010 May 2005
Oyster Creek Generating Station, Submittal of Changes to Technical Specifications Bases
ML0509402342005-03-28028 March 2005
License Amendment Request No. 315 - Application of Alternative Source Term
ML0508705402005-03-25025 March 2005
Technical Specification Change Request No. 332 - Upgrade of 69 Kv Offsite Power Transmission Line
RS-05-024, Application for Approval of Indirect License Transfers2005-03-0303 March 2005
Application for Approval of Indirect License Transfers
RS-05-006, Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License2005-02-25025 February 2005
Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License
ML0505900852005-02-24024 February 2005
Technical Specification Change Request No. 319 - Revision to Table 3.1.1 Notes Aa and Bb Regarding Reactor Building Closed Cooling Water Pump and Service Water Pump Trip Conditions
RS-04-157, Proposed Revision to Appendix B, Environmental Protection Plan (Non-Radiological) of the Facility Operating License2004-12-17017 December 2004
Proposed Revision to Appendix B, Environmental Protection Plan (Non-Radiological) of the Facility Operating License
RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004
Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program
2021-03-16
[Table view] |
Text
Arnren SM AmerGen Energy Company, LLC www.exeloncorp.com An Exelon Company 200 Exelon Way Kennett Square, PA 19348 10 CFR 50.90 2130-04-20089 CPril 16, 2004 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Oyster Creek Generating Station Facility Operating License No. DPR-16 Docket No. 50-219 Supplement to Oyster Creek License Amendment Request No. 306 - DC Electrical Power Sources Based on TSTF-360 (T^A- MB8481).
References:
- 1. AmerGen Letter No.2130-03a-20058, dated April 21, 2003, License Amendment Request No. 303 - DC Electrica' Power Sources Based cn TSTF-360 (TAC No. MB8481').
- 2. Technical Specification Task Force (TSTF) T-aveler-360, "DC Electric.'l Rewrite", Revision 1.
"his letter is being sent to supplement License Amendmeint Roquest (LAR) No. 3K& to modify Technical Specification (TS) requirements for direct current (DC) sources through revision of Specifications 3.7 and 4.7, and addition of new Specification 6.8.5 (Reference 1). The Reference 1 LAR proposed TS requirements that are consistent, except for format. with the requirements of Specifications 3.8.4, 3.8.6 and 5.5.14 described in NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWR/4", Revision 2, which are based on the NRC approved industry/Technical Specification Task Force (TSTF) change TSTF-360, Revision l (Reference 2). This supplemental letter provides information regarding an editorial error that was recently identified related to the surveillance requirements (SR) foathe Diesel Generator starting batteries.
In Reference 1, AmerGen Energy Company, LLC, proposed reformatting TS 4.7.B to separate the SRs for the Diesel Generator starting batteries and the SRs for station batteries 'B' and 'C'.
This proposed reformatting of TS 4.7.B was editorial in nature and no change was proposed to the Diesel Generator starting battery SRs. Subsequent review of Reference 1 determined that the SR to perform weekly monitoring of the Diesel Generator starting battery pilot cell voltage was omitted from the proposed TS 4.7.B. A revised TS page 4.7--, which includes the SR for Diesel Generator starting battery pilot cell voltage is provided in Enclosure 1. This change corrects an oversight and has no impact on the technical analysis cr the No Significant Hazards Consideration Determination submitted in the Reference 1 letter.
poO
U. S. Nuclear Regulatory Commission April 16, 2004 Page 2 Additionally, Reference 1, submitted to the NRC on April 21, 2003, included a change to TS page 3.7-2. Subsequent to the Reference 1 submittal, NRC issued Amendment 239, which also revised TS page 3.7-2. The revised TS page 3.7-2 from Amendment 239, with the changes proposed in Reference 1, is attached to this letter. contains the marked-up TS pages 3.7-2 and 4.7-1, which supersede the same TS pages submitted with the Reference 1 LAR. Enclosure 2 contains the retyped proposed TS pages 3.7-2 and 4.7-1, which supersede the typed proposed TS pages 3.7-2 and 4.7-1 submitted with the Reference 1 LAR.
There are no additional regulatory commitments contained in this letter.
We are notifying the State of New Jersey of this supplement to the application for changes to the Technical Specifications by transmitting a copy of this letter and its attachment to the designated State Official.
If any additional information is needed, please contact Dave Robillard at (610) 765-5952.
I declare under penalty of perjury that the foregoing is true and correct.
Sincerely, Executed On Michael P. Gallagher Director, Licensing & Regulatory Affairs AmerGen Energy Company, LLC
Enclosures:
(1) Oyster Creek Technical Specification Change Request No. 306, Corrected Mark-up of Proposed Technical Specification Pages (2) Oyster Creek Technical Specification Change Request No. 306, Retyped Technical Specification Pages cc: H. J. Miller, Administrator, USNRC Region 1 P. S. Tam, USNRC Senior Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No. 03042
ENCLOSURE 1 Oyster Creek License Amendment Request No. 306 Corrected Mark-up of Proposed Technical Specification Pages TS PAGES 3.7-2 4.7-1
not to exceed 7 days if a startup transformer is out of service. None of the engineered safety feature equipment fed by the remaining transformer may be out of service.
- 2. The reactor may remain in operation for a period not to exceed 7 days if 125 VDC Motor Control Center DC-2 is out of service, provided the requirements of Specification 3.8 are met.
tandby Diesel Generators
- 1. The reactor shall not be made critical unless both diesel generators are operable and capable of feeding their designated 4160 volt buses.
- 2. If one diesel generator becomes inoperable during power operation, repairs shall be initiated immediately and the other diesel shall be operated at least one hour every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at greater than 80% rated load until repairs are completed. The reactor may remain in operation for a period not to exceed 7 days if a diesel generator is out of service. During the repair period none of the engineered safety features normally fed by the operational diesel generator may be out of service or the reactor shall be placed in the cold shutdown condition. If a diesel is made inoperable for biennial inspection, the testing and engineered safety feature requirements described above must be met.
- 3. If both diesel generators become inoperable during power operation, the reactor shall be placed in the cold shutdown condition.
- 4. For the diesel generators to be considered operable:
A) There shall be a minimum of 14,000 gallons of diesel fuel in the standby diesel generator fuel tank, OR B) To facilitate inspection, repair, or replacement of equipment which would require full or partial draining of the standby diesel generator fuel tank, the following conditions must be met:
- 1) There shall be a minimum of 14,000 gallons of fuel oil contained in temporary tanker trucks, connected and aligned to the diesel generator fill station.
OYSTER CREEK 3.7-2 Amendment No.: 11, 55, 99, 149, 118, 107, 239
4.7 AUXILIARY ELECTRICAL POWER Applicability: Applies to surveillance requirements of the auxiliary electrical supply.
Objective: To verify the availability of the auxiliary electrical supply.
Spec~fication:
A. Diesel Generator
- 1. Each diesel generator shall be started and loaded to not less than 80% rated load every two weeks.
- 2. The two diesel generators shall be automatically actuated and functionally tested during each refueling outage. This shall include testing of the diesel generator load sequence timers listed in Table 3.1.1.
- 3. Deleted.
- 4. The diesel generators' fuel supply shall be checked following the above tests.
- 5. The diesel generators' starting batteries shall be tested and monitored per Specification 4.7.B.
B. on eried Diesel Generator Starting Batteries
- 1. RWeekly surveillance will be performed to verify the following:
s A i a. The active metallic surface of the plates shall be fully covered with
___________ electrolyte in all batteries.
___________ he designated Sot cell voltage is Seater than or equal t 2.09 volts for 7 Station Battery and 2.0 volts for tation Battery C whi the respective battery is one float charge.
/AV The-overall battery voltage is greater than or equal to
~S~l ete < _ w h il29V1t 2wie the i /
battery is on a float charge.,(isiat [ i _
Hi)3 A The pilot cell specific gravity, corrected to 770 F, is greater than or equal to 1.190.
Ala
< ~~ Z ac ~ o)Li ~ ~ -- -- -
OYSTER CREEK Amendment No.: 144,189,197,227, 236 CbpqI Cc,.rfeick 'I/1 6j,0
ENCLOSURE 2 Oyster Creek License Amendment Request No. 306 Retyped Technical Specification Pages TS PAGES 3.7-2 4.7-1
- 4. Station batteries B and C and an associated battery charger are OPERABLE.
Switchgear control power for 4160 volt bus 1D and 460 volt buses 1B2 and 1B3 is provided by 125 VDC Distribution Center DC-B. Switchgear control power for 4160 volt bus 1C and 460 volt buses 1A2 and 1A3 is provided by 125 VDC Distribution Center DC-C.
- 5. Bus tie breakers ED and EC are in the open position.
B. The reactor shall be PLACED IN the COLD SHUTDOWN CONDITION if the availability of power falls below that required by Specification A above, except that
- 1. The reactor may remain in operation for a period not to exceed 7 days if a startup transformer is out of service. None of the engineered safety feature equipment fed by the remaining transformer may be out of service.
- 2. The reactor may remain in operation for a period not to exceed 7 days if 125 VDC Motor Control Center DC-2 is out of service, provided the requirements of Specification 3.8 are met.
- 3. The reactor may remain in operation provided the requirements of Specification 3.7.D are met.
C. Standby Diesel Generators
- 1. The reactor shall not be made critical unless both diesel generators are operable and capable of feeding their designated 4160 volt buses.
- 2. If one diesel generator becomes inoperable during power operation, repairs shall be initiated immediately and the other diesel shall be operated at least one hour every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at greater than 80% rated load until repairs are completed. The reactor may remain in operation for a period not to exceed 7 days if a diesel generator is out of service. During the repair period none of the engineered safety features normally fed by the operational diesel generator may be out of service or the reactor shall be placed in the cold shutdown condition. If a diesel is made inoperable for biennial inspection, the testing and engineered safety feature requirements described above must be met.
- 3. If both diesel generators become inoperable during power operation, the reactor shall be placed in the cold shutdown condition.
- 4. For the diesel generators to be considered operable:
A) There shall be a minimum of 14,000 gallons of diesel fuel in the standby diesel generator fuel tank, OR B) To facilitate inspection, repair, or replacement of equipment which would require full or partial draining of the standby diesel generator fuel tank, the following conditions must be met:
- 1) There shall be a minimum of 14,000 gallons of fuel oil contained in temporary tanker trucks, connected and aligned to the diesel generator fill station.
OYSTER CREEK 3.7-2 Amendment No.: , 55, 99, 110, 18, 197, 239,
4.7 AUXILIARY ELECTRICAL POWER Applicability: Applies to surveillance requirements of the auxiliary electrical supply.
Obiective: To verify the availability of the auxiliary electrical supply.
Specification:
A. Diesel Generator
- 1. Each diesel generator shall be started and loaded to not less than 80% rated load every two weeks.
- 2. The two diesel generators shall be automatically actuated and functionally tested during each refueling outage. This shall include testing of the diesel generator load sequence timers listed in Table 3.1.1.
- 3. Deleted.
- 4. The diesel generators' fuel supply shall be checked following the above tests.
- 5. The diesel generators' starting batteries shall be tested and monitored per Specification 4.7.B.
B. Diesel Generator Starting Batteries
- 1. Weekly surveillance will be performed to verify the following:
- a. The active metallic surface of the plates shall be fully covered with electrolyte in all batteries.
- b. The designated pilot cell voltage is greater than or equal to 2.0 volts.
- c. The overall battery voltage is greater than or equal to 112 volts while the battery is on a float charge.
- d. The pilot cell specific gravity, corrected to 77 0F, is greater than or equal to 1.190.
- 2. Quarterly surveillance will be performed to verify the specific gravity for each fourth cell is greater than or equal to 1.190 when corrected to 770F. The specific gravity and electrolyte temperature of every fourth cell shall be recorded for surveillance review.
- 3. Annual surveillance will be performed to verify the specific gravity for each cell is greater than or equal to 1.190 when corrected to 77 0F. The electrolyte temperature and specific gravity for every cell shall be recorded for surveillance review.
OYSTER CREEK 4.7-1 Amendment No.: 111,189,197, 227, 236,