ML021280502
| ML021280502 | |
| Person / Time | |
|---|---|
| Site: | Cook  (DPR-058, DPR-074) |
| Issue date: | 05/30/2002 |
| From: | Stang J NRC/NRR/DLPM |
| To: | Bakken A Indiana Michigan Power Co |
| References | |
| TAC MB4760, TAC MB4761 | |
| Download: ML021280502 (16) | |
Text
May 30, 2002 Mr. A. Christopher Bakken III, Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS (TAC NOS. MB4760 AND MB4761)
Dear Mr. Bakken:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 269 to Facility Operating License No. DPR-58 and Amendment No. 250 to Facility Operating License No. DPR-74 for the Donald C. Cook Nuclear Plant, Units 1 and 2. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated April 9, 2002, as supplemented April 25, 2002. In your April 25, 2002, supplemental letter, you requested that the portion of the original application dealing with the Unit 2 AB and CD train batteries for Unit 2 only be processed on an emergency basis. By letter dated April 26, 2002, the NRC issued Amendment No. 249 for Unit 2.
The amendments revise the Surveillance Requirement (SR) for the Train AB, and CD batteries in TS 4.8.2.3.2.c.1 for Unit 1 and SR TS 4.8.2.5.2.c.1 for the N train batteries in both Units 1 and 2. The amendments modify the requirements to verify that battery cells, cell plates and racks show no visual indication of physical damage or abnormal deterioration. The amendments would allow the operability of batteries exhibiting damage or deterioration to be determined by an evaluation. The amendments are consistent with an NRC-approved change to the Standard Technical Specifications for Westinghouse plants (NUREG 1431, Revision 1) as documented in Technical Specification Task Force Standard Technical Specification Change Traveler-38.
A copy of our related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
John F. Stang, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Amendment No. 269 to DPR-58
- 2. Amendment No. 250 to DPR-74
- 3. Safety Evaluation cc w/encls: See next page
ML021280502 *Provided SE input by memo ** See previous concurrence OFFICE PM:PD3-1 LA:PD3-1 SC:RORP
- OGC**
SC:PD3-1 NAME JStang THarris RDenning RH0efling LRaghavan DATE 05/28/02 05/30/02 04 /25 /02 05 /24/02 05/29/02
Donald C. Cook Nuclear Plant, Units 1 and 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, MI 48913 Township Supervisor Lake Township Hall P.O. Box 818 Bridgman, MI 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, MI 49127 David W. Jenkins, Esquire Indiana Michigan Power Company One Cook Place Bridgman, MI 49106 Mayor, City of Bridgman P.O. Box 366 Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, MI 48909 Drinking Water and Radiological Project Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr. Blvd.
P. O. Box 30630, CPH Mailroom Lansing, MI 48909-8130 Scot A. Greenlee Director, Nuclear Technical Services Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495 Michael J. Finissi Plant Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Joseph E. Pollock Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 269 License No. DPR-58 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated April 9, 2002, as supplemented April 25, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
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. DPR-58 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 269, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 7 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 30, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 269 TO FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 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 3/4 8-13 3/4 8-13 3/4 8-17 3/4 8-17 B 3/4 8-2 B 3/4 8-2
INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 250 License No. DPR-74 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated April 9, 2002, as supplemented April 25, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
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. DPR-74 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 250, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 7 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 30, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 250 FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 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 3/4 8-17 3/4 8-17 B 3/4 8-2 B 3/4 8-2
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 269 TO FACILITY OPERATING LICENSE NO. DPR-58 AND AMENDMENT NO. 250 TO FACILITY OPERATING LICENSE NO. DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316
1.0 INTRODUCTION
By application dated April 9, 2002, as supplemented April 25, 2002, the Indiana Michigan Power Company (the licensee) requested amendments to the Technical Specifications (TSs) for the Donald C. Cook Nuclear Plant, Units 1 and 2. In your April 25, 2002, supplemental letter, you requested that the portion of the April 9, 2002, application dealing with the AB and CD train batteries for Unit 2 only be processed on an emergency basis. By letter dated April 26, 2002, the Nuclear Regulatory Commission (NRC) issued Amendment No. 249 for Unit 2.
The amendments revise the Surveillance Requirement (SR) for the Train AB, and CD batteries in TS 4.8.2.3.2.c.1 for Unit 1 and SR TS 4.8.2.5.2.c.1 for the N train batteries for both Units 1 and 2. The amendments modify the requirements to verify that battery cells, cell plates and racks show no visual indication of physical damage or abnormal deterioration. The amendments would allow the operability of batteries exhibiting damage or deterioration to be determined by an evaluation. The amendments are consistent with an NRC-approved change to the Standard Technical Specifications for Westinghouse plants (NUREG 1431, Revision 1) as documented in Technical Specification Task Force Standard Technical Specification Change Traveler-38.
2.0 BACKGROUND
The Train AB & CD batteries at D. C. Cook Units 1 and 2, supply 250-volt dc power for operation of turbine generator emergency auxiliaries, switchgear, annunciators, vital bus inverters, motor operated valves, and emergency lighting. The batteries are central power station type designed for continuous duty. The battery system for each unit consists of two separately located sets of 116 lead acid cells connected in series. Each cell is of the sealed type, assembled in a shock absorbing clear plastic container, with covers bonded in place to form a leakproof seal. The batteries are mounted on protected, corrosion resistant steel racks for security, and to facilitate maintenance. The Train AB & CD battery each has its own active normal charger and a wired standby charger.
In 1994, the licensee purchased 109 LCR-25 batteries cells (Shop Order No. 0111031-01) from C&D Technologies, Inc. These battery cells were installed in the Unit 2 AB battery system. In December 2001, the licensee began to see signs of degradation of these batteries. In April of 2002, the licensee discovered cracks in the battery cells top covers. The cracking did not impair the ability of the battery cells to perform their safety function. On April 4, 2002, the licensee requested, and was granted Enforcement Discretion in accordance with NRC Manual Chapter 9900 to allow additional time beyond the 2-hour limiting condition for operation (LCO) to replace 3 battery cells in the Unit 2 AB battery. The Enforcement Discretion precluded an unnecessary plant shutdown due to the existing TS being overly restrictive. Since April 4, 2002, on two separate occasions, the licensee has discovered cracks in the top cover of a battery cell in the Unit 2 AB battery. In both cases, the licensee replaced the battery cells with spare battery cells within the 2-hour LCO. Based on the trend of the battery degradation, the licensee considers that cracking on additional cells may be identified in the near future. This coupled with the limited LCO time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, prompted the licencee to request that the NRC process the Unit 2 AB battery portion of the amendment on an emergency basis.
3.0 REGULATORY EVALUATION
TSs 4.8.2.3.2.c.1 and 4.8.2.5.2.c.1 currently require verification at least once per 18 months that the Train AB CD and N battery cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration. The licensee is proposing a license amendment that would modify this SR, consistent with TSTF-38, to clarify that physical damage or abnormal deterioration to Train AB, CD or N battery cells, cell plates, and racks would not render the batteries inoperable unless the damage or deterioration could degrade battery performance.
The amendments would also modify the TS Bases to describe the reason for the SR and the criteria for determining operability. In its submittal, the licensee indicated that adopting the provisions of TSTF-38 is appropriate because it considers that, under some conditions, the current TSs are overly restrictive.
Prior to approval of TSTF-38, STS SR 3.8.4.3 state, Verify battery cells, cell plates, and racks show no visual indication of physical damage or abnormal deterioration. TSTF-38 clarified the requirements of this SR to be consistent with the regulatory intent of the visual inspection as reflected in the associated STS Bases. The purpose of the battery visual inspection is to identify physical damage or abnormal deterioration that could potentially degrade battery performance. Thus, any identified physical damage or abnormal deterioration has to be of a type that could degrade battery performance before the SR would not be satisfied. The presence of physical damage or deterioration does not necessarily represent a failure of the SR, provided an evaluation determines that the physical damage or deterioration does not affect the operability of the battery (its capability to perform its intended safety function). For these reasons and for clarity, TSTF-38 revised the wording of STS SR 3.8.4.3 by adding the phrase, that could degrade battery performance. Additionally, the associated STS Bases was revised to clarify the measures to be taken in the event physical damage or deterioration is discovered.
The staff finds that the licensee in its submittal identified the applicable regulatory requirements.
The regulatory requirements for which the staff based its acceptance criteria are:
10 CFR Sections 50.36, 50.55a, 50.59, 50.65, 50.90, and 50.92;
Technical Specification Task Force Traveler TSTF-38, Revision 0. Approved by the NRC on August 13, 1997;
The model TSs contained in the improved standard technical specifications (STSs),
NUREG-1431, Revision 2, Standard Technical Specifications, Westinghouse Plants,"
dated October 10, 2001; specifically SR 3.8.1 and associated Bases; and
NRC Generic Letter 91-18, Information To Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability.
The NRC previously approved implementation of TSTF-38 for Grand Gulf Nuclear Station and Perry Nuclear Power Plant. Grand Gulf and Perry are boiling water reactors; however, TSTF-38 was approved as applicable to all boiling and pressurized water reactors.
4.0 TECHNICAL EVALUATION
The staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment which are described in Enclosure 1 of the licensees application.
The evaluation below supports the conclusions that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
The licensee proposed to change SRs 4.8.2.3.2.c.1 and 4.8.2.5.2.c.1 in current Specifications 3/4.8.2.3 and 3/4.8.2.5, DC Distribution - Operating, for the train AB, CD and N batteries, from
[Each 250-volt battery bank and charger shall be demonstrated operable at least once per 18 months by] Verifying that the cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.
to
[Each 250-volt battery bank and charger shall be demonstrated operable at least once per 18 months by] Verifying that the cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.
The licensee also proposed an accompanying change to the Bases for TS Section 3/4.8, Electrical Power Systems, by adding the following paragraph:
Visual inspection of the battery cells, cell plates, and battery racks provide an indication of physical damage or deterioration that could potentially degrade battery performance. The presence of physical damage or deterioration does not necessarily represent a failure of SR 4.8.2.3.2.c.1, provided an evaluation determines that the physical damage or deterioration does not affect the OPERABILITY of the battery (its ability to perform its design function).
The operability of the dc power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety-related equipment required for the safe shutdown of the facility, and the mitigation and control of accident conditions within the facility. By periodically visually inspecting the battery cells, cell plates, and battery racks, the licensee can identify physical damage or abnormal deterioration that could potentially degrade battery performance. SRs 4.8.2.3.2.c.1 and 4.8.2.5.2.c.1 currently require verification at least once per 18 months that the train AB, CD and N battery cells, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration. Literal compliance with these requirements results in the battery being declared inoperable if any physical damage or abnormal deterioration is observed, regardless of the actual effect on battery performance. Were battery performance not affected, the current SR would be overly restrictive.
The amendments would eliminate the requirement to declare the train AB, CD or N battery inoperable due to physical damage or abnormal deterioration of the cells, cell plates, or racks if the damage or deterioration would not degrade battery performance. The amendments would also require basing a decision to not declare the battery inoperable on an evaluation of the observed physical damage or abnormal deterioration.
The discovery of physical damage or abnormal deterioration on a battery would be addressed through the D. C Cook corrective action program. The licensee has committed that this program contains provisions for promptly determining operability consistent with the guidance in NRC Generic Letter 91-18, Information To Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability. The battery operability evaluation would be driven by the nature and extent of the material condition identified. The damage or deterioration would be evaluated based on its severity and its relation to the critical parts of the battery and its performance requirements, and would involve the manufacturers representative as appropriate.
The provisions of TSTF-38, Rev. 0, which has been incorporated into the STSs, are applicable to D. C. Cook Units 1 and 2. Thus, the licensee has modeled the proposed changes on TSTF-38. The proposed wording of D. C. Cook TS 4.8.2.3.2.c.1 and TS 4.8.2.5.2.c.1 is virtually identical to that of the corresponding STS SR.
The proposed changes to SR 4.8.2.3.2.c.1 and TS 4.8.2.5.2.c.1 permit the evaluation of any identified physical damage or abnormal deterioration to determine operability, rather than automatic declaration of inoperability. These changes are acceptable because (a) it meets the intent of the current SR, as explained in the STS Bases for the corresponding STS SR, (b) the D. C. Cook Unit 2 corrective action program contains adequate controls for performing operability evaluations; and (c) it will preclude unnecessary entry into the action statements of Specifications 3/4.8.2.3 and 3/4.8.2.5 when identified physical damage or abnormal deterioration is determined not to affect battery performance, thereby avoiding the risk associated with a unit shutdown. The proposed changes are also consistent with corresponding STS SR 3.8.4.3.
Although the current TS Bases do not specifically address TS 4.8.2.3.2.c.1 and TS 4.8.2.5.2.c.1, the STS Bases for the corresponding SR is valid for the 2 SR, as revised.
Therefore, the licensee has adopted the STS Bases language in support of the revised SR.
The staff verified that the associated change to the TS Bases adequately explained the technical basis for the revised requirement. Therefore, the staff has no objection to the proposed Bases change.
5.0
SUMMARY
The licensee proposed that the wording of TS SR 4.8.2.3.2.c.1, TS SR 4.8.2.5.2.c.1 and its associated Bases, be changed to reflect the evaluation of physical damage to determine operability, rather than automatic declaration of inoperability when any physical damage is noted. These changes are acceptable since it meets the intent of the SR, as explained in the Bases; the licensee has adequate provisions for performing such an evaluation; and it will preclude unnecessary entry into the action statements of Specification 3/4.8.2.3 or 3/4.8.2.5 when identified physical damage or abnormal deterioration is determined not to affect battery performance, thereby avoiding the risk associated with a unit shutdown. The changes are also consistent with corresponding STS SR 3.8.4.3.
6.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Michigan State official was notified of the proposed issuance of the amendments. The State official had no comments.
7.0 ENVIRONMENTAL CONSIDERATION
These amendments change the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change the surveillance requirements. The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding (67 FR 20552). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
8.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Jack Foster Date: May 30, 2002