ML072780605
| ML072780605 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/18/2007 |
| From: | Tam P NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Nazar M Indiana Michigan Power Co |
| tam P, NRR/ADRO/DORL, 415-1451 | |
| Shared Package | |
| ML072960030 | List: |
| References | |
| GL-04-002, TAC MD5901, TAC MD5902 | |
| Download: ML072780605 (17) | |
Text
October 18, 2007 Mr. Mano K. Nazar Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 & 2 (DCCNP-1 AND DCCNP-2) -
ISSUANCE OF AMENDMENTS RE: CONTAINMENT SUMP MODIFICATIONS PER GENERIC LETTER 2004-02 (TAC NOS. MD5901 AND MD5902)
Dear Mr. Nazar:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 299 to Renewed Facility Operating License No. DPR-58 for DCCNP-1, and Amendment No. 282 to Renewed Facility Operating License No. DPR-74 for DCCNP-2. The amendment consists of changes to the technical specifications (TS) in response to your application dated June 27, 2007, as supplemented on September 21, 2007.
The amendments made changes to Sections 3.3.3, Post Accident Monitoring Instrumentation, 3.5, Emergency Core Cooling Systems, and 3.6.14, Containment Recirculation Drains, of the DCCNP-1 and DCCNP-2 TSs to reflect resolution of issues raised by Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors.
A copy of our related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Amendment No. 299 for DCCNP-1
- 2. Amendment No. 282 for DCCNP-2
- 3. Safety Evaluation cc w/encls: See next page
Mr. Mano K. Nazar Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 & 2 (DCCNP-1 AND DCCNP-2) -
ISSUANCE OF AMENDMENTS RE: CONTAINMENT SUMP MODIFICATIONS PER GENERIC LETTER 2004-02 (TAC NOS. MD5901 AND MD5902)
Dear Mr. Nazar:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 299 to Renewed Facility Operating License No. DPR-58 for DCCNP-1, and Amendment No. 282 to Renewed Facility Operating License No. DPR-74 for DCCNP-2. The amendment consists of changes to the technical specifications (TS) in response to your application dated June 27, 2007, as supplemented on September 21, 2007.
The amendments made changes to Sections 3.3.3, Post Accident Monitoring Instrumentation, 3.5, Emergency Core Cooling Systems, and 3.6.14, Containment Recirculation Drains, of the DCCNP-1 and DCCNP-2 TSs to reflect resolution of issues raised by Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors.
A copy of our related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Amendment No. 299 for DCCNP-1
- 2. Amendment No. 282 for DCCNP-2
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION PUBLIC GHill, OIS LPL3-1 R/F RidsOgcRp RidsNrrLATHarris RidsNrrPMPTam RidsDorlDpr RidsNrrDirsltsb RidsAcrsAcnwMailCenter RidsRgn3MailCenter PChung, NRR BMarcus, NRR RidsNrrDorlLpl3-1 RidsNrrPMPTam RidsNrrDssSrxb RidsNrrDeEicb Package Accession Number: ML072960030 Amendment Accession Number: ML072780605 TS Pages Accession Number: ML072950100 OFFICE LPL3-1/PM LPL3-1/LA SCVB/BC SSIB/BC EICB OGC/NLO LPL3-1/BC(A)
NAME PTam THarris RDennig*
MScott*
WKemper*
MLoftus TTate*
DATE 10/12/07 10/12/07 9/27/07*
9/27/07 10/3/07*
10/16/07 10/18/07
- Safety evaluation transmitted by memo on date shown.
OFFICIAL RECORD COPY
INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 299 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 June 27, 2007, as supplemented by letter dated September 21, 2007, 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.
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 Renewed Facility Operating License No. DPR-58 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 299, are hereby incorporated in the renewed operating 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 prior to entry into Mode 4 following the units spring 2008 refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Travis L. Tate, Acting Chief Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Operating License and Technical Specifications Date of Issuance: October 18, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 299 RENEWED FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Replace the following page of Renewed Facility Operating License No. DPR-58 with the attached revised page. The change area is identified by a marginal line.
REMOVE INSERT 3
3 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The change areas are identified by a marginal line.
REMOVE INSERT 3.3.3-5 3.3.3-5 3.5.2-3 3.5.2-3 3.6.14-1 3.6.14-1 3.6.14-2 3.6.14-2 3.6.14-3
and radiation monitoring equipment calibration, and as fission detectors in amounts as required.
(4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of thee Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3304 megawatts thermal in accordance with the conditions specified therein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 299, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Less Than Four Loop Operation The licensee shall not operate the reactor at power levels above P-7 (as defined in Table 3.3.1-1 of Specification 3.3.1 of Appendix A to this renewed operating license) with less than four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.
(4)
Indiana Michigan Power Company shall implement and maintain, in effect, all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for the facility and as approved in the SERs dated December 12, 1977, July 31, 1979, January 10, 1981, February 7, 1983, November 22, 1983, December 23, 1983, March 16, 1984, August 27, 1985 Renewed License No. DPR-58 Amendment No. 1 through 299
INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 282 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 June 27, 2007, as supplemented by letter dated September 21, 2007, 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.
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 Renewed Facility Operating License No. DPR-74 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 282, are hereby incorporated in the renewed operating 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 prior to entry into Mode 4 following the unit=s fall 2007 refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Travis L. Tate, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Operating License and Technical Specifications Date of Issuance: October 18, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 282 RENEWED FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Replace the following page of Renewed Facility Operating License No. DPR-74 with the attached revised page. The change area is identified by a marginal line.
REMOVE INSERT Page 3 Page 3 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The change areas are identified by a marginal line.
REMOVE INSERT 3.3.3-5 3.3.3-5 3.5.2-3 3.5.2-3 3.6.14-1 3.6.14-1 3.6.14-2 3.6.14-2 3.6.14-3
radiation monitoring equipment calibration, and as fission detectors in amounts as required.
(4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3468 megawatts thermal in accordance with the conditions specified therein and in attachment 1 to the renewed operating license. The preoperational tests, startup and other items identified in to this renewed operating license shall be completed. is an integral part of this renewed operating license.
(2)
Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 282, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Additional Conditions (a)
Deleted by Amendment No. 76 (b)
Deleted by Amendment No. 2 (c)
Leak Testing of Emergency Core cooling System Valves Indiana Michigan Power company shall prior to completion of the first inservice testing interval test each of the two valves in series in the Renewed License No. DPR-74 Amendment No. 1 through 282
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 299 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-58 AMENDMENT NO. 282 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNITS 1 & 2 (DCCNP-1 AND DCCNP-2)
DOCKET NOS. 50-315 AND 50-316
1.0 INTRODUCTION
By application to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated June 27, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML071910354), as supplemented by letter dated September 21, 2007 (ADAMS Accession No. ML072750687), Indiana Michigan Power Company (I&M, the licensee) requested an amendment to the technical specifications (TS) for Donald C. Cook Nuclear Plant, Unit 1 and Unit 2 (DCCNP-1 and DCCNP-2). The licensee proposed several changes to the DCCNP-1 and DCCNP-2 TS to support resolution of issues raised by Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors.
The licensee's September 21, 2007, supplement provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register on July 31, 2007 (72 FR 41786).
2.0 REGULATORY EVALUATION
The NRCs regulations at Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix A, General Design Criterion 35, Emergency core cooling, requires that the emergency core cooling system (ECCS) provide abundant emergency core cooling.
The regulation at 10 CFR 50.46(b)(5) requires that after successful initial operation of the ECCS, the calculated core temperature shall be maintained at an acceptably low value, and decay heat shall be removed for the extended period of time required by the long-lived radioactivity remaining in the core.
The regulation at 10 CFR 50.36(c)(2)(ii)(C) requires that TS Limiting Conditions of Operation (LCO) of a nuclear reactor be established for a structure, system, or component that is part of the primary success path, and which functions or actuates to mitigate a design-basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
The regulation at 10 CFR 50.36(c)(3) requires that TS surveillance requirements (SR) assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met.
Regulatory Guide (RG) 1.97 describes a method acceptable to the NRC staff for complying with the Commissions regulations to provide instrumentation for monitoring plant variables and systems during and after an accident. Type A variables are those that provide primary information needed to permit the control room operating personnel to take specific manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design-basis accidents.
NRC GL 2004-02 requests that pressurized-water reactor licensees evaluate the potential for adverse effects of post-accident debris blockage and operation with debris-laden fluids, which could impede or prevent the recirculation functions of the ECCS and containment heat removal pumps.
3.0 TECHNICAL EVALUATION
3.1 Containment Recirculation Drains The licensee proposed to revise the DCCNP-1 and DCCNP-2 TS, Section 3.6.14, Containment Recirculation Drains, to ensure the availability of two flow paths needed to provide an adequate water level in the ECCS recirculation sump following a loss-of-coolant accident. These two flow paths provide water to the sump via the CEQ (see below) fan room drains and the flood-up overflow wall holes. The proposed wording change to LCO 3.6.14 is as follows (strikeout =
deleted words, italics = new words):
LCO 3.6.14 The ice condenser floor drains, and two refueling canal drains, one drain in each Containment Air Recirculation/Hydrogen Skimmer System (CEQ) fan room, and the flood-up overflow wall flow paths shall be OPERABLE.
With one required CEQ fan room drain inoperable, the licensee proposed a required action to restore the required CEQ fan room drain to OPERABLE status within a completion time of one hour. Likewise, the licensee proposed that with one flood-up overflow wall flow path inoperable, the required action is to restore the flood-up overflow wall flow path to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The NRC staff agrees with the licensee that these flow paths are needed in addition to the ice condenser floor drains and the refueling canal drains, which are covered by the existing LCO 3.6.14, and should be included in the TS as the licensee proposed. The licensees proposed required actions to restore the flow paths are acceptable and the associated completion times are conservative and also acceptable.
The licensee's response (letter, J. N. Jensen to NRC Document Control Desk, dated August 31, 2005; Accession No. ML052510512) to GL 2004-02, stated that debris interceptors would also be installed on the approach area to the remote strainer in the annulus and in the area of the inlet nozzles for the containment wide range level instruments in addition to the drain paths from the CEQ fan rooms and the existing flow holes from the loop compartment to the annulus. The licensees September 21, 2007, letter, stated that it is not necessary to include the debris interceptors installed on the approach area to the remote strainer in the annulus and in the area
of the inlet nozzles for the containment wide range level instruments since no credit is taken for these in the analyses performed to resolve the GL 2004-02 issues. The NRC staff agrees that since no credit is taken in the supporting analyses, these interceptors are not required to be included in the TS.
3.2 Recirculation Sump Level Instrumentation The licensee proposed to revise TS Section 3.3.3, Post-Accident Monitoring Instrumentation, to include containment recirculation sump level instrumentation, which will be used for indication of recirculation sump strainer blockage. Specifically, the licensee proposed to revise Table 3.3.3-1, Post Accident Monitoring (PAM) Instrumentation, to add a new Function 25, Containment Recirculation Sump Water Level. The new function will provide an indication and alarm function if the water level in the sump drops below an acceptable level. The selected level setting provides advanced warning of potential air entrainment due to vortexing, which, for the DCCNP-1 and DCCNP-2 design is more limiting for proper pump functioning than the net positive suction head limitation. Air entrainment can lead to degraded pump flow. The level switches are armed by a rising level in the recirculation sump. The two new recirculation sump level instruments are in addition to the existing containment water level instruments which are located outside the recirculation sump. The new instruments are located inside the recirculation sump enclosure.
The licensees September 21, 2007, letter, provided details on the actions the operator will take upon actuation of the level alarms. The licensee stated that procedures will direct the operator to reduce flow by securing emergency core cooling or containment spray pumps, and wait a specified period for the alarm to clear. If the alarm does not clear, additional pumps will be secured.
The level instrumentation provides the operator with the opportunity to correct an adverse condition (loss of adequate pump suction) and, therefore, adds additional margin to the licensees new recirculation sump design. The addition of this instrumentation is, therefore, acceptable.
The new Containment Recirculation Sump Water level function will be a Type A variable monitored by a Category I instrument, as defined in RG 1.97, Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants.
The NRC staff finds the licensees proposal acceptable with respect to its function of providing indication and alarm to ensure adequate performance of the ECCS and containment heat removal pumps. The acceptability of the instrumentation design and the associated TS Table 3.3.3-1 is evaluated below in Section 3.4.
3.3 Replacing the Term Trash Rack and Screens with the Term Strainers The licensee proposed to modify SR 3.5.2.7 by changing the terminology of "trash racks and screens" to "strainers." The licensee indicated that the replacement of "trash racks and screens" with "strainers" in SR 3.5.2.7 provides a more appropriate description of the sump configuration after the installation of a larger strainer assembly to address GL 2004-02 concerns. The licensees application states that the new main and remote strainer assemblies, designed and fabricated by Control Components Incorporated, integrally combine the screen and trash rack functions for the recirculation sump.
The licensees September 21, 2007, letter, addressed the basis for the removal of the existing trash rack function with regards to qualification of the replacement strainer for missile protection, jet impingement, and pipe whip. The licensee also addressed the qualification of the strainers for the maximum expected differential pressure that could exist due to debris collection on the strainer. The licensee predicted that the most significant pieces of debris would be portions of the reflective metallic insulation dislodged during the postulated high-energy line break. This material is thin gauge stainless steel sheet that would not damage the face of the strainer.
The licensee stated that the strainers have been designed and qualified by vendor analysis to withstand the differential pressure due to complete blockage at the predicted maximum containment water level. The licensee also stated that evaluations of the potential for damage to the strainers from direct jet impingement or pipe whip due to breaks in branch lines connected to the main coolant loop piping were performed. These evaluations demonstrated that there would be no impacts to the strainers from direct jet impingement, missiles, and pipe whip for main coolant loop branch connections or other high-energy line breaks inside containment. Based on these evaluations, the NRC staff finds the change in terminology from trash racks and screens to strainers to be acceptable since the proposed new strainers satisfy the same safety functions as previously satisfied by the trash racks and screens.
3.4 Post Accident Monitoring Instrumentation (PAM)
The licensee proposed to revise TS Section 3.3.3, Post Accident Monitoring Instrumentation, Table 3.3.3-1, by adding a new Function 25, "Containment Recirculation Sump Water Level."
This Function will have two required channels, and will reference Condition "G" from Required Action F.1.
The proposed containment recirculation sump water level instrumentation will provide indication and alarm function if the water level in the containment recirculation sump drops to an undesirable level. This setting will provide advanced warning of excessive fouling or blockage of the sump strainers. The licensee has determined that the containment recirculation sump water level instrumentation satisfies 10 CFR 50.36 (c)(2)(ii)(C) and should, therefore, be classified as a RG 1.97, Type A, variable and be included in TS Section 3.3.3. The licensee stated that the containment recirculation sump water level instrumentation meets the Category 1 criteria of RG 1.97, which includes environmental and seismic qualification, redundancy, Class 1E power sources, and continuous real-time display. Based on the licensees classification of this instrumentation as a Type A variable, and the licensees commitment that this instrumentation meets Category 1 of RG 1.97, the NRC staff finds that the containment recirculation sump water level instrumentation is in conformance with RG 1.97.
The new Function 25 will provide indication and alarm function if the water level in the sump drops to an undesirable level. System redundancy is provided by having two required channels of instrumentation. The TS requirement for two operable channels provides redundancy from a single failure causing a complete loss of function.
The current TS 3.3.3 LCO, Applicability, Actions, and Surveillance Requirements will apply to the new containment recirculation sump water level function. Action A.1 will require that an inoperable containment recirculation sump water level channel be restored to operable status within 30 days. In the event that the inoperable channel cannot be restored to operable status within 30 days, Action B.1 will require that TS 5.6.6 be followed which requires submittal of a report within 14 days outlining the pre-planned alternative method of monitoring, the cause of
the inoperability, and the plans and schedule for restoring the instrumentation channels of the function to operable status.
The licensees proposed 30-day allowed outage time (AOT) is appropriate based on operating experience and takes into account the remaining operable channels, the passive nature of the instrument (i.e., the instrument does not initiate critical automatic actions), and the low probability of an event requiring the accident monitoring instrumentation during this interval. If the inoperable channel cannot be restored to operable status within 30 days, the proposed submission of a special report within the next 14 days is appropriate because there would be at least one functional instrument channel to provide information, and the special report would adequately address actions taken and the availability of diverse or alternate monitoring capability.
If both containment recirculation sump water level channels are inoperable, Action D.1 will require that one channel be restored to operable status within 7 days. If one channel cannot be restored to operable status within 7 days, Actions F.1, G.1, and G.2 will require that the unit be in Mode 3 (hot standby) in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 4 (hot shutdown) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed 7-day restoration AOT, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to reach hot standby, and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to reach hot shutdown, are appropriate because they allow a reasonable time for repair or shutdown. In addition, the probability of an event requiring the accident monitoring instrumentation during this interval is low.
SR 3.3.3.1 requires a channel check to be performed for each containment recirculation sump water level channel every 31 days. SR 3.3.3.3 requires a channel calibration be performed for each containment sump water level channel every 24 months. The frequency for SR 3.3.3.1 and SR 3.3.3.3 are the same for all PAM functions in TS Table 3.3.3-1. Therefore, SR 3.3.3.1 and SR 3.3.3.3 are appropriate for the containment recirculation sump water level instrumentation.
The NRC staff has reviewed the licensees proposed TS changes concerning the addition of containment recirculation sump water level instrumentation to TS Table 3.3.3-1. The NRC staff finds the Actions, AOTs, and SR proposed by the licensee meet the requirements of 10 CFR 50.36(c)(2)(ii)(C) and 10 CFR 50.36(c)(3), and are, therefore, acceptable.
3.5 TS Bases The licensee proposed changes to the TS Bases associated with the TS sections evaluated above. The TS Bases are not part of the TS (see 10 CFR Section 50.36(a)), and currently exist in a licensee-controlled document. The NRC staff reviewed the licensee's proposed TS Bases changes and found that they reflect the proposed modifications as evaluated above in Sections 3.1 thru 3.4.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation and use of facility components located within the restricted area as defined in 10 CFR Part 20, and change the surveillance requirements. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (72 FR 41786). 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.
6.0 CONCLUSION
The Commission 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 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.
Principal Contributor: R. Lobel R. Architzel B. Marcus P. Chung Date: October 18, 2007
Donald C. Cook Nuclear Plant, Units 1 and 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 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 Inspector's Office 7700 Red Arrow Highway Stevensville, MI 49127 Kimberly Harshaw, 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 Susan D. Simpson Regulatory Affairs Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Michigan Department of Environmental Quality Waste and Hazardous Materials Div.
Hazardous Waste & Radiological Protection Section Nuclear Facilities Unit Constitution Hall, Lower-Level North 525 West Allegan Street P. O. Box 30241 Lansing, MI 48909-7741 Lawrence J. Weber, Plant Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Joseph Jensen, Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106