ML20137T057
| ML20137T057 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/10/1997 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9704150304 | |
| Download: ML20137T057 (6) | |
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Northern states Power Company 1717 Wakonade Dr. E.
Welch, MN 55089 Telephone 012-388-1121 I
l April 10,1997 l
Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk l
Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 l
Supplement to License Amendment Request Dated November 6,1996 j
Resubmittal of Coolina Water System Technical Specification Amendments l
l This letter is submitted to supplement the subject license amendment request in response to the NRC request for additional information (TAC NOS. M97332 and M97333) dated February 21,1997 and to provide schedule information related to this license amendment request.
The NRC Staff has requested specific details regarding the new location for information relocated from current Technical Specifications 5.1 and 5.4. These details are provided as follows:
l TS 5.1. Pace TS.S.1-1. Paraaraoh 1 l
The corrected information regarding the nearest population center is currently located in USAR Section 2.2 and is under the control of 10 CFR 50.59. The regulations in 10 CFR 50.36(c)(4) requires design features to be included in Technical Specifications which if altered or modified would have a significant effect on safety and are not covered by the Technical Specification j
safety limits, limiting conditions for operation, or surveillance requirements.
This information is appropriately removed from the Technical Specifications
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since it does not meet the requirements of 10 CFR 50.36 because if it is 970415o304 970410 PDR ADOCK0500g2 gg
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altered or modified it would not have a significant effect on safety.
Furthermore,10 CFR 50.59 controls will identify those potential changes which would have a significant effect on safety.
TS 5.1. Paae TS.S.1-1. Paraaraoh 2 The information in this paragraph will be incorporated into USAR Chapter 2 in the next USAR update and will be under 10 CFR 50.59 control. Relocation of this information from Technical Specifications to the USAR is appropriate since 10 CFR 50.59 controls will identify changes which have a significant effect on safety.
TS 5.1. Pace TS.5.1-1. Paraaraoh 3 Meteorological considerations are discussed in USAR Chapter 2. During original plant licensing, NSP provided the AEC detailed meteorological data in FSAR, Appendix H which has been retained as USAR, Appendix H..ne atmospheric diffusion factors presented in this paragraph were generated by the NRC based on the Appendix H data for review and approval of the Prairie Island original license application and these numbers are presented in the original AEC Safety Evaluation Report (SER). Since these values appear in the AEC SER, the basis for these values have been retained in the USAR and they are not used by NSP, these numbers have not been relocated.
TS 5.1. Paae TS.S.1-1. Paraaraoh 4 The flood information presented in this paragraph is currently contained in USAR Section 2.4 and is currently under 10 CFR 50.59 control. Relocation of this information from Technical Specifications to the USAR is appropriate since 10 CFR 50.59 controls will identify changes due to acts of nature which have a significant effect on safety.
TS 5.1. Paae TS.5.1-1. Paraaraoh 5 The flood protection information contained in this paragraph is currently included in USAR Section 2.4 except that the number of doors with flood barriers shown in Figure 2.4-7 has changed due to the addition of two safeguarde diesels. This figure will be revised in the next USAR update.
Relocation of this information from Technical Specifications to the USAR is appropriate since 10 CFR 50.59 controls will identify changes which have a significant effect on safety.
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j TS 5.1. Paae TS.5.1-1. Paraaraoh 6 Flood protection information is currently included in USAR Section 2.4 and is under 10 CFR 50.59 control. The information contained in this Technical Specification paragraph will be corrected and incorporated into the USAR i
with the next update. Relocation of this information from Technical l
Specifications to the USAR is appropriate since 10 CFR 50.59 controls will identify changes which have a significant effect on safety.
TS 5.1. Paae TS.S.1-1. Paraaraoh 7 which carries over to Paae TS.S.1-2 i
USAR Section 2.4 requires that plant operating procedures and emergency l
plans state the flood stage elevation at which plant protective measures must i
i be taken. Removal of this information from the Technical Specifications is
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addressed in NSP's License Amendment Request dated December 14,1995.
Current Technical Specification 6.5.A.6 requires Prairie Island to prepare and follow procedures for flood conditions. Also, the License Amendment Request dated December 14,1995, includes a Technical Specification commitment to l
Regulatory Guide 1.33, Appendix A which requires the plant to have l
procedures to address flood conditions. Thus, in accordance with the proposal in the License Amendment Request dated December 14,1995, the l
l' requirement to have shutdown procedures will be controlled by the Technical i
Specifications although specific flood elevations will be addressed in plant procedures.
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TS 5.1. Paae TS.5.1-2. Paraaraoh 1
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USAR Sections 2.6 and 12.2 currently contain the seismic information presented in this paragraph. Current Technical Specification 6.5.A.6 requires Prairie Island to prepare and follow procedures for earthquakes. Also, the j
License Amendment Request dated December 14,1995, includes a
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Technical Specification commitment to Regulatory Guide 1.33, Appendix A which requires the plant to have procedures to address earthquakes. Thus the requirement for earthquake procedures remains under Technical Specification control.
J TS 5.4. Paae TS.5.4-1. Introductory Paraaraoh The information in this paragraph is general in nature. An overview of plant features provided to meet the objectives reflected in the AEC General Design Criteria is provided in USAR Section 1.2. A general discussion of applicable codes and standards is provided in USAR Section 12.2. More detailed description of the design features for each of the systems listed in this
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paragraph is presented in the applicable section of the USAR. Since this material is duplicative in nature it is not necessary to be retained.
TS 5.4. Paae TS.5.4-1. Paraaraoh 1 The correct shared system information contained in this paragraph is currently included in USAR Section 1.3, Tables 1.3-1 and 1.3-2 and is currently under 10 CFR 50.59 control. The onsite diesels are no longer shared systems since Prairie Island installed two additional safeguards diesels. Relocation of this information from Technical Specifications to the USAR is appropriate since 10 CFR 50.59 controls will identify changes which have a significant effect on safety prior to their implementation.
TS 5.4. Paae TS.5.4-1. Paraaraoh 2 The emergency cooling water pump information contained in this paragraph is currently included in USAR Section 10.4 and is currently under 10 CFR 50.59 control. Relocation of this information from Technical Specifications to the USAR is appropriate since 10 CFR 50.59 controls will identify changes which have a significant effect on safety prior to their implementation.
TS 5.4. Paae TS.S.4-1. Paraaraoh 3 The discussion in this paragraph relating to dividing the cooling water system into two Icops is currently included in USAR Section 10.4 and is under 10 CFR 50.59 control. Relocation of this information from Technical Specifications to the USAR is appropriate since 10 CFR 50.59 controls will identify changes which have a significant effect on safety prior to their -
implementation.
The balance of this paragraph relates to isolation of the turbine building supply header. The logic for the turbine building supply header isolation will be modified following issuance of the subject license amendment. This information will be incorporated into the USAR where it is under 10 CFR 50.59 control with the next update (mid-1999) following installation of the isolation logic modification in both Prairie Island Units. Incorporating this information into the USAR is appropriate since 10 CFR 50.59 controls will identify changes which have a significant effect on safety prior to their implementation. It should also be noted that these design features are covered by Technical Specification surveillance requirements and therefore, in accordance with 10 CFR 50 '.,6, are not required to be in the Technical Specification design features section.
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Due to the nature of the modification to the turbine building cooling water supply header isolation logic, NSP plans to install the first modification in a unit that is shut l
down and modify the other unit while it is operating. Accordingly, we request that l
this license amendment be issued on or about October 15,1997 and allow 90 days l
for implementation. "his would allow us to modify Unit 1 during the refueling outage l
scheduled to start October 15,1997 and would allow time to modify Unit 2 after the
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Unit 1 outage is completed.
A revised Safety Evaluation, Significant Hazards Determination and Environmental Assessment have not been submitted since these evaluations, as oriphally presented in the November 6,1996 submittal, continue to bound the proposed license amendment as supplemented. License amendments issued by the NRC subsequent to November 6,1996 do not have any impact on the subject license amendment.
If you have any questions related to this License Amendment Request please contact Dale Vincent at 612-388-6758.
Joel P. Sorensen Plant Manager Prairie Island Nuclear Generating Plant c:
Regional Administrator-Ill, NRC NRR Project Manager, NRC Senior Resident inspector, NRC State of Minnesota Attn: Kris Sanda J E Silberg i
UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET Nos. 50-282 50-306 REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR-42 & DPR-60 i
LICENSE AMENDMENT REQUEST DATED November 6,1996 4
Resubmittal of Coolino Water System Technical Specification Amendments Northern States Power Company, a Minnesota corporation, by this letter dated April 10,1997, provides supplemental information in support of the subject license amendment request dated November 6,1996 in response to the NRC Staff request i
for additional information dated February 21,1997.
This letter and its attachments contain no restricted or other defense information.
NOR ERN STATES OWER COMPANY By yogP. sorens60 i
Plant Manager Prairie Island Nuclear Generating Plant On this /0 day of bo l9 N before me a notary public in and for said County, perschally appeared, Joel P. Sorensen, Plant Manager, Prairie Island Nuclear Generating Plant, and being first duly sworn 3
acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.
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DALE M. VINCENT
- 0T m Pseuc.M*atsota DAKOTA COUNTY b ^^
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