ML20134L885
| ML20134L885 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/12/1997 |
| From: | Sorenstein J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20134L888 | List: |
| References | |
| NUDOCS 9702200001 | |
| Download: ML20134L885 (5) | |
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1 Northern States Power Company i
1717 Wakonade Dr. E.
Welch. MN 55089 Telephone 612-388-1121 February 12,1997 10 CFR Part 50 i
Section 50.90
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U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Supplement to License Amendment Request Dated February 6,1997 Amendment of Safety inlection Pump Low Temperature Operations J
This letter is submitted to supplement the subject license amendment request pursuant to discussions with the NRC staff. Specific Technical Specification page changes are presented in Attachments 1 and 2 to this letter. Attachment 1 contains Technical Specification pages marked up to show the changes proposed by this supplement. Attachment 2 contains Technical Specification pages revised to their final form to reflect the changes proposed by this supplement. The Technical Specification page changes contained in Attachments 1 and 2 supersede all Technical Specification page changes presented in Exhibits B and C of the subject j
license amendment request. Specific changes to the Technical Specifications proposed by this supplement are discussed below.
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The underlying purpose of Prairie Island Technical Specifications 3.3.A.3 and 3.3.A.4 is to protect the RCS from low temperature overpressurization. These specifications and their bases have been revised as shown in Attachments 1 and 2 in a fashion which continues to achieve the underlying purpose with fewer changes involved.
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USNRC 2/12/97 Pggs 2 of 3
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Specification 3.3.A.3 is revised by including a new clause, "for up to one hour",
which will provide further assurance, in addition to the current Technical Specification provisions, that the RCS will not be subjected to conditions under which it could potentially be overpressurized. Currently the Technical Specifications require that a gas or steam bubble is maintained in the pressurizer and an isolation valve is closed.
Also a footnote has been added to Specification 3.3.A.3 which allows other safety injection system tests and operations to be conducted under the same provisions as the safety injection integrated test. RCS integrity will tu protected during an i
integrated safety injection test by the provisions currently in the Prairie Island Technical Specifications and the new restriction limitating the safety injection pump l
to run for one hour. The current Technical Specification provisions are discussed i
fully in the subject license amendment request. The clarification that a valve other i
than the safety injection pump discharge valve may be used for isolation from the RCS, as proposed in the subject submittal, has been retained. The Technical I
Specification changes proposed by tbh,upplement limit the use of a steam or gas bubble in the pressurizer with a closed isolation valve in each flow path to one hour.
When in this condition, this proposed Technical Specification appropriately requires
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a single isolation valve to be closed since it is not always possible to close two j
isolation valves. Specifically, when an ECCS accumulator is filled it is not possible -
i to close two isolation valves, since there is only one isolation valve in the system which can be closed.
Specification 3.3.A.4 is revised by adding a footnote that states the provisions of this specification do not apply when the reactor vessel head is removed. When the
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reactor vessel head is removed it is not possible to overpressurize the RCS and the
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provisions of this specificaticn no longer need to be applied. An additional clause is inserted stating "one or both pumps may be run" to make it clear that the exceptions in 3.3.A.3 are also allowable if only one pump is operated.
The Bases have also been revised to reflect the changes in these specifications.
The discussion pertaining to performance of the integrated safety injection test has j
been revised to limit running the pump to no more than one hour under these conditions and to allow performance of other tests and operations.
A revised Safety Evaluation, Significant Hazards Determination and Environmental Assessment have not been submitted with the changes proposed by this letter since these evaluations, as originally presented in the February 6,1997 submittal, continue to bound the proposed license amendment as modified by this supplement.
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If you have any questions related to this information in support of the subject license j
amendment request, please contact myself or Dale Vincent at 612-388 6758.
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Joel P. Sorensen 1
Plant Manager, i
Prairie Island Nuclear Generating Plant i
S 1
- Marked Up Technical Specification Pages
~ : Revised Technical Specification Pages c:
Regional Administrator-Ill, NRC NRR Project Manager, NRC Senior Resident inspector, NRC 4
State of Minnesota Attn: Kris Sanda J E Silberg i
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l UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET Nos. 50-232 50-306 j
REQUEST FOR AMENDMENT T0 OPERATING LICENSES DPR-42 & DPR-60 l
LICENSE AMENDMENT REQUEST DATED February 6,1997 Amendment of Safety Iniection Pumo Low Temperature Ooerations j
Northern States Power Company, a Minnesota corporation, by this letter dated l
February 12,1997, with Attachments 1 and 2, provides supplemental information in support of its license amendment request dated February 6,1997. Attachment 1 contains current Prairie Island Technical Specification pages marked up to show propcced changes. Attachment 2 contains the revised Technical Specification i
5 pages incorporating the proposed changes.
This letter and its attachments contain no restricted or other defense information.
NORTHERN STATES POWER COMPANY By M
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Jgpf4). sorens(n '
Plant Manager Prairie Island Nuclear Generating Plant i
On this /2 4A day of k\\nw m
\\W before me a notary public in and for said County, personally a'p"p' eared, Joel P. Sorensen, Plant Manager, Prairie Island Nuclear Generating Plant, and being first duly sworn 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 csde in it are true and that it is not interposed for delay.
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i ATTACHMENT 1 I
SUPPLEMENT to 4
LICENSE AMENDMENT REQUEST DATED February 6,1997 Amendment of Safety iniection Pumo Low Temperature Operations J
4 Appendix A, Technical Specification Pages Marked Up Pages as proposed in this Supplement 1
TS.3.3-3 B.3.3-2 I
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