ML20094S270
| ML20094S270 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/28/1995 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20094S271 | List: |
| References | |
| NUDOCS 9512060096 | |
| Download: ML20094S270 (4) | |
Text
.
Northern States Power Company 1
1717 Wakonede Dr. E.
Welch, MN 55000 l
Telephone 612-388-1121 November 28,1995 I
10 CFR Part 50 Section 50.90 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 July 17,1995 Radiological Effluent Technical Specifications Conformance To Standard Technical Specifications and Generic Letter 89-01 Pursuant to discussions with your staff regarding the subject license amendment request, this supplement proposes changes as presented in Attachments 1 and 2 to this letter. Attachment 1 contains current Prairie Island Technical Specification pages marked up to implement the proposed modifications to this license amendment request. Attachment 2 contains Technical Specification pages revised to their final form to reflect the proposed changes. Supplemental information in support of these changes follows.
Pages 2 and 8 of Exhibit A of the subject LAR indicated that the Prairie Island Plant will continue to use Appendix B to old 10CFR Part 20. That discussion is clarified in that the Prairie Island Plant's instantaneous release rate limits will continue to be the values in the old 10CFR Part 20 Appendix B in accordance with the guidance provided in the June 30,1993 letter from Thomas E. Murley, NRC, to Thomas E.
Tipton, Nuclear Management and Resources Council. Accordingly, the references 06000G 1
Ch 9512060096 951528 g
PDR ADOCK 05000282
.P_
_PDR_
4 USNRC i
11/28/95 l
1 Page 2 of 4 in proposed Specifications 6.5.E.1.b and 6.5.H.3, pages TS.6.5-5 and TS.6.5-7, respectively, have been changed to "10CFR20.1302."
i As proposed in the July 17,1995 submittal, Technical Specification 6.5.B.1.a item d
(4), page TS.6.5-2, will not be used alone but rather will always t;e used in addition to item (1), (2), or (3). Thus item (4) has been deleted from the Technical
(-
Specifications proposed in Attachments 1 and 2 to this letter. Since paragraph 6.5.B.1.b referenced 6.5.B.1.a item (4), it has been revised to appropriately J
incorporate the referenced wording from item (4). This change improves I
conformance of the proposed Prairie Island Technical Specifications to NUREG-1431, Standard Technical Specifications.
From discussions with the NRC staff, it is our understanding that Technical
{,
Specification 6.5.H Paragraphs 4, 8, and 9, as proposed in the July 17,1995 i
submittal, would be interpreted to reduce the allowable plant releases below the j
regulatory and current Prairie Island Technical Specification limits. Accordingly, "the site" in each of these paragraphs is revised to "each unit". This change also 4
improves conformance of the proposed Prairie Island Technical Specifications to j-NUREG-1431, Standard Technical Specifications.
Specification 6.7.C.1, Annual Radiological Environmental Monitoring Report, has l
been revised to retain existing paragraphs (c) and (d) on page TS.6.7-6. This change improves conformance of the proposed Prairie Island Technical l
Specifications to NUREG-1431, Standard Technical Specifications. This change also introduces some changes in the specification pagination and concomitant changes to the Table of Contents page TS-ix are provided.
A revised Safety Evaluation, Significant Hazards Determination and Environmental Assessment have not been submitted with the changes proposed by this letter since i
these evaluations, as originally presented in the July 17,1995 submittal, continue to l
bound the proposed license amendment as modified by this supplement.
Recently issued Amendments 120 and 121 do not have an impact on the subject license amendment request, this supplement or the previous supplement dated October 16,1995.
I a
4 USNRC
' 11/28/95 Page 3 of 4 If you have any questions related to this information in support of the subject license amendment request, please contact myself or Dale Vincent at 612-388-6758 X4107.
M. D. Wadley Plant Manager, Prairie Island Nuclear Generating Plant : Marked Up Technical Specification Pages : Revised Technical Specification Pages c:
Regional Administrator-lil, NRC NRR Project Manager, NRC Senior Resident Inspector, NRC State of Minnesota Attn: Kris Sanda J E Silberg
4 USNRC
' 11/28/95 Page 4 of 4 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 50-306 REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR-42 & DPR-60 LICENSE AMENDMENT REQUEST DATED July 17,1995 Northern States Power Company, a Minnesota corporation, by this letter dated November 28,1995 provides this supplemental information in support of its license amendment request dated July 17,1995.
This letter contains no restricted or other defense information.
l NORTHERN STATES POWER COMPANY By Michael D. Wadley Plant Manager Prairie Island Nuclear Generating Plant i
fh before me a notary
]
On this day of public in and for said County, personally appeared, Michael D. Wadley, Plant j
Manager, Prairie Island Nuclear Generating Plant, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern l
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.
3 V
1
/
- --- ::::::::::::::::.. ;:::::::::.m y
' avusvsaswyms i l l IdARML& ta001E U
IM;
~
EQ l
n,
=
=
.... m r.... w
-I 7 ~~~ ~~~"~"""'