ML20024B085
| ML20024B085 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/01/1983 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20024B084 | List: |
| References | |
| TAC-51991, TAC-51992, TAC-53458, TAC-53459, NUDOCS 8307050098 | |
| Download: ML20024B085 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION NORTilERN STAIES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLA?Tf Docket No. 50-282 50-306 REQUEST FOR AMENDMEITT TO OPERATING LICENSE NOS. DPR-42 & DPR-60 (License Amendment Request Dated July 1, 1983)
Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Exhibit B.
Exhibit A describes the proposed changes along with reasons for the change. Exhibit B is a set of Technical Specification pages incorporating the proposed changes.
Exhibit C is a table for use when cross referencing FSAR table 7.7-2 (USAR table 7.10-2) and the Technical Specifications.
This letter contains no restricted or other defense inf orma tion.
NORTHERN STATES POWER COMPANY By km David Musolf Manager - Nuclear Support Service on this
/Y day of 4M/
//f_3 before me a notary public in and for said County, personally appeared David Musolf, Manager - Nuclear Support Services, 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 made in it are true and that it is not interposed for delay.
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EXHIBIT A Prairie Island Nuclear Generating Plant License Amendment Request Dated July 1, 1983 Proposed Changes to the Technical Specifications Appendix A of Operating Licenses DPR-42 and DPR-60 Pursuant to 10 CFR 50.59 and 50.90, the holders of operating licenses DPR-42 and DPR-60 hereby, propose the following changes to Appendix A, Technical Specifications:
- 1. Specification: Containment System Reconbiners TS 3.6 & Table TS.4.4-1 PROPOSED CHANGE The Technical Specifications on page TS 3.6-3A, TS 3.6-6 and Table TS.4.4-1 are to be revised as noted in Exhibit B.
REASON FOR CRANCE These changes revise the Technical Specifications to reflect the hydrogen recombiners being installed to meet the requirements of the Commission's interin hydrogen rule.
SIGNIFICANT HAZARDS EVALUATION The Technical Specification changes follow the guidance provided in the NRC's Standard Technical Specifications for Westinghouse PWR's.
The proposed limiting conditions for operation and surveillance requirements constitue additional limitations, restrictions and controls not presently included in the Technical Specifications.
- 2. Specification: K(z) Curve Explanation TS.3.10 PROPOSED CHANGE Rephrase the second sentence in the fourth paragraph on page TS.3.10-9.
The replacement sentences are noted in Exhibit B.
REASON FOR CHANGE The description of the K(z) curve was inaccurate.
SIGNIFICAtTr HAZARDS EVALUATION The proposed change in wording is a purely administrative change to the Technical Specifications.
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r Exhibit A 3.
Specification: Table TS 3.12-1 (pg 7 of 8)
PROPOSED CHANGE Add CVCH-166 to Table TS.3.12-1 REASON FOR CHANGE The snubber was omitted from NSP License Amendment Request dated October 29, 1982. Amendment 63 for DPR-42 and Amendment 57 for DPR-60 were then issued with the omission.
SIGNIFICANT HAZARDS EVALUATION The proposed snubber addition constitutes an additional limitation, restriction or control not presently included in the Technical Specifications.
- 4. Specification: TS 3.13 & Table TS.4.1-1 Chlorine Detection System PROPOSED CHANGE A limiting condition of operation for the chlorine detection system was added to the Control Room Air Treatment Technical Specifications.
See Exhibit B, page TS.3.13-1. TS.3.13-1A, TS.3.13-2 and Table TS.4.1-1 (pg 5 of 5).
REASON FOR CHANGE These changes revise the Technical Specifications to reflect the toxic gas monitors installed in response to NUREC-0737, Item III.D.3.4.
SIGNIFICA?TT HAZARDS EVALUATION The proposed limiting conditions for operation and surveillance requirements constitue additional limitations, restrictions and controls not presently included in the Technical Specifications.
5.
Specification: TS 3.13.A f
PROPOSED CHANGE Delete the words "and the diesel-generator" in the technical l
specification section 3.13.A.
c J
l Exhibit A,
REASON FOR CHANGE TS.3.7.B.2 already requires the plant to have all engineered safety features operable before a Diesel Generator is removed fro service.
The words in TS.3.13.A are redundant and are not included in most of the other sections in the same category. The definitions of
" Operable" in Section 1 of the Technical Specifications also addresses this issue.
SIGNIFICANT HAZARDS EVALUATION The proposed change in wording is a purely administrative change to the Technical Specifications.
- 6. Specification: Table TS.4.1-1 Reference to FSAR Table 7.7-2 PROPOSED CHANGE Remove the reference to the FSAR Table 7.7-2 in Table TS 4.1-1, item
- 35.
REASON FOR CHANGE Confusion can exist between FSAR and USAR tables referencing the same information.
The statement is unclear since many of the instruments in FSAR Table 7.7-2 are separately identified in Table TS 4.1-1.
The change would eliminate the two areas of confusion.
SIGNIFICANT HAZARDS EVALUATION Exhibit C contains the cross reference of FSAR Table 7.7-2 Instruments to its location in the Technical Specification.
Exhibit C items #12, 13 & 14 are not instruments but are listed in the Technical Specification for their surveillance requirements.
As shown in this table, surveillance requirements are specified for all post accident monitoring instrumentation.
The proposed change is a purely administrative change to the Technical Specifications.
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Exhibit A,
- 7. Specification: Table TS.4.1-1 (pg 3 of 5) & (pg 4 of 5)
PROPOSED CHANGE The change will remove the words in the remarks column in Table TS 4.1-1 for items 18a, 18b, 33, 34 and 36.
REASON FOR CHANGE These remarks do not provide useful information and in some cases could be misleading. The references to the FSAR in the items 33, 34 & 36 remarks column are redundant. Most if not all the instrument Channels listed in this table originated because of a statement in the FSAR.
SIGNIFICANT HAZARDS EVALUATION The proposed change is a purely administrative change to the Technical Specifications.
8.
Specification: Steam Exclusion System TS 4.8.C PROPOSED CHANGE In the second papagraph on TS.4.8-2, replace the words "at each reactor refueling shutdown" with the words "once each year".
REASON FOR CHANGF; To clarify the technical specifications so there is no confusion as to when and how of ten the test is performed.
SIGNIFICANT HAZARDS EVALUATION The system is common to both units since it affects the Auxiliary Building Ventilation System which is common to both units.
The Steam Exclusion System is not classified as a Unit 1 or a Unit 2 system.
Consequently, the requirement to test the system twice a year by doing it at each reactor refueling should not be necessary.
The safety concern is to assure the dampers are checked at least once during a refueling or at a yearly interval. This concern is still being fulfilled by the yearly inspection interval.
The proposed change is therefore purely administrative.
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e EXHIBIT B l
License Amendment Request Dated July 1, 1983 Exhibit B, attached, consists of the following revised pages of the Appendix A Technical Specifications which incorporate the proposed changes.
Pages TS.3.6-3A TS.3.6-6 TS.3.10-9 Table TS.3.12-1 (Pg 7 of 8)
TS.3.13-1 TS.3.13-1A (new page)
TS.3.13-2 Table TS.4.1-1 (Pg 3 of 5)
Table TS.4.1-1 (Pg 4 of 5)
Table TS.4-1-1 (Pg 5 of 5)
TS.4.4-5 TS.4.4-5A (new page)
TS.4.8-2
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