ML20138D348

Application for Amends to Licenses DPR-42 & DPR-60,adding TS Requirements for Addl Fire Protection & Detection Equipment Installed in New Bldg Which Houses Two New Safeguards EDGs & Associated Equipment

ML20138D348
Person / Time
Site:	Prairie Island
Issue date:	02/10/1993
From:	Parker T NORTHERN STATES POWER CO.
To:
Shared Package
ML20138D331	List: ML20138D327 ML20138D348 ML20138D352
References
NUDOCS 9302170266
Download: ML20138D348 (7)

Text

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, e 3 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLWD NUCLEAR CENERATING PLMIT DOCKET NO. 50 282' 50 306 REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR 42. & DPR 60 LICENSE AMENDMENT REQUEST DATED February 10, 1993 Northern States Power Company, a Minnesota corporatico, requests authorization fo; changes to Appendix A of the Prairie Island Operating Licenso as shown on the attaclunents labeled Exhibits A, B, and C. Exhibit A describes the proposed changes, reasons for the changes, and a significant hazards eval- ,

uation. Exhibit B contains current Prairie Island Technical Specf fication pages marked up to show the proposed changes. Exhibit C contains the revised Technical Specification pages.

This letter contains no restricted or other defense informatton.

NORTHERN STATES P.W COMPANY

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By hh

'Th,o)masMlParkerQ, . , _

Director of Licensfag Nuclear Generation on this]_O_ day of Aqp, / lbefore me a notary public in and for said i

County, persona H y appeared Iho as M Parker, Director of' Licensing,. Nuclear.-

L Ceneration, and being first duly rworn acknowledged that he is-authorized to L execute this document on behalf of_ Northern States Power Company, that he ,

i knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are trua and that it it, not-interposed for delay.

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Exhibit A i I

Prairie Island Nuclesr Generating Plant License Amendment Request Pated February 10, 1993-Evaluation of Proposed Changes to.the Technical Specifications Appendix _A of' Operating License DPR-42 and DPR-60 ,

i Pursuane to 10 CFR Parc 50, Sections 50.59 and 50.90,'the holders of Operating ,

Licenses DPR-42 and DPR-60 hereby propose the following changec to Appendix A, '

Technical Specifications:

1. Add New Spray and. Sprinkler Areas, New Building to Be Protected by Yard.

Hydrant- Hose 11ouses and Modify the List of Fire Deteg.g.lon Instry m _ .

Proposed Channga Add the D5 Diesel Gene;ator Area PA-12 and D6' Diesel Generator Area PA-13 l to the list in TS.3.14.C.1. as areas requiring OPERABLE spray and -  ;

sprinkler systems whenever the equipment protected by these cystema isi required.to be OPERABLE. .In addition, redesignate Diesel Generator Areas '

PA-1 as D1 and D2 -Diesel Generator Areas PA-1.

Add the D5/D6 Building as a building which requires protection from an

- OPERABLE yard hydrant hose house whenever equipment in the:05/D6 Building is required to be OPERABLE. ,

The list (TABLE TS.3.14-1) of fire detecdion instruments , and their -

OPERABILITY requirements are being~ revised to include the new rooms and q their associated detectors and to reflect the changes in room designations of some of the existing rooms,

. Egasons for Chance.a_end safety Evaluation M'

As part- of a project which will bring'the . plant into compliance with IO

-CFR Part 50, Section 50.63 (the Station Blackout Rulo),-two-additional:

safety emergency diesel generators, associated diesel generator supportL equipment, associated electrical distribution system equipment, and a v4w building _(D5/D6 Building) to house the new equipment are being added to-the plant. This . equipment; requires firo protection similar' to that . .

requited for other safety-related ' equipment In the plant. Fire' protection provisions have been provided as described in- the SB0/ESU Project Design

< Report Rev. 1' submitted by letter. dated December 23. 1991 from .

7 M Parker, Northern Stater Powerf Company to U S Nuclear Regulatory Commisalon titled " Design Report for the Station Blackout / Electrical ~

Safeguards Upgrade: Project". The croposed changes to the Technical

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Specifications provide OPE 9 ABILITY requirenents for ;the fire-protection. ,

equxpment dedicated to the new safety related structures and equipment. .

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Exhibit A Page 2 of 6 ,

I The requirements for the existing fire protection provisions remain-unchanged and the proposed requirements for the ,,ow fire protection  ;

provisions are consistent with the existing except that the proposed '

l minimum number of OPERAB1.E fire detection instruments is higher than the existing plant areas.

Therefore, NSP believes that there is reasonable assurance that- the health-  !

4 and safety of the public will not be adversely affected by the proposed Technical Specification changes.

Determination of Sirnificant llazards Considerations The proposed changes to the Operating License have been evaluated to ,

determine whether they constitute a significant hazards consideration as-required by 10 CPR Part 50, Section 50.91 using the standards provided in Section 50.92. This analysis is provided below: -

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1. The proposed amendment will not involve a significant increase in the orobability or consecuences of an accident previous 1v evaluated.

Adding Technical Specification requirements for fire detection and

, protection functions for the new structures and equipment provides additional assurance that required structures and equipment will properly function.

changing the designations of existing spray and sprinkler areas and i existing fire detection zones are merely editorial ~ changes which cause no change in the way in which the plant ca ' operated or maintained.

Therefore, these changes will have no offect on the probability or consequences of an accident previously evaluated.

2. The proposed amendment vill not_ create the possibility of a new or different_ Find of accident from eny accident previous 1v analyzed.  ;

As starod above, the proposed changes provide additional assurance that required structures and equipment will. properly function.

Therefore, these changes will not create the possibility of a new or -

different kind of accident from any accident previously analyzed.

3. .ne proposed amendment will not involve a significant reduction in'the EaEEin Ef_fafetv- 4 As stated!above, the proposed changes provide additional assurance.that required structures and equipment.will properly function.

Therefore, these changes will not involve a si6 nificant reduction in the margin of safety.

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.. V e s Exhibit A Page 3 of 6 Based on'the evaluation described above, and pursuant to.10 CFR Part 50, Section 50.91, Northern States Power Compaay han determined that operation of the Prairie Island Nuclear Cencrating-Plant in accordance with-the proposed license amendment request does not involve:any significant:

hazards considerations as defined by NRC regulations in 10 CPR Part 50, Section 50.92.

Environmental Assessment i

Northern States Power has evaluated the proposed changes and determined  ;

that: ,

1. The changes do not involve a significant hazards consideration. ~!

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2. The_ changes _ do not involve a significant change in the types or -

j significant increase in the amounts of any effluents that may be~ j released offsite, or

3. The changes do not involve a sigr.ificant increase in individua17or.

cumulative occupational radiation exposure.

l Accordingly, the proposed changes meet the eligibility criterion' for. ,

categorical exclusion set forth in 10 CFR Part 51 Section 51.22 (c)(9).

Therefore, pursuant to 10 CFR Part 51 Section 51.22(b), an environmental '

assessment of the proposed changes is not required.

2. - Fire Detection Instrumentation Surveillance Reautrementa - ,

Proposed Changes ,

Change the words in the first sentence contained in Technical .

Specification 4.16.A.1, -i from: l The minimum number of fire detectors required ~in each zone.

specified in Table TS.3.14-1 shall be functionally teated once ,

every six months.

I to:

The minimum number of lon and flame _ fire _ detectors required in each-zone specified-in' Table:TS.3.14 1_'shall be functionally tested once every six months, axceptcthat, for ion detectors that are addressable from a~ dedicated con;rol panel,Ethe proper le sensitiv1ry shall'be verified quarterly;with the minimum number of addressable fire detectors 'specified iti Table _TS.3.14 1:  ;

functionally tested-once overy two years. -

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Exhibit A  ;

Page 4 of 6' .. i and add the sentence: i A minimwn of 20% of the restorable thermal detectors will be f

- tested on an annual schedule with all thermal detectors tested l at least~once per 5 years.

Revise specification-basis 4.16 to describe two configurations for. ion-- ,

fire detectors and provide.the basia_for the dlffering surv;'11ance  :

requirements for the two configurations. '

Erasons for channes and saferv EvalwLtinn In order to provide assurance of OPERABILITY-of the new fire detection l instruments, surveillance requirements are proposed,  !

1 The ion detectora'which are being utilized in'the D5/D6'Buildin5 differ:

• irom those 5thich previously have been used in the plant in that the new; ones are addressable by a dedicated control panel. An addressabic  !

detector allows for a more frequent check of sensitivity yhich is generally more informative than a functional test. Therefore, the proposed surveillance' requirements for the addressable ion detectors are intended to take advantage of the capabilities of the dedicated control' panel, and a more frequent detector check is proposed.

In' addition., new surveillance requirements are being proposed for flame.

and restorable thermal detectors. Previously, there were no flame'or- '

thermal. detectors among th'e fire. detectors: required.to be OPERABLE,: and so .

there were no surveillance requirements established. .There vill be flame 4

and thermal detectors in che DS/D6 Building which are requ2 redi to be ,

OPERABLE, so that surveillance requirements for these detectors are .

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-In all cases the surveillance frequencies proposed are equal to or exceco the manufacturers' recommendations.

• Therefore, NSP believes' that there is reasonable assurance thAt the health- .j and ~ safety of the public will not be adversely affected by the proposed TS '

changes.

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- u patinplar}ilon of Sign [ficant Hazards 'considerationg O i

The proposed changes / to the' Operating Licenre have been evaluated to . ]

determine whether they constitute a significant nazards consideration-as' required by 10 CFR Part 50, Section 50.91 using the standards .provided in Section 50,92; This analysis is providet below:

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Exhibit A j Pese 5 of 6 .

1. The' proposed amendment will not involve a significant increase in the i orobability or consecuences of an accident previousiv-evaluated. l t

t Providing surveillance requirements for fire detection instruments associated with the new structures and equirment provides additional '

assurance that required structures and equipment will properly -i I

function.

Therefore, these changes will have no significant increase in the ,

probability or consequences of an accident previously evaluated. *

2. The proposed amendment will not create the possibility of a.new or different kind of accident from any accident oreviousiv analvred.__

As stated above, the proposed changes provide additional assurance that :i required structures and equipment will properly function.  ;

Therefore, these changes will not create-the possibility of a new or different kind of accident from any accident previously analyzed. 3

3. The proposed amendment will not involve a significant reduction.in the margin of safety.

As stated above, the proposed changes provide additional assurance that required structures and equipment will properly function.

Therefore these cl.anges will not involve a significant reduction in the margin of safety. -

Based on the evaluation described above, and pursuant to 10 CFR Part 50.-

Section 50.91, Northern States Power Company has determined that operation-of the Prairie _ Island Nuclear Cenerating Plant in accordance with the.

proposed license amendment request does not involve any significant?

L hazards considerations as defined by NRC regulations- in.10 CFR Part 50, ,

Section 50.92.

Environmenta1' Assessment Northern States Power has evaluated the proposed changes and determined 1 that:

- 11. The changes do not involve a significant hazards consideration,.

2. The changes do not involve a significant' change in the types or

- significant increase in the amounts of any effluents that-may be '

released offsite, or j

3. The changes do not involve a significant increase in individual or cumulative' occupational radiation? exposure..

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Exhibit A ,

Page 6 of ) . >

Accordingly, the proposed changes meet the eligibility criterion for categorical exclusion set forth in 10 CFR Part 51 Section 51.22 (c)(9). ,

Therefore, pursuant to 10 CFR Part 51 Section 51.22(b), an environmental l assessment of the proposed changes is not required.

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