ML20079E373
| ML20079E373 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/26/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079E374 | List: |
| References | |
| 7590, 7590-01, 7590-1, NUDOCS 9110070136 | |
| Download: ML20079E373 (4) | |
Text
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.EF,VJ fphpEp,T,A,l,,A,5,5f,5,ST,Ep,T,,A t p, f)pp) pp, pf, pp,,5j p!1)f J,C,AFL I MP ACT The U.S. fluclear Regulatory Commission (the Conriission) is considering issuance of an exemption from certain requirements of 10 CFR Part 50, Appendix R.
Section 111.G and Section 111.M for the Peach Bottom Atomic Power Station, Units 2 and 3, located at the licensee's site in York County, Pennsylvania.
E NV I R0tWE N,T,AL,,A5S.ES,Spf N,T 33.ep,t,1,f,i,c,a,t,ipp, p,f,f,rpposed Action:
The licensee would be exenpted from the technical requirements of Section 111 C.2, Appencix R to 10 CFR Part 50 as follows:
1)totheextentibetthewallseparatingtheindividualTurbineBuilding Emergency Switchgear and Battery Rooms from each other and from an access corridor and two duct chases are constructed of concrete block with a fire resistance rating of only 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; L
- 2) to the extent that fire barriers between the access corridor on elevation l
l 135 feet of the Turbine building and the 12KV switchgear area on elevation 116 l
feet of the Turbine building consists, in part, of two duct chases in two 4KV t.
Emergency Switchgear Rooms, penetration fire stops and fire dampers within ducting inside the chase. The fire dampers and penetration stops are in different planes and different elevations. This configuration does not meet 9110070136.910926 PDR ADOCK 05000277 p
2 the requirements of Section Ill.G.E in that the intervening ducting between the fire dampers and penetration stops does not rett the required 3-hour fire rating; and 3)-to the extent that a 1/8-inch steel angle atop a 3-hour rated fire barrier between the Radwaste Centrifuge and Sample Tank Area and the Pemote Shutdown Fanel area cortpromises the fire protection capability of the 3-hour rated fire barrier.
The licensee would be exerrpted from the technical requirements of Section 111.M. Appendix R to 10 CFR part 50 as follows:
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-1) to the extent that electrical condait fire barrier penetration seals in approximately 1300 applications have not been tested in their ability to withstand a 3-hour fire; and
- 2) to the extent that seventeen normally energized 4KV bus ducts in the Turbine Building lack 3-bour rated penetration seals.
The exemption is in response to the licensee's request for NRC staff technical review and concurrence dated December 10, 1986.
The Need,for the Pr,op,0,s,e_d, A,c,t,i,0,n:
-The exemption from Section lil.G to allow present fire barrier configura-tions to not meet the specific 3-hour fire barrier rating is needed in order to preclude extensive plant modifications that do not significantly increase plant fire protection.
The exemption.from Section 111.M to allow present fire barrier cable conduits and 4KV bus ducting to not have 3-hour rated penetration seals is needed to avoid extensive penetration inodifications that do not significantly increase plant fire protection.
. l
_EPJ P9Pf.ep,t,a,1,,lo pa ct of the P rot osed Ac tions :
I The proposed exerption will provide a degree of fire protection that is equivalent to tFat recuired by Apterdix R for tre affected areas of the plants such that thete is ;o increase in the risk of fires at these facilities.
Consequently, the prcbability of fires has not betn increased and the post fire radiological releases will not be greater than previously dctermined, nor does the proposed exenption otherwise af fect radiological plant ef fluents.
Therefore, the Concission concludes that there is no significant radiological impacts associated with the proposed exemption.
With regard to potential non-radiological inipacts, the proposed exemption involves features located entirely within the restricted area as defined in 10 CFR Part 20.
It does not affect non-radiological plant effluents and has no other environnental impact. Therefore, the Commission concludes that there are no significant non-radiological environmental impacts associated with the proposed exemption.
A 1 t e r n a t i v 4,,t p,,t,b e, P,rpp,o,s e,d, A,c,t,ipp :
Since the Consnission has concluc.
' at there are no measurable
.nvironnental impacts associated with the proposed exemption, any alternatives with equal or greater environmental impact need not be evaluated.
The principal alternative to the exemption would be to require rigid compliance with the applicable portions of Section Ill.G and Section 111.M of the Appendix R requirements.
Such action would not enhance the protection of the environn,ent.
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.O Alternative Use of Pesources:
This action involves no use of resources not previously considered in the
" Final Environnertal Statenent for the reach Cottom Atomic Power Station, Units 2 and 3," dated April 1073.
.A !P.C.i.$..a n,d,,Pp,r,s,0,n,s,,C on s u 1 t e d :
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The Connission's staff reviewed the licensee's request and did not consult other ageraies or persons.
FlttDltlG OF tiO SIGt11FICAhi llTACT The Consnission has determined not to prepare an environnental in1 pact statenient for the proposed exemption.
Based upnn the foregoirig environmental assessnent, the Consnission concludes that the proposed action will not have a significant effect on the quality of the human environment.
For further details with respect to this action, see the licensee's request for NRC staff review dated December 10, 1986, which is available for public inspection at the Consnission's Public Document Room,1717 H Street, it.W.,
Washington, D.C. and at the Government Publications Section, State Library of Pennsylvania, (Regional Depository) Education Building, Walnut Street and Commonwealth Avenue, Box 1601, Harrisburg, Pennsylvania 17105.
Dated at Roc 6ville, Maryland, this 26th day of September 1991.
FOR THE ttVCLEAR REGULATORY COMMISION (L
Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of fluclear Reactor Regulation