ML20126G024

Responds to FOIA Request for Seven Specified Documents & Encls.Forwards App Documents.Documents Also Available in PDR

ML20126G024
Person / Time
Site:	Salem
Issue date:	12/04/1984
From:	Felton J NRC OFFICE OF ADMINISTRATION (ADM)
To:	Graber L NUS CORP.
Shared Package
ML20126G027	List: IA-84-843, Safety Evaluation Supporting Amend 25 to License DPR-75 ML20126G024 ML20126G049 ML20126G055
References
FOIA-84-843 NUDOCS 8506180041
Download: ML20126G024 (2)

Text

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,. g UNITED STATES

- o NUCLEAR REGULATORY COMMISSION Q j WASHINGTON, D. C. 20555

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OE004 8 Mr. Lyle Graber Licensing Engineer Licensing Information Service NUS Corporation 2536 Count.ryside Boulevard IN RESPONSE REFER Clearwater, FL 33515-2094 TO F01A-84-843

Dear Mr. Graber:

This is in response to your letter dated October 29, 1984, in which you requested, pursuant to the Freedom of Information Act, that seven specified documents and enclosures be placed in the Public Document Roon (PDR).

The subject documents, as identified on the enclosed appendix, are being placed in the PDR,1717 H Street, NW, Washington, DC 20555, for your inspection and copying. The records will be filed in folder F01A-84-843 under your name.

Sin rely,

. M. Felton, Director Division of Rules and Records Office of Administration

Enclosure:

As stated M

8506180041 841204 PDR FDIA GRABER84-843 PDR

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Re: FOIA-84-843 EPENDIX ITEM 1. 8/30/84 Letter to J. J. Carey from Steven A. Varga re:

Beaver Valley Power Station, Unit 1 - Request for Additional Information from some Requirements of Appendix R to 10 CFR Part 50 w/ enclosed Exemption and Notice of Exemption (17 pages)

ITEM 2. 8/30/84 Letter to Richard A. Uderitz from Donald Fischer re:

Amendment No. 25 to Facility Operating License No.

DPR-75 w/ enclosed Amendment No. 25 to DPR-75 and Safety Evaluation (7 pages)

ITEM 3. 7/30/84 Letter to Harold R. Denton from J. G. Marshall re: LaSalle County Station Units 1 and 2 -

Baseline Inspection Report ASME Section XI Update, with Authorized Inspector Signatures w/ enclosure (100 pages)

ITEM 4. 8/1/84 Letter to C. W. Fay from James R. Miller re:

Technical Specification Changes w/ enclosed Request for Additional Information (4 pages)

ITEM 5. 7/26/84 Letter to J. W. Williams, Jr., from Steven A. Varga re: Pressurized Thermal Shock (PTS) Flux Reduction Program - Request for Additional Neutron Source Data, Turkey Point Units 3 and 4 w/ enclosure (5 pages)

ITEM 6. 8/8/84 Letter to J. J. Carey from Peter Tam re: Amendment No. 79 to Facility Operating License No. DPR-66 for Beaver Valley w/ enclosed Amendments No. 79 to DPR-66 and Safety Evaluation (9 pages)

ITEM 7. 8/14/84 Letter to J. W. Williams from Daniel G. Mcdonald, Jr., re: Amendment No.104 to Facility Operating License No. DPR-41 w/ enclosed Amendment No. 104 to DPR-31, Amendment No. 98 to DPR-41 and Safety Evaluation (31 pages) i

em Docket No. 50-334 DISTRUBT}0_N l dockptFila3 1 August 30, 1984 inu, FliR JNGrace LPDR TBarnhart 4 I[

Mr. J. J. Carey, Vice President ORB #1 Rdg ACRS 10 Nuclear Division Gray 4 CMiles Duquesne Light Company DEisenhut CMiles Post Office Box 4 ORAB RDiggs Shippingport, PA 15077 CParrish PTam

Dear Mr. Carey:

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SUBJECT:

BEAVER VALLEY POWER STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATIONS FROM SOME REQUIREMENTS OF APPENDIX R TO 10 CFR PART 50 By letter dated December 16, 1983, you requested additional exemptions from' the requirements of Appendix R to 10 CFR Part 50 for nine fire areas. By letter dated May 30, 1984 you provided additional infonnation. Prior to this request, the stoff has granted an Exemption dated March 14, 1983 for five fire areas. The nine exemptions you requested are in addition to those granted previously.

Based on our evaluation, we concluded that eight of the exemptions can be granted. The Exemption is enclosed, together with a copy of the Federal Register Notice.

The ninth request concerns structural steel. It is a generic issue and our review is ongoing. Therefore, we are deferring our action on that request.

Sincerely,

/s/SVarga Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing

Enclosures:

1. Exemption o

2. Notice of Exemption 3po cc w/ enclosures: .

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1 Mr. J. J. Carey Beaver Valley Power Station Duquesne Light Company Unit 1 cc: Mr. W. S. Lacey Mr. Thomas J. Czerpah Station Superintendent Mayor of the Burrough of Duquesne Light Company Shippingport Beaver Valley Power Station Post Office Box 26 Post Office Box 4 Shippingport, PA 15077 Shippingport, PA 15007 Pennsylvania Power Company Mr. K. Grada, Superintendent Ray E. Sempler of Licensing and Compliance One E. Washington Street Duquesne Light Company New Castle, PA 16103 Post.0ffice Box 4 Shippingport, PA 15077 Ohio Environmental Protection Agency Division of Planning Mr. John A. Levin Environmental Assessment Section Public Utility Comission Post Office Box 1049 Post Office Box 3265 Columbus, Ohio 43216 Harrisburg, PA 17120 Office of the Governor Gerald Charnoff, Esquire State of West Virginia Jay E. Silberg, Esquire - Charleston, West Virginia 25305 Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W. Charles A. Thomas, Esquire l Washington, DC 20036 . Thomas and Thomas 212 Locust Street i Karin Carter, Esquire Box 999 Special Assistant Attorney Gen 5ral Harrisburg, PA 17108 Bureau of Administrative Enforcement 5th Floor, Executive House Regional Radiation Representative Harrisburg, PA 17120 EPA Region III Curtis Building - 6th Floor Marvin Fein Philadelphia, PA 19106 Utility Counsel City of Pittsburgh Governor's Office of State Planning 313 City-County Building and Development Pittsburg, PA 15219 ATTN: Coordinator, Pennsylvania State Clearinghouse Resident Inspector Post Office Box 1323 U.S. Nuclear Regulatory Commission Harrisburg, PA 17120 Post Office Box 298 Shippingport, PA 15077 Mr. Joseph H. Mills, Acting Comissioner State of West Virginia Department Department of Environmental Resources of Labor ATTN: Director, Office of Radiolo- 1900 Washington Street gical Health East Charleston, West Virginia 25305 Post Office Box 2063 Harrisburg, PA 17105

. . . l Beaver Valley Power Station Unit 1 cc: N. H. Dyer, M.D. -

State Director of Health State Department of Health 1800 Washington Street, East Charleston, West Virginia 25305 Irwin A. Popowsky, Esquire Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 L

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UNITED STATES OF AMERICA ,

NUCLEAR REGULATORY COMMISSION

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In the Matter of Docket No. 50-334 DEQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY (Beaver Valley Power Station )

Unit No. 1)

EXEMPTION I.

The Duquesne Light Company, Ohio Edison Company and Pennsylvania Power -

l Company (the licensees), are the holder of Facility Operating License No.

DPR-66 which authorizes operation of the Beaver Valley Power Station, Unit No.

1 (the facility) at steady-state power levels not in, excess of 2652 megawatts thennal . The facility is a pressurized water reactor (PWR) located at the licensee's site in Beaver County, Pennsylvania. The license provides, among i

other things, that it is subject to all rules, regulations and Orders of the Nuclear Regulatory Comission (the Comission) now and hereafter in effect.

II.

On November 19, 1980, the Comission published a revised Section 10 CFR 50.48 and a new Appendix R to 10 CFR 50 regarding fire protection features of l nuclear power plants (45 FR 76602). The revised Section 50.48 and Appendix R  ;

became effective on February 17, 1981. Section III of Appendix R contains j l

fifteen subsections, lettered A through 0, each of which specifies requirements for a particular aspect of the fire protection features at a CC-L12_m '[$-l2 ff

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i nuclear power plant. One of those fifteen subsections, III.G, is the subject j of this exemption.

Subsection III.G specifies detailed requirements for fire protection of the equipment used for safe shutdown by means of separation and barriers -

(III.G.2). If the requirements for separation and barriers cannot be met in an area, alternative safe shutdown capability, independent of that area and equipment in that area is required (III.G.3).

In response to previous requests from the licensee, the Commission granted an exemption to requirements of Subsection III.G and III.L on March 14, 1983. By letter dated December 16, 1983 and supplemented by letter dated May 30, 1984, Duquesne Light Company requested additional exemptions from the requirements of Subsection III.G of Appendix R.

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III.

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We have reviewed the licenseh's exemption requests and evaluation of (

these requests is as follows: J.

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1. Fixed Suppression and Detection Systems .

For the following areas, an exemption is requested from Section III.G.3 to the extent it requires fixed suppression and detection to be provided throughout a fire area for which alternative shutdown has been provided:

Primary Auxiliary Building (PA-1 A), Elev. 768 Control Room HVAC Equipment Room (CR-2), Elev. 713 Emergency Switchgear Rooms (ES-1 & 2), Elev. 713 Process Instrument Room (CR-4), Elev. 713 Communications Equipment & Relay Panel Room (CR-3), Elev. 713 Normal Switchgear Room (NS-1), Eley. 713

Carbon Dioxide Storage /PG Pump Room (C0-2) l Pipe Tunnel (Sub-area QP-1), Elev. 735 With the exception of the Carbon Dioxide Storage /PG Pump Room (C0-2), all of these areas are provided with either partial or complete fire detection ~

systems. The carbon dioxide storage area is in a separate building adjacent ,

to the diesel generator buildings. A fire in this area would not threaten '

l safe-shutdown equipment.

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, All of the fire areas for which exemptions have been requested represent a similar configuration, i.e., combustible loading is light, there is alternate shutdown capability, detection (except CO 2storage area) and manual

fire suppression equipment is available. (The CO storage area contains only 2

equipment valves and cables in conduit._ It is in a separate building and a fire here would not threaten adjacent safety related areas.) The low combustible loading in these areas ensures that safety-related equipment in adjacent areas will not be threatened. The-installation of a fixed fire suppression system would not significantly increase the level of fire protec-tion in these areas.

Based on our evaluation, we find that the existing fire protection in j conjunction with alternate shutdown capability in the eight areas for which an exemption has been requested provides a level of fire protection equivalent to the technical requirements of Section III.G.3 of Appendix R and, therefore, the exemptions should be granted.

2. Control Room HVAC Equipment Room (CR-2) Elev. 713 An exemption is requested from Section III.G.2 to the extent it requires the separation of adjacent fire areas by 3-hour rated fire barriers.

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! The control room HVAC equipment room is separated from other areas by 3-hour rated fire barriers with the exception of a 1 1/2-hour rated fire door i

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which leads to the Relay Room (CR-3). The combustible loading in both areas (CR-3 and CR-2), if totally consumed, would correspond to an equivalent fire severity of approximately 40-50 minutes on the ASTM E-119 Standard Time-Temperature Curve. Smoke detection and manual fire suppression equipment-is provided in each area. Alternate shutdown capability is provided independent of the fire area.

The 1 1/2-hour rated fire door which leads to the relay room exceeds the combustible loading in both the HVAC equipment room and the relay room with considerable margin. In the event a fire occurred in either room, there is reasonable assurance that the installed smoke detection system would alarm and alert the fire brigade before the door's integrity is challenged. Replacing the existing door with a 3-hour rated assembly would not significantly enhance fire protection safety-Based on our evaluation, we find that the existing fire door in the HVAC equipment room (CR-2) provides a level of fire protection equivalent to the technical requirements of Section III.G. The exemption should, therefore, be granted.

3. Emergency Switchgear Rooms (ES-1 and ES-2) Elev. 713 An exemption is requested from Section III.G.2 to the extent it requires the separation of adjacent fire areas by 3-hour rated fire barriers.

The Emergency Switchgear Rooms are located on the 713, elev. beneath the cable spreading room. The ceiling which fonns a boundary between the two areas constitutes a 1 1/2-hour fire barrier. All other adjacent boundaries are 3-hour rated. The combustible loading in the emergency switchgear room, if totally consumed, would correspond to an equivalent fire severity of approximately 25 minutes on the ASTM E-119 Standard Time-Temperature Curve.

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8 Smoke detection and manual fire suppession equipment are provided in the area. The 1 1/2-hour rated ceiling exceeds the conibustible loading in the switchgear room with considerable margin. In the event a fire occurred, there is reasonable assurance that the installed smoke detection system would alam -

l and alert the fire brigade before the ceiling's integrity is challenged.

Replacing the existing ceiling with a 3-hour rated assemblies would not significantly enhance fire protection safety.

Based on our evaluation, we find that the protection provided for the emergency switchgear room ceiling provides a level of fire protection equivalent to the technical requirements of Section III.G. The exemption should, therefore, be granted.

4. Process Instrument Room (CR-4), Elev. 713 An exemption is requested from Section III.G.2 to the extent it requires the separation of adjacent fire areas by 3-hour rated fire barriers. i The process instrument room is. located on the 713 elev. beneath the cable

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spreading room. The ceiling which foms a barrier between the process instrument room and the cable spreading room is a 1 1/2-hour rated fire '

barrier. In addition, three doors which communicate to the adjacent relay room (CR-3) are 1 1/2-hour rated fire doors. All other boundaries are 3-hour rated.

The combustible loading in the area, if totally consumed, would correspond to an equivalent fire severity of approximately 45 minutes on the ASTM E-119 Standard Time-Temperature Curve. Smoke detection and manual fire suppression equipment are provided in the area. Alternate shutdown capability independent of the area is also provided.

The 1 1/2-hour rated fire doors which lead to the relay room and 1 1/2-hour rated ceiling exceed the combustible loading in both the process

l instrument room and the relay room with considerable margin. In the event a fire occurred in either room, there is reasonable assurance that the installed smoke detection system would alarm and alert the fire brigade before the door's or ceiling's integrity is challenged. Replacing the existing doors and-i ceiling with 3-hour rated assemblies would not significantly enhance fire protection safety.

Based on our evaluation, we conclude that the protection provided for the process instrument room provides a level of fire protection equivalent to the technical requirements of Section III.G. The exemption should, therefore, be granted.

5. Comunication Equipment & Relay Panel Room (CR-3) Elev.173 An exemption is requested from Section III.G.2 to the extent it requires the separation of adjacent fire areas by complete 3-hour rated barriers.

The comunications equipment and relay panel room is located on the 713' '

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elev. beneath the cable spreading reom. The ceiling that separates the relay room from the cable spreading room is a 1 1/2-hour rated fire barrier. In addition, two doors that comunicate with the adjacent process instrument room (CR-4) carry a 1 1/2-hour rating.

Smoke detection and manual fire suppression equipment are provided in the area. The combustible loading in the area, if totally consumed, would correspond to an equivalent fire severity of approximately fifty minutes on the the ASTM 2-119 Standar'd Time-temperature Curve. Alternate shutdown capability independent of the area is provided. ,

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i The 1 1/2-hour rated fire doors which lead to the process instrument room and the 1 1/2-hour rated ceiling exceed the combustible loading in both the process instrument room and the relay room with considerable margin. In the l 1

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event a fire occurred in either room, there is reasonable assurance that the installed smoke detection system would alam and alert the fire brigade before the door's integrity is challenged. Replacing the existing doors and ceiling with 3-hour rated assembies would not significantly enhance fire protection -

safety.

Based on our evaluation, we conclude that the protection provided for the Communications Equipment & Relay Panel Room provides a level of fire protection equivalent to the technical requirements of Section III.G. The exemption should, therefore, be granted.

6. Normal Switchgear Room NS-1 Elev. 713 An exemption is requested from Section III.G.2 to the extent it requires 1 the separation of adjacent fire areas by 3-hour rated barriers.

The nomal switchgear room is located on the 713 elev. of the service ,

l building, one floor below the cable spreading room. The nomal switchgear room is surrounded by 3-hour rated barriers with the exception of 1 1/2-hour 1 ..

l rated fire dampers installed in the ductwork that penetrates the cable spreading room. 5

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f Smoke. detection and manual fire suppression equipment are provided in the i

l area. The combustible loading in the area, if totally consumed, would correspond to an equivalent fire severity of approximately 50 minutes on the

! ASTM E-119 Standard Time-Temperature Curve. Alternate shutdown capability

independent of the area is provided.

The 1 1/2-hour rated fire dampers which lead to the cable spreading ~ room I exceed the combustible loading in the nomal switchgear room with considerable

} margin. In the event a fire occurred in the switchgear room, there is reasonable assurance that the installed smoke detection system would alam and l: alert the fire brigade before the dampers' integrity is challenged. Replacing r

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the existing dampers with 3-hour rated assemblies would not significantly i enhance fire protection safety.

l l Based on our evaluation, we conclude that the protection provided for the nonnal switchgear room provides a level of fire protection equivalent to the -

technical requirements of Section III.G. The exemption should, therefore, be granted.

I 7. Cable Spreading Room An exemption is requested' from Section III.G.2 to the extent it requires the separation of adjacent fire areas by complete 3-hour rated barriers.

The cable spreading room is located on the 725'6" elev. of the service building. The walls and ceilings constitute 3-hour rated barriers. The floor-is a 1 1/2-hour rated floor. Ductwork is provided with 3-hour rated dampers

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except those ducts which penetrate the floor and the west wall which separates

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the cable spreading room from the normal switchgear room. These ducts are ,

provided with 1 1/2-hour rated dampers. All cables and equipment needed for safe-shutdown will be removed from the nonnal switchgear room and relocated at

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the next refueling outage. The cable spreading room doors are 3-hour rated 1

( except for the 1 1/2-hour rated door that opens to the east stairtower.

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The combustible loading in the cable s,nreading room, if totally consumed, l would correspond to an equivalent fire severity of approximately 1-hour and twenty, minutes .on the ASTM E-119 Standard Time-Temperature Curve. l l

l To approve fire area boundaries of less than a 3-hour rating, we need reasonable assurance that the proposed boundaries will exceed the in-situ fuel f load with margin. In the cable spreading room, the margin proposed is not considered adequate for the general case. However, in the three specific cases cited, we have evaluated the location and configuration of the 1 i

l l 1/2-hour rated components and consider them acceptable for the following reasons:

1 1/2-hour rated stairtower door - Section C.5.a of our guidelines recommends the use of 2-hour rated concrete stairtower enclosures with

• self-closing Class B (1 1/2-hour) fire doors. The licensee has provided this level of protection. We, therefore, find the 1 1/2-hour rated fire doors acceptable.

1 1/2-hour rated floor and 1 1/2-hour rated fire dampers in the floor. In

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the event of a fire in the cable spreading room, the heat from the fire would rise and challenge the ceiling and upper wall areas of the cable spreading room. Only after a considerable time period will the heat transfer down through the floor become significant. With the added benefit of the installed smoke detection system, automatic suppression system and response of the fire brigade, there is reasonable assurance }

that the 1 1/2-hour rated flook and dampers will remain functional.

1 1/2-hour rated dampers penetrating the wall to the normal switchgear room. The licensee has comitted to remove all cables and equipment from the nonnal switchgear room needed for safe-shutdown. Therefore, if a fire propagated to this area, by the failure of the 1 1/2-hour rated damper, no safe-shutdown equipment would be damaged. The walls of the nonnal switchgear room that separate it from the remainder of the plant are 3-hour rated barriers. Therefore, a cable spreading room fire which spreads to the switchgear room by failure of the 1 1/2-hour rated dampers will not spread beyond the nonnal switchgear room.

Based on our evaluation, we conclude that the protection provided for the cable spreading room provides a level of fire protection equivalent to the f

technical requirements of Section III.G. The exemption should, therefore, be granted. )

8. Reactor Containment RC-1 An exemption is requested from Section III.G. to the extent it requires -

the separation of redundant trains of the source range monitor within ,

containment by greater than 20 feet.

This fire area includes the entire area inside containment. The redundant trains of safe shutdown components in this area include the containment ventilation, pressurizer pressure controls, pressurizer power operated relief valves, pressurizer relief blocking valves, pressurizer heaters, steam generator level transmitters, pressurizer level transmitters, reactor coolant hot and cold leg temperature instrumentation, and associated cables. -

The combustible loading in this area consists of approximately 48,000 pounds of cable insulation, 265 gal'lons of lubricating oil for each of three reactor coolant pumps, and 200 pounds of charcoal in the containment air filter cubicles.

All cable insulation is qualified to a test comparable to IEEE Standard 383. The reactor coolant pumps are fitted with an oil collection system.

Smoke detection systems and water deluge systems are provided only in the cable penetration area and in the residual heat removal pump area. Portable fire extinguishers and manual hose stations are provided throughout the fire area.

We had previously approved an exemption for the separation of redundant equipment and cables inside containment. At our request, the licensee has added an additional channel of source range neutron detection. Due to the physical arrangement inside containment, separation of the redundant cables by l

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more than 20-feet is not possible. A minimim separation of approximately five feet is maintained. Each channel of neutron detection is in a separate conduit.

The protection for redundant trains of safe shutdown equipment inside -

containment does not meet the technical requirements of Section III.G because redundant power cables are not separated by at least 20 feet free of combustibles. Due to the configuration and location of the cables within the containment and to the restricted access of these sub-areas during plant operation, an exposure fire involving the accumulation of significant quantities of transient combustible materials is unlikely. Because there are only a few cables in these sub-areas and all cables inside containment are qualified to a test comparable to that of IEEE Standard 383 and routed in conduit, a fire of sufficient magnitude to damage redundant cables or components is also unlikely.

Based on the above evaluation,.the existing protection for the containment area provides a level of fire protection. equivalent to the technical requirements of Section III.G of Appendix R. Therefore, the exemption should be granted.

IV.

Accordingly, the Comission has determined that, pursuant to 10 CFR 50.12, an exemption is authorized by law and will not endanger life or

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property of comon defense and security and is otherwise in the public interest and hereby grants an exemption from the requirements of Subsections III.G of Appendix R to 10 CFR 50 to the extent that it requires fixed suppession and detection systems, 3-hour rated fire barriers or 20-foot i

separation of, redundant equipment for the areas / equipment described above.

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Pursuant to 10 CFR 51.32, the Commission has determined that the issuance of the Exemption wil.1 have no significant impact on the environment (49 FR 32135).

FOR THE NUCLEAR REGULATORY COMMISSION .

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, Gus C. Lainas, Acting Director Division of Licensing Dated at Bethesda, Maryland this 30th day of August 1984 J.

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7590-01 UNITED STATES NUCLEAR REGULATORY COMISSION DOCKET NO. 50-334 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSLYVANIA POWER COMPANY NOTICE OF EXEMPTION FROM APPENDIX R TO 10 CFR 50 FIRE PROTECTION REQUIREMENTS The U. S. Nuclear Regulatory Comission (the Commission) has granted an Exemption from certain requirements of Appendix R to 10 CFR 50 to Duquesne Light Company, Ohio Edison Company and_ Pennsylvania Power Company (the licensees). The Exemption relates to the Fire Protection Program for the Beaver Valley Power Station, Unit No.1 (the facility) located in Beaver County, Pennslyvania. The Exemption is effective as of The Exemption waives certain requirements of Subsection III.G for this facility, to the extent that fixed fire suppression and detection systems need not be provided for certain fire areas, 3-hour rated fire barriers need not be installed between certain fire areas, and 20-feet separation is not required between certain pieces of equipment. The Exemption is granted mainly on the i

basis that the combustible loading in all these areas are light. Details are provided in the Exemption, j

The request for Exemption complies with the standards and requirements of

the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR which are set forth in the Exemption. 2 D

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7590-01 Pursuant to 10 CFR 51.32, the Commission has determined that the issuance of the Exemption will have rc_- significant impact on the environment (49 FR 32135).

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ForfErtherdetailswithrespecttothisaction,see(1)theapplication-for Exemption dated December 16, 1983 and supplemented by letter dated May 30, 1984, (2) the Commission's letter dated August 30, 1984 and (3) the Exemption.

All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D.C. and at the B. F.

Jones Memorial Library, 663 Franklin Avenue, Aliquippa, Pennsylvania 15001. A copy of items (2) and (3) may be obtained upon request addressed to the U. S.

Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Director, Division of Licensing. .

Dated at Bethesda, Maryland, this August 30 , 1984.

F0 - E NUCLEAR REGULATORY C009tISSION (A O Gus C. Lainas, Acting Director Division of Licensing e

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? Cf Docket No. 50-311 DISTRIfWTION an d e + " l => TBarnhart 4 August 30, 1984 NRC PDR RDiggs L PDR WJones Mr. Richard A. Uderitz, Vice President - Gray File 4 JNGrace Nuclear ORB #1 Rdg DBrinkman Public Service Electric and Gas Company CParrish CMiles l

Post Office Box 236 DFischer EJordan ,

Hancocks Bridge, New Jersey 08038 DEisenhut RFerguson l OELD LHannon

Dear Mr. Uderitz:

ACRS 10 The Connission has issued the enclosed Amendment No. 25 to Facility Operating License No. DPR-75 for the Salem Nuclear Generating Station, Unit No. 2. This amendment adds two new license conditions in response to your request dated June 30, 1983.

The amendment consists of the addition of License Conditions which ensure the implementation of 10 CFR 50 Appendix R fire protection modifications on Unit No. 2.

A copy of the Safety Evaluation is enclosed. A Notice of Issuance will be included in the Connission's next regular monthly Federal Register notice.

. Sincerely, Donald Fischer, Project Manager .

Operating Reactors Branch #1 Division of Licensing

Enclosures:

1. Amendment No. 25 to DPR-75

2. Safety Evaluation {

I cc: w/ enclosures l See next page .

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!b Mr. R. A. Uderitz Salem Nuclear Generating Station i V;.j -

Public Service Electric & Gas Company Units 1 and 2 l

cc: Mark J. Wetterhahn, Esquire Regional Radiation Representative Conner and Wetterhahn EPA Region II

' Suite 1050 26 Federal Plaza 1747 Pennsylvania Avenue, NW New York, New York 10007 .

, Washington, DC 20006 Mr. R. L. Mitti, General Manager Richard Fryling, Jr. , Esquire Nuclear Assurance and Regulation i Assistant General Solicitor Public Service Electric & Gas Co.

i~ Public Service Electric & Gas Company Mail Code T160 - P. O. Box 570 P. G. Box 570 - Mail Code T5E Newark, New Jersey 07101

Newark, New Jersey 07101 Regional Administrator, Region I Gene Fisher, Bureau of Chief U.S. Nuclear Regulatory Consnission Bureau of Radiation Protection 631 Park Avenue

, 380 Scotch Road King of Prussia, PA 19406

{ Trenton, tiew Jersey 08628 Lower Alloways Creek Township -

!. Mr. John M. Zupko, Jr. c/o Mary O. Henderson, Clerk .

General Manager - Salem Operations -

Municipal Building, P.O. Box 157

, Public Service Electric & Gas Company Hancock Bridge, NJ 08038

Post Office Box E l A Hancock Bridge, New Jersey 08038 Mr. Alfred C. Coleman, Jr.-

i* Mrs. Eleanor G. Coleman i

! Mr.. Dale Bridenbaugh -

35'K Drive .

M.H.B. Technical Associates Pennsville, New Jersey 08070.

I 1723 Hamilton Avenue .,

! San Jose, California 95125 -

Carl Valore, Jr. , Esquire i

j Vakre, McAllister, Aron Jame,s, Linville, Resident Inspector and Westmoreland, P.A.

3 Salem Nuclear Generating Station 535 Tilton Road i U.S. Nuclear Regulatory Comission Northfield, NJ 08225 l Drawer I

Hancock Bridge, New Jersey 08038 June D. MacArtor, Esquire i

Deputy Attorney General l Richard F. Engel Tatnall Building Deputy Attorney General Post Office Box 1401 Department of Law and Public Safety Dover, Delaware 19901 CH-112 State House Annex Harry M. 'Coleman, Mayor i

Trenton, New Jersey 08625 Lower Alloways Creek Township l Municipal Hall l l Richard B. McGlynn, Comittion Hancock Bridge, New Jersey 08038 4 Department of Public Utilities State of New Jersey 101 Consnerce Street . . -- - -

Newark, New Jersey 07102 g+ -

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.NT;) . Salem Nuclear Generating Station Units 1 and 2

- 2-cc: Mr. Edwin A. Liden, Manager .

Nuclear Licensing & Regulation ,

Public Service Electric & Gas Company

. Post Office Box 236 .

Hancock Bridge, New Jersey 08038 Mr. Charles P. . Johnson .

Assistant to Vice President, Nuclear Public Service Electric & Gas Company Post Office Box 570 80 Park Plaza - 15A

• Newark, New Jersey 07101 Mr. David Wersan ,

Assistant Consumer Advocate Office of Consumer Advocate *

• 1425 Strawberry Square .,

Harrisburg, PA 17120 ,

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