ML20113C368
| ML20113C368 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/18/1996 |
| From: | Olshan L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20113C372 | List: |
| References | |
| NUDOCS 9607010171 | |
| Download: ML20113C368 (8) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION PUBLIC SERVICE ELECTRIC AND GAS COMPANY DOCKET NOS. 50-272 AND 50-311
@TICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is.considering issuance of an amendment to Facility Operating License Nos. DPR-70 and DPR-75 issued to Public Service Electric & Gas Company (the licensee) for operation of Salem Nuclear Generating Station, Units 1 and 2, located in Salem County, New Jersey.
The proposed amendments would revise Technical Specification 3/4.7.6,
" Control Room Emergency Air Conditioning System (CREACS]," to reflect a control room design in which the common Salem Unit I and Unit 2 control room envelope is supplied by 2 one-hundred percent capable Control Room Emergency Air Conditioning System trains.
Before issuance cf the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
The Commission has made a proposed determination that the amendment request involves no significant hazards consideration.
Under the Commission's
.i regulations in 10 CFR 50.92, this means that operation of the fac'lity in i
accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of 9607010171 960618 PDR ADOCK 05000272 P
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l accidant from any accident previously evaluated; or (3) involve a significant 4
reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards i
consideration, which is presented below:
i 1.
The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
CREACS ensures adequate protection after an accident and is not an accident initiator. The changes to the emergency operating mode and configuration of the CREACS, while modifying the control room dose assessment, do not affect the probability of an accident.
1 The proposed operation of the CREACS in the pressurization mode at the initiation of an accident will reduce overall operator doses from such an event and will ensure that the requirements of General Design Criterion (GDC) 19 will be met.
Operation in the recirculation mode to mitigate the consequences of a fire or a toxic release, if necessary, or as a compensatory measure when receiving ammonium hydroxide does not significantly increase the J
consequences of other accidents due to the short duration of these events, the ability to re-align the system to the pressurization mode manually, and the suspension of Core Alterations or fuel j
movement.
The CREACS as modified satisfies [ technical specification] TS 4
Bases 3.7.6.
The CREACS ensures that (1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for equipment and instrumentation cooled by the CREACS and (2) the Control Room will remain habitable for operations personnel during and following all credible accident conditions.
4 The proposed changes reflect the commonality of the Salem Unit 1 and Unit 2 [ common room envelope] CRE and the supporting CREACS trains by adopting the guidance for required actions, allowed outage times, and testing provided in the (Standard Technical Specification) STS.
Therefore, the proposed TS change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
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I The establishment of the CREACS as a shared system for both Units 1 and 2 will not result in a new accident release scenario.
The upgraded CREACS reflected by this submittal revises the emergency operating mode from the original recirculation mode to a pressurization mode in the event of a radiological emergency.
This change in CREACS operating philosophy is in support of compliance with the limits of GDC 19. Modifications to the Salem control rooms regarding the controlled atmospheric boundary configuration and how the configuration is maintained cannot 6
result in new accident scenarios.
Therefore, the proposed TS change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
The proposed change does not involve a significant reduction in a margin of safety.
The proposed changes support modifications to the CREACS as part of corrective actions identified in Licensee Event Reports with the intent of compliance with General Design Criterion 19 limits.
The changes do no[t] impact the existing safety analyses while retaining and meeting current requirements and General Design Criteria limitations and gaining a redundancy in the affected system. The modified CREACS meets the TS Bases 3.7.6 requirements.
CREACS ensures that (1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for equipment and instrumentation cooled by the CREACS and l
(2) the Control Room will remain habitable for operations personnel during and following all credible accident conditions.
This clarification of the CREACS operability requirements and the application of more conservative requirements to Unit I will i
result in a net increase to operator safety.
Therefore, the proposed TS change does not involve a significant reduction in the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied.
Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination.
1.
Normally, the Commission will not issue the amendment until the expiration of the 30-day notice period. However, should circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 30-day notice l
period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider l
all public and State comments received. Should the Commission take this l
action, it will publish in the FEDERAL REGISTER a notice of issuance and provide for opportunity for a hearing after issuance.
The Commission expects th4t the need to take this action will occur very infrequently.
Written comments may be submitted by mail to the Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written comments may also be delivered to Room 6022, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays.
Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Buildi~ng, 2120 L Street, NW., Washington, DC.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By July 24, 1996
, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and
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. a who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene.
Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
Interested persons should consult a current copy of 10 CFR 2.714 which is available at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, and at the local public 1
document room located at the Salem Free Public Library, 112 West Broadway, Salem, New Jersey.
If a request for a hearing or petition for leave to 4
intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chairman of the Atomic i
Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding.
The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors:
(1) the nature of the petitioner's right under the Act to be made party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest.
The petition a
should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has e
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4 filed a petition for leave to intervene or who has been admitted as a party l
may amend the petition without requesting leave of the Board up to 15 days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than 15 days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter.
Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted.
In addition, the petitioner shall provide a brief explanation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide t
references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion.
Petitioner must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact.
Contentions shall be limited to matters within the scope of the amendment under consideration.
The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one i
contention will not.be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the l
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opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held.
If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment.
If the final determination is that the amendment request involves a
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significant hazards consideration, any hearing held would take place before the issuance of any amendment.
A request for a hearing or a petition for leave to intervene must be 1
l filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Docketing and Services Branch, or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L. Street, NW., Washington, DC, by the above date. Where petitions are filed during the last 10 days of the notice period, it is requested that the petitioner promptly so inform the Commission by a toll-free i
telephone call to Western Union at 1-(800) 248-5100 (in Missouri 1-(800) 342-6700).
The Western Union operator should be given Datagram Identification j
Number N1023 and the following message addressed to John F. Stolz:
petitioner's name and telephone number, date petition was mailed, plant name, and publication date and page number of this FEDERAL REGISTER notice. A copy 1
of the petition should also be sent to the Office of the General Counsel, U.S.
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1 Nuclear Regulatory Commission, Washington, DC 20555-0001, and to Mark J.
Wetterhahn, Esquire, Winston and Strawn, 1400 L Street, NW., Washington, DC 20005-3502, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be J
entertained absent a determination by the Commission, the presiding officer or i
the presiding Atomic Safety and Licensing Board that the petition and/or i
request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendment dated June 10, 1996, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, and at the local public document room located at the Salem Free Public Library, 112 West Broadway, Salem, New Jersey.
Dated at Rockville, Maryland, this 18th day of June 1996.
FOR THE NUCLEAR REGULATORY COMMISSION hJa'h,,/
Leonard N. Olshan, Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i