ML17157B987
| ML17157B987 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/26/1992 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157B988 | List: |
| References | |
| NUDOCS 9209030247 | |
| Download: ML17157B987 (10) | |
Text
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION
'P NNSYLVA IA POWER AND LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NOS. 50-38 AND 50-388 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDM NTS TO FACILITY OPERATING LICENSE PROPOSED NO SIGNIFICANT HAZARDS
- CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to Facility Operating License Nos.
NPF-14 and NPF-22 issued to Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc. (the licensees) for operation of the Susquehanna Steam Electric Station (SSES),
Units 1 and 2, located in Salem Township, Pennsylvania.
The proposed amendments would make changes to the technical specifications to prevent inadvertent isolation of the Reactor Water Cleanup (RWCU) system due to high seasonal temperatures while still providing timely leak detection capability.
Before issuance of 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 regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously 920'9030247'920826~
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evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant 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 consideration, which is presented below:
NO SIGNIFICANT HAZARDS CONSIDERATION The proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated.
The SSES FSAR does not analyze the size of the small leak on which the, temperature setpoints are based.
Other accidents which result in coolant leakage outside containment are analyzed in FSAR Sections 15.6.2 (Instrument Line Break) and 15.6.4 (Steam System Piping Break Outside Containment).
Both of these are assumed accidents, with no causes identified.
The analysis in Section 15.6.4 is the enveloping evaluation for pipe breaks outside containment.
The proposed 25 gpm leakage rate basis is well below the leakage corresponding to a
catastrophic pipe failure for the applicable system piping and does not significantly increase the risk of a break.
The radiological consequences of a coolant leak outside primary containment was analyzed.
The analysis concludes that there is no impact on the 10 CFR 100 offsite dose limits or on the 10 CFR 50, Appendix A, GDC 19 control room dose limits.
Additionally, the temperature switches and isolation valves are redundant.
Failure of a single switch to detect a leak does not preclude detection and where appropriate, isolation by the other switch and valve.
The reliability of the temperature switches is not affected by the setpoint.
The other methods of leak detection provide backup for the temperature instruments.
The proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
The proposed technical specification change does not affect any systems other than leak detection and does not affect the ability to detect and isolate leakage.
Although a 25 gpm leak is not specifically analyzed in the FSAR, it is bounded by the analysis in Chapter 15.6.4.
The proposed change does not, therefore, create the possibility of an accident or malfunction of a different type than any evaluated previously in the FSAR.
III.
The proposed change does not involve a significant reduction in a margin of safety.
The temperature switches and setpoints are listed in Technical Specification Section 3.3.2, "Isolation Actuation Instrumentation,"
but the Technical Specification basis does not discuss setpoint basis with respect to leakage rate or process conditions.
The bases
- does, however, state "the setpoints... are established at a level away from the normal operating range to prevent inadvertent actuation of the system involved."
Temperature measurement is not discussed in the basis for Technical Specification 3.4.3, "Reactor Coolant System Leakage."
The proposed technical specification change satisfies the bases for Section 3.3.2 by defining that the setpoints margin above maximum design temperatures, but does not reduce any margin of safety defined for any Technical Specification.
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 thirty (30) days after the date of publication of this notice will be considered in making any final determination.
The Commission will not normally make a final determination unless it receives a
request for a hearing.
Written comments may be submitted by mail to the Rules and Directives Review Branch, Division of Freedom of Information and Publications
- Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC
- 20555, and should cite the publication date and page number of this FEDERAL REGISTER notice.
Written comments may also be delivered to Room P-223,
Phillips Building, 7920 Norfolk Avenue,
- Bethesda, 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 Building, 2120 L Street, NW., Washington, DC 20555.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By October 1,
1992
, 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 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, NM., Mashington, DC 20555 and at the local public document room located at Osterhout Free Library, Reference Department, 71 South Franklin Street, Wilkes-Barre, Pennsylvania 18701.
If a request for a hearing or petition for leave to 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 Safety and Licensing Board, 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 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 filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to fifteen (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 fifteen (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 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 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 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
significant hazards consideration, any hearing held would take place before the issuance of any amendment.
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
- period, provided that its final determination is that the amendment involves no significant hazards consideration.
The final determination will consider all public and State comments received.
Should the Commission take this action, it will publish in the FEDERAL REGISTER a notice of issuance and provide for opportunity for a hearing after issuance.
The Commission expects that the need to take this action will occur very infrequently.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S; Nuclear Regulatory Commission, Washington, DC 20555, 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
- 20555, by the above date.
Where petitions are filed during the last ten (10) days of the notice period, it is requested that the petitioner promptly so inform the Commission by a toll-free telephone call to Western Union at 1-(800) 325-6000 (in Missouri l-(800) 342-6700).
The Western Union operator should be given Datagram Identification
Number N1023 and the following message addressed to Charles L. Hiller, Director, Project Directorate I-2, Division of Reactor Projects I/II:
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 of the petition should also be sent to the Office of the General
- Counsel, U.S.
Nuclear Regulatory Commission, Washington, DC
- 20555, and to Shaw,
- Pittman, Potts and Trowbridge, 2300 N Street NW., Washington, D.C.
- 20037, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the presiding Atomic Safety and Licensing Board that the petition and/or 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 January 9,
- 1991, and its supplements dated August 19,
- 1991, June 22, 1992 and August 3,
- 1992, which are available for public inspection at the Commission's Public Document Room, the Gelman Bu'ilding, 2120 L Street, NW., Washington, DC 20555 and at the local public document room located at
Osterhout Free Library, Reference Department, 71 South Franklin Street, Wilkes-Bar re, Pennsylvania 18701.
Dated at Rockville, Maryland, this 26th day of August 1992.
FO E NUCLEAR EGULATORY COMMISSION
'c C ark, Acting Project Director roject Dir ctorate I-2 ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation