ML20154C946

Notice of Consideration of Issuance of Amend to Licenses NPF-10 & NPF-15 & Proposed NSHC Determination & Opportunity for Hearing.Amends Revise Lsited Tech Spec Sections, Including Remote Shutdown Monitoring Instrumentation

ML20154C946
Person / Time
Site:	San Onofre
Issue date:	08/30/1988
From:	Rood H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154C949	List: ML20154C946
References
NUDOCS 8809150093
Download: ML20154C946 (10)

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UNITED STATES NUCLEAR REGULATORY COMMISSIO_N SOUTHERN CALIFORNIA EDISON COMPANY. ET AL DOCKET N05. 50 361 AND 50-362 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO I

FACILITY OPERATING LICENSES AND OPPORTUNITY FOR HEARING I

The U. S. Nuclear Regulatory Comission (the Comission) is considering issuance of amendments to Facility Operating License Nos. NPF-10 and NPF-15 issued to Southern California Edison Company (SCE), San Diego Gas and Electric f

Company, the City of Riverside, California and the City of Anaheim, California (the licensees), for operation of San Onofre Nuclear Generating Station Units 2 and 3 located in San Diego County, California. The requests for amendrents were submitted by letter dated May 6, ;988 and identified as Proposed Chenge Numbers 243 and 244.

Each proposed change is discussed below.

Proposed change No. NPF-10/15-243 would change several Technical Specification i

(TS)sectionsasdescribedbelow:

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T.S. Table 3.3 9 "Remote Shutdown Monitoring Instrumentation" - This j

table provides a listing of the required instruments for the remote shut-downpanel(RSP)alongwiththeinstrumentchannelrange. This proposed l

change would revise the stated RCS cold leg temperature r&nge from l

0-600'F to 0-700'F. The RCS hot leg temperature range would similarly be changed from 190-625'F to 0-700'F. This change would also clarify the need to have RCS cold and hot leg temperature indication at RSP L411 only.

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. 4 This change would also delete s.be Reactor Coolant Boron Concentration Instrument display and replace it with source range neutron flux indication (10*I-10 CPS).

5 T.S. Table 4.3-6, "Remote Shutdown Monitoring Instrumentation Surveil-lance Requirements" - This table provides a listing of RSP instruments and ths associated surveillance requirements. The proposed change would replace reactor coolant boron concentration with source range neutron flux to be consistent with the changes to Table 3.3-9.

(b) 7.$. 3/4.3.3.7 "Fire Detection In;.trumentation" - This specification and the associated Table 3.3-12 specify the number of fire detection early warning and actuation instruments that must be operable in each fire zone, the action that must be taken when detection equipment is inoperable, and the surveillance requirements for deterinining operability. This change would allow more early warning detectors to be inoperable before an hourly fire watch is required, would suspend the requirement for an hourly fire watch in areas of temporary radiation and/or Itfe-threatening hazards, and l

would change the method for determining operability of the fire detection system following a seismic event. Table 3.3-11 would be changed to replace the current designation of each fire zone with the designations used in the Updated Fire Hazards Analysis (UFHA) and to specify only those fire detection based upon the UFMA,10 CFR 50 Appendix R and Generic Letter 86-10 guidance.

The proposed change to Table 3.3-11 would also remove the distinction between heat, smoke, and flame type early warning detectors.

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T.S. 3/4.7.8.2 "Spray and/or Sprinkler Systems" - This specification and the associated Table 3.7-5 designate the actions to be taken when any of the systems listed in Table 3.7-S are inoperable, and the surveillance requirements for determining operability. The proposed change would suspend the fire watch requirement when equipment is inoperable in areas of temporary radiation and/or life threatening hazards, would specify what constitutes establishment of backup fire suppression equipment, and would change the 18 month surveillance interval to "once per refueling outage i

for those plant areas that are inaccessible during non-refueling plant I

operation. Also Table 3.7-5 would be changed to agree with the UFHA and the coeputerized plant equipment data base, and to specify only thote systerns which protect safe shutdown and/or safety related equipeent based upon the UFHA, 10 CFR 50 Appendix R. and Generic Letter 86-10 guidance.

1 (d)

T.S. 3/4.7.8.3 "Fire hose Stations" - This specification and the associated l

Table 3.7-6 describe which fire hose stations are required to be operable.

l the actions to taken when any are inoperable, and the surveillance requirerents for determining operability. This change would remove the requirement to lay backup fire hose to an area served by an inoperable fire hose station if that stations is inside containment with the equipment l

hatch closed, within 250 feet of an operable water source, or if two 150 foot hose packs on the fire engine are operable. The change would also I

remove the requirement to identify the purpose and location of the backup

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i hose valves on the '2igns required to be mounted above the hose and at the inoperable station. The 18-month surveillance requirements would be changed to "once per refueling outage for those plant areas that are inaccessible during non-refueling plant operation." Table 3.7-6 would be change by adding a new column labeled "Fire Area / Zone," by adding 31 hose stations, and by removing Unit 2 hose stations from the Unit 3 Specifications and vice versa, i

(e)

T.S. 3/4.7.0 "Fire Rated Assemblies" - This specification delineates which fire rated assemblies and penetrations are required to be operable, when they are required to be operable, the actions to be taken when any j

are inoperable and the surveillance requirements for determining operability. This change would clarify which assembites are required to i

be operable and would only require them to be operable when equipment protected by the asstmbly is required to be operable, rather than at all times as currently specified. The change would also clarify the action l

to be taken when any assembly is inoperable, would suspend the requirement for a fire watch in an area of temporary radiation and/or life-threatening hazards, and would change the 18-month surveillance interval to "once per i

refueling outage for those plant areas that are inaccessible during non-refueling plant operation."

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T.S. Bases 3/4.3.3.7 "Fire Detection Instrumentation" - This section would be changed to reflect proposed changes described in (b) above.

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Proposed Change No. NPF-10/15-244 would revise License Conditions 2.C(14) and 2.G for Unit 2 and 2.C(12) and 2.G for Unit 3.

The existing license conditions 2.C(14) for Unit 2 and 2.C(12) for Unit 3 reference specific amendments to the fire protection program which were reviewed and approved by the NRC, but have since been superseded by the Updated Fire Hazards Analysis (UFRA) and subsequent SCE submittals to the NRC. The proposed change will require SCE to implement and euintain in effect the fire protection program described in the UFHA and subsequent submittals as approved in the Updated Fire Hazards Analysis Evaluation for San Onofre 2 and 3, Revision 1 dated June 29, 1988. The proposed license condition will allow changes to be made, exclusive of those requirements addressed by Technical Specifications, without prior NRC approval under the authority of 10 CFR 50.59 provided that the changes do not involve an unreviewed' safety question and that the changes do not adversely affect the ability to achieve and r.aintain safe shutdown in the event of a fire.

Specifically, changes which do not require prior NRC approval are those which do not reduce the current level of San Onofre 2 and 3 compliance with the requirements of 10 CFR 50 Appendix R. Sections !!!.G. !!!.J. !!!.L and !!!.0 (and approved deviations thereto) and which do not involve an unreviewed safety question under 10 CFR 50.59.

Compliance with the above sections of Appendix R is identified in the documents referenced in the proposed license condition.

License condition 2.G for both units requires that violation of a license condition be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Regional Administrator with written followup within 14 days.

Deviations from the fire protection program required by License Condition 2.C(14) for Unit 2 and 2.C(12) for Unit 3 are currently exempted from 2.G reportability unless they violate the provision of

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10 CFR 50. Appendix R. Section !!!.G. !!!.J. or !!!.0 and are not otherwise l

covered by technical specification requirements. The proposed change would revise License Condition 2.G to exempt deviations from the fire protection i

i program which could be interpreted as failure to comply with License Condition i

2.C(14) for Unit 2 and 2.C(12) for Unit 3 from reportability under License I

Condition 2.G.

Deviations from the fire protection program which are not i

otherwise subject to technical specification reporting requirements and which i

would have adversely affected the ability to acheive and maintain safe shutdown in the event of a fire will be reported under revised Technical J

Specification 6.9.4 "Special Reports."

This proposed change would also add a new Section 6.9.3 to the Techni ul i

4 Specification for each unit. This change would clarify that violations of l

the requirements of the fire protection program which are not otherwise

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subject to technical specification reporting requirements and which would have 4

adversely affected the ability to achieve and maintain safe shutdown in the l

event of a fire shall be reported to the Regional Administrator of the

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Regional Office of the NRC via the Licensee Event Report System within'30 days.

Before issuance of the proposed license amendments, the Comission will have i

made findings required by the Atomic Energy Act of 1954, as aranded (the Act)

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and the Comission's regulations.

l By October 11. 1988 the licensee may file a request for a hearing with l

l respect to issuance of the amendments to the subject facility operating licenses, and any person whose interest may be affected by this proceeding and I

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who wishes to participate as a party in the proceeding must file a written i

request for hearing and petition for leave to intervene. Requests for a l

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hearing and petitions for leave to intervene shall be filed in accordance with the Commission's "Rules of Practice for Domestic Licensing Proceedings" in 10 f

CFR Part 2.

If a request for a hearing or petition for leave to intervene is filed by the above date, the Cosnission or an Atomic safety and Licensing Board panel designated by the Cosnission or by the Chairman of the Atomic Safety and f

Licensing Board Panel will rule on the request and/or petition, and the Secretary I

or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.

I 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 j

pemitted with particular reference to 4,ne following factors (1)thenature f

of the petitioner's right under the Act to be made a 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 ray 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 pre-hearing conference scheduled in the proceeding, but such an amended petition rust satisfy the specificity requirements described above.

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i Not later than fif teen (15) days prior to the first pre hearing conference l

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, and the bases for each contention set i

fo'th with reasonable specificity. Contentions shall be limited to matters l

within the scope of the amendments under consideration. A petitioner who l

fails to file such a supplement which satisfies these requirements with respect

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to at least one contention will not be perinitted to participate as a party, j

Those pcmitted to intervene become parties to the proceeding, subject to l

any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the i

opportunity to present evidence and cross-examine witnesses, j

A request for a hearing or a petition for leave to intervene shall be filed I

with the Secretary of the Comission, U.S. Nuclear Regulatory Comission, Washington, DC 20555, Attention: Docketing and Service Branch, or may be delivered to the Comission's Public Document Room 1717 H Street NW, f

Washington, DC, by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested that the petitioner or represevitative for the petitioner promptly inform the Comission by a toll-free telephone call to Western Union at 1-(800)3256000(inMissourt 1-(800)3426700).

The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to George W. Knighton petitioner's name anil telephone number; date petition was mailed; plant name; and publication date and page aumber 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

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l Comission. Washington, DC 20555 and to Mr. C.wles R. Kocher. Esq. Southern i

California EOson Company. 2244 Walnut Grove Avenue. P.O. Box 800. Rosemead.

California 91770 and Orrick. Herrington and Sutcliffe Attention: David R. Pigott. Esq. 600 Montgomery Street. San Francisco, California 94111 l

attorneys for the licensees.

Nontimely filings of petitions for leave to intervene, amended petitions, i

supplemental petitions and/or requests for hearing will not be entertained l

absent a detemination by the Comission, the presiding officer or the presiding Atomic Safety and Licensing Board, that the petition and/or request 4

e should be granted based upon a balancing of the factors specified in the 10 l

j CFR2.714(a)(1)(1)-(v)and2.714(d).

l If a request for hearing is received, the Comission's staff may issue

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i the amendment after is completes its technical review and prior to the i

completion of any required hearing if it publishes a further notice for public l

l coment of its proposed finding of no significant hazards consideration in accordance with 10 CFR 50.91 and 50.92.

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For further dotatis with respect to this action, see the application for l

amendments which is available for public inspection at the Comission's public Document Room,1717 H 5treet NW, Washington, DC, and at the General Library, University of California at Irvine, Irvine, California 92713.

s Dated at Rockville, Maryland, this 30th day of August.1988.

FOR THE NUCLEAR REGULATORY C0m!S$10N l

Harry Rood, Senior Project Manager i

Project Directorate Y Division of Reactor Projects - !!!,

!Y, Y and Special Projects i

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