ML20209D152

Notice of Consideration of Issuance of Amend to License NPF-29 & Proposed NSHC Determination & Opportunity for Hearing Re Addition of Specs to Table 3.3.3-1, ECCS Actuation Instrumentation

ML20209D152
Person / Time
Site:	Grand Gulf
Issue date:	08/28/1986
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20209D142	List: ML20209D136 ML20209D152
References
TAC-59440, NUDOCS 8609090210
Download: ML20209D152 (8)

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O 7590-01 e

UNITED STATES NUCLEAR REGULATORY COMMISSION

, MISSISSIPPI POWER & LIGHT COMPANY

, MIDDLE SOUTH ENERGY, INC.

SOUTH MISSISSIPPI ELECTRIC POWEP, ASSOCIATION DOCKET NO. 50-416 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS

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g CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING i

The U.S. Nuclear Regulatory Comission (the Comission) is considering issuance of an amendment to Facility Operating License No. NPF-29 issued to Mississippi Power & Light Company, Middle South Energy Inc., South Mississippi Electric Power Association, for operation of the Grand Gulf Nuclear Station,

Unit I, Claiborne County, Mississippi.

The proposed amendment would make the following changes in the Technical l

Specifications;addspecificationsinTable3.3.3-1,"EmergencyCoreCooling System (ECCS)ActuationInstrumentation"andTable3.3.3-2,"EmergencyCore Cooling System Actuation Instrumentation Setpoints" to incorporate interlock instrgntation which is designed to prevent inadvertent overpressurization l

oflowgesignpressureemergencycorecoolingsystemsbythereactorcoolant systems, and make associated changes in Table 3.3.3-3, "ECCS Response Times" and Surveillance Requirement 4.5.1 regarding response times of ECCS injection systems. Table 4.3.3.1-1, "ECCS Actuation Instrumentation Surveillance Require-ments," Surveillance Requirement 4.4.3.2.2, " Reactor Coolant System Operational 8609090210 860902 6 DR ADOCK 0500

Leakage " Table 3.4.3.2-2, " Reactor Coolant System Interface Valves Pressure Monitors Alam," and Table 3.4.3.2-3 " Reactor Coolant System Interface Valves Pressure Inkrlocks." These proposed changes were requested in Item 13 of the attachment to the licensee's letter dated August 12, 1985, as amended September 25, 1985 and supplemented October 5 and October 22, 1985 and May 30, 1986. The changes requested in Item 12 of the August 12, 1985 letter were previously noticed and issued as Amendment No. 7 to GGNS Unit 1 License No. NPF-29 on s

November 8, 1985.

! This notice supersedes a previous notice published in the Federal Register

( on August 28, 1985 (50 FR 34994). The previous notice was based on the licensee's i, initial application for amendment dated August 12, 1985. During its safety review of proposed changes to Technical Specifications for the ECCS injection valve interlocks the staff noted the licensee's proposed deletion of tests of response times for starting the ECCS systems associated with the injection valves,

! because the system response with valve interlocks would vary, depending on the rate of depressurization during a loss of coolant accident. The presently specified system response time (40 seconds) includes 10 seconds for starting an emergency diesel generator and 30 seconds for opening the injection valve j in the system. In response to staff questions, regarding surveillance tests of injection valve opening, the licensee proposed by letter dated September 25, 1985 to include surveillance tests of the time for injection valves to move from l

the closed position to the open position (29 seconds). Surveillance tests of emergency diesel generator starting times (10 seconds) are presently included I .

f in Technical Specification 4.8.1.1.2. This notice is based on the revised application from that initially noticed which results in greater assurance that the ECCS injection valves will open within the design time. Appropriate changes

L i to the initial notice regarding ECCS injection valve response time have been incorporated in this notice. .

Before iIsuance of the proposed license amendment, the Comission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulaticns.

The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Comission'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 f increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accidentpreviouslyevaluated;or(3)involveasignificantreductionina margin of safety.

The licensee has made an analysis of significant hazards considerations using the standards of 10 CFR 50.92 ar.J has concluded that the proposed amend-ment does not involve a significant hazards consideration. The NRC staff has

. made a preliminary review of licensee's analysis and associated bases. Staff's discussion of the proposed amendment as it relates to the three standards follows.

The addition to the Technical Specifications of interlock instrumentation on pressure isolation valves, is needed to implement a design change required by a license condition. The present compensatory requirement for leak tests of low pressure core spray (LPCS) and low pressure coolant injection (LPCI) check valves would be deleted. The design change would result in an increase of 51*F in calculated peak cladding temperature to 2149"F during a postulated loss ~of coolant accident because of a longer time required for LPCS and LPCI injection valves to start to open. The required response time for LPCS

and LPCI injection valves to move from the closed to the open position (29 seconds) will be slightly faster than the required response time defined in present Techhical Specifications (30 seconds). The calculated peak cladding I temperature of 2149'F is still below the limiting 2200*F required by 10 CFR 50.46, so the safety margin is not affected. The design change will be pEr-formed in accordance with appropriate regulatory and industry codes and standards, the GGNS quality assurance program, and applicable requirements of the GGNS FSAR.

Therefore, the design change would be consistent with the licensing basis.

Because these changes will add requirements not presently included in the Tech-f nical Specifications which more than offset the removal of the compensatory leak

~ test requirement, and because the change would result in the performance of the ECCS safety function without affecting the safety margin, this change does not i significantly increase the probability or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any accident previously evaluated, nor does it involve a significant reduction in a margin of safety.

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Accordingly, the Comission proposes to detemine that these changes do not involve a significant hazards consideration.

The Commission is seeking public coments on this proposed determination.

Any coments received within 30 days after the date of publication of this notice will be considered in making any final determination. The Comission will not normally make a final determination unless it receives a request for a hearing.

, Written comments should be addressed to the Rules and Procedures Branch, Division of Rules and Records, Office of Administration, U.S. Nuclear Regulatory Consnission, hashington, D.C. 20555, and should cite the publication date and page number of this FEDERAL REGISTER notice. Copies of comments received may be examined at the NRC Public Document Room, 1717 H Street, NW, Washington, D.C.

By , 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 f petition for leave to intervene. Request for a hearing and petitions for leave to intervene shall be filed in accordance with the Ccnnrtsin1's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or en Atomic Safety Md Licens4rs Board, designated by the Commission or by the Chairman of the Atomic 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 92.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and l how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be pennitted with particular reference to the following factors: (1)thenature l of the petitioner's right under the Act to be made a party to the proceeding; I

(2)thenatureandextentofthepetitioner'sproperty, financial,oroth:r 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 ,

proceedingaktowhichpetitionerwishestointervene. 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 f scheduled in the proceeding, a petitioner shall file a suppleent to the petition to intervene which must include a list of the contentions wh.ich are sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendment under consideration. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be pemitted 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 l on the issue of no significant hazards consideration. The final detemination will serve to decide when the hearing is held. l If the final detemination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment.

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t If the final determination is that the amendment involves a significant hazardsconsideration,anyhear;ingheldwouldtakeplacebeforetheissuance i

of any amendment.

Normally, the Comission 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

, in derating or shutdown of the facility, the Comission may issue the license amendment before the expiration of the 30-day notice period, provided that its final detennination is that the amendment involves no significant hazards f

consideration. The final determination will consider all public and State coments received. Should the Commission take this action, it will publish a notice of issuance and provide .for opportunity for a hearing after issuance.

The Comission 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 Comission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Att: Docketing and Service Branch, or may be delivered to the Comission's Public Document Room,1717 H Street, NW Washington, D.C., 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 infonn the Commission by a toll-free telephone call to Western Union at (800) 325-6030 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Walter R. Butler, Director, BWR Project Directorate No. 4, Division of BWR Licensing: petitioner's name and telephone number; date petition was mailed; plant name; and publication date and page

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number of this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Executive Legal Director U. S. Nuclear Regulatory Consission, Washington, D.C. 20555, and to Nicholas S. Reynolds. Esquire, Bishop, Liebeman, Cook, Purcell, and Reynolds, 1200 17th Street, N.W., Washington, D.C. 20036, 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 f based upon a balancing of 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 August 12, 1985 as amended September 25, 1985 and supplemented October 5 and October 22, 1985 and May 30, 1986 which is available for public inspection at the Comission's Public Document Room,1717 H Street, NW, Washington, D.C., and at the Hinds Junior College, McLendon Library, Raymond, Mississippi 39154.

4 Dated at Bethesda, Maryland, this 28th day of August 1986.

FOR THE NUCLEAR REGULATORY COMMISSION i

w I Walter R. Butler Director BWR Project Directorate No. 4 Division of BWR Licensing l

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