ML20137H590

Proposed Tech Specs Change Request Re Change in Co Name

ML20137H590
Person / Time
Site:	Palisades
Issue date:	03/27/1997
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18067A458	List: ML20137H590
References
NUDOCS 9704020293
Download: ML20137H590 (11)

Text

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ATTACHMENT 2 t

CONSUMERS ENERGY COMPANY PALISADES PLANT '

DOCKET 50-255 i

FACILITY OPERATING LICENSE AND  :

TECHNICAL SPECIFICATIONS CHANGE REQUEST CHANGE IN COMPANY NAME N

Existing Facility Operating License Pages Marked to Show Proposed Changes  !

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4 Pages 9704020293 970327 ~~

PDR ADOCK 05000255.

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UNITED STATES _ i NUCLEAR REGULATORY COPMISSION  !

j WASHINGTON, DC 20555 0001 cere ns aa"ra c m .ar " ~ " # "

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DOCKET NO. 50-255-  !

PALISADES PLANT l FACILITY OPERATING LICENSE  ;

1 1 License No. DPR-20

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for a license filed by Consumers' Power Company (CPCo)! j complies with the standards and requirements of the Atomic Energy Act i of 1954, as amended (the Act), and 10 CFR Chapter I, and all required i 4

. notifications to other agencies or bodies have been duly made; j i

B. Construction of the Palisades Plant (the facility) has been completed )

in conformity with Provisional Construction Permit No. CPPR-25 and the 1

application, as amended, the provisions of the Act, and the e regulations of the Commission, and has been operating under a l

provisional operating license since March 24, 1971; C. The facility will operate in conformity with the application, as amended,'the provisions of the Act, and the rules and regulations of i' the Commission (except as exempted from compliance in Section 2.D.

below);

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D. There is reasonable assurance that the activities authorized by this

i. Facility Operating License can be conducted without endangering the P health and safety of the public; E. CPCoh is technically qualified to engage in the activities authorized by this license, as amended, in accordance with 10 CFR Chapter I;

i. F. CPCo! has satisfied the applicable provisions of 10 CFR Part 140,

" Financial Protection Requirements and Indemnity Agreements";

G. The issuance of this license will not be inimical to the common

, defense and security or to the health and safety of the public; M. The issuance of this license is in accordance with 10 CFR Part 51 and I i all applicable requirements have been satisfied; and I. The receipt, possession, and use of source, byproduct, and special

. nuclear material as authorized by this license will be in accordance with 10 CFR Parts 30, 40, and 70.

2. Provisional Operating License No. DPR-20, dated March 24, 1971 as amended, ,

is superseded in its entirety by Facility Operating License No. DPR-20 hereby issued to Ccr.:=:r; ":=r Cupre (CPCc) Csnisisi@EsidilCsipahi to read-as follows:

l N E E ! N NESINEIE5 N N Amendment No.

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2 -i A. This license' applies to the Palisades Plant, a pressurized light water moderated and cooled reactor and electrical generating equipment (the facility). The facility is located in Van Buren County, Michigan, and is described in C"C:': CimisiliFREsiIr Anal as supiilisiWfid sRd~jf33s[d, amende aiid in CPC ':ifnyfi Updated C6sisiiFi

@ @ysis ReportCijii@d Environmental Report, as supplemented and aieW B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1) GPGe CM&EnTerg~~yiCHi[Ei, pursuant to Section 104b of the  !

AtomiB Energy Ait if 1954, as amended, and 10 CFR Part 50,

" Domestic Licensing of Production and Utilization Facilities," to possess, use, and operate the facility in accordance with the '

limitations set forth in this license;

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(ti (2) GPGe Ciii@~iid~70,~Wj)iiip]iiny, pursuant to the Act and 10 CFR Parts 40 to receive, possess, and use source and <pecial  !

nuclear material as reactor fuel, in accordance with the i limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3) Parts'30~~40~,^I GPGe CsisisiFIItsiF@~ICi@'

d"70, t'6 ribe'ive, possess, and use byproduct,h source, and special nuclear material as sealed sources for reactor startup, reactor instrumentation, radiation monitoring equipment calibration, and fission detectors in amounts as required; I (4) GPGe C6WisisFillEse~r$^IC6s[Ef, pursuant to the Act and 10 CFR Parts"30740',"Thd"70, t6" receive, possess, and use in amounts as required any byproduct, source, or special nuclear material for sample analysis or instrument calibration, or associated with I radioactive apparatus or components; and (5) GPGe C6is~4siiMfiir~gyJCis@, pursuant to the Act and 10 CFR Parts 30,^ 40, a6a 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operations of the facility.

C. This license shall be deemed to contain and is subject to all applicable )rovisions of the Act; to the rules, regulations, and orders of tie Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

C Csii is authorized to operate the (1) GPGe ' 6HIGEifsilis@ tate'@ reactor core power levels not in excess facility ~at~~ifiidj!s of 2530 Megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) The Technical Specifications contained in Appendix A, as revised through Amendment No. W 6 , and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. GPGe C 'iiiiigaspiiE6sfiflC6spshy shall operate the facility in accordance with~ths"TibhilcaT Specifications and the Environmental Protection Plan.

Amendment No.

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• 1 (3) GPGe T. 'MW9(15f6ns*of~pegy~" iiii.W~fMoiii-~ shall implement and maint effec @t@~i

~p6 thi approved-fire protection program as .

i

. described in the Final Safety Analysis Report for the facility.and ,

las ap roved in the SERs dated 09/01/78,03/19/80,02/10/81, l J 05/26 83, 07/12/85, 01/29/86, 12/03/87, and 05/19/89 and subject j to th following provisions: i

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a.

GPGe fire' pF6tiction p-@1Tj1iii1ff_fj~n6fr~gy'D~s~p~ithout pfo'graiii prior approval of theep i Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event f of a fire. l t

b.

GPGe the appF61/id lisi 7C Etf6n program provided:

M. ~f\YE~ii@rofe'iii5si@"^ may alter specific features of I

- Such changes do not result in failure to complete the fire i 4

>rotection program as approved by the Commission. GPGe  !

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' misiiiii~fi1Energi a ifuFrent Fidord[Cdispny I

6f^all suchshall maintain in auditable form, '

changes, including an

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. analysis of the effects of the change on the fire J protection program and shall make such records available

< to the Commission' Inspectors upon request. All changes to the ap) roved program shall be reported annually, along with tie FSAR revision; and .

Temporary changes to specific fire )rotection features C which may be necessary to accomplis 1 maintenance or modifications are acceptable provided interim compensatory measures are implemented.

D. The facility has been granted certain exemptions from the requirements i of Section III.G of Appendix R to 10 CFR Part 50, " Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1,

, 1979." This section relates to fire protection features for ensuring the systems and associated circuits used to achieve and maintain safe

, shutdown are free of fire damage. These exemptions were granted and senttoCPCosinlettersdatedFebruary8,1983, July 12,1985,and July 23, 1985.

!- In addition, the facility has been granted certain exemptions from Appendix J to 10 CFR Part 50, " Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors." This section contains leakage test requirements, schedules and acceptance criteria for tests of the leak-tight integrity of the primary reactor containment and systems and components which penetrate the containment. These exemptionsweregrantedandsenttoCPCojinaletterdated December 6, 1989.

These exemptions granted pursuant to 10 CFR 50.12, are authorized by

. law, will not present an undue risk to the public health and safety, l and are consistent with the common defense and security. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the. rules and regulations of the Commission.

? IK@pj_Ppj$6ippijj[EM3@gty Amendment No.  ;

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. , 4 E. GPGe Cssisiiiifsi'EdiFjy]^C6iiijissy shall fully implement and maintain in effec't'il1~iiF6viiT6ns 6f~the Commission-approved " Palisades Plant Physical Security. Plan," " Palisades Plant Suitability Training and Qualification Plan," and " Palisades Plant Safeguards Contingency..

Plan," and all approved amendments. GPGeC65sumeFGEnsFyyiCom make changes to these plans without prior Commissi]on approval,pasi^

if the changes do not decrease the safeguards effectiveness of the plans, in accordance with 10 CFR 50.54(p)(2).

F. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 50.73(b), (c), and (e).

G. ihy shall have and maintain financial GPGe C6iisisiiFiMssFjyICsii@d proteEtl6E"5f Iti~ch*tyjie'in in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

H. This license is effective as of the date of issuance and shall expire at midnight on March 14, 2007.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By: Thomas E.Murley Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments:

1. Appendix A - Technical >

Specifications

2. Appendix B - Environmental Protection Plan Date of Issuance: February 21, 1991 1

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Amendment No.

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ATTACHMENT 3 i

CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 4

FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS CHANGE REQUEST CHANGE IN COMPANY NAME Proposed Technical Specifications Pages 5-1 and 6-30 s

2 Pages 1

5,0 DESIGN FEATURES 5.1 ,

11J1 The Palisades reactor shall be located on 437 acres owned by Consumers Energy Company on the eastern shore of Lake Michigan approximately four and one-half miles south of the southern city limits of South Haven, Michigan. Figure 5-1 shows the plan of the site. The minimum distance to the boundary of the exclusion area as defined in 10 CFR 100.3 shall be 677 meters.

5.2 CONTAINMENT DESIGN FEATURES 5.2.1 Containment Structure

a. The containment structure completely encloses the primary coolant system to minimize release of radioactive material to the environment should a failure of the primary coolant system occur.

The prestressed, post-tensioned concrete structure provides adequate biological shielding for both normal operation and accident situations and is designed for low leakage at a design pressure of 55 psig and 283*F.

The principal design basis for the structure is that it be capable of withstanding the internal pressure resulting from a design basis loss-of-coolant accident. In this event, the total energy l contained in the water of the primary coolant system is assumed to be released into the containment through a double-ended break of the largest primary coolant pipe coincident with a loss of normal and standby electrical power. Subsequent pressure behavior is determined by the engineered safety features and the combined influence of energy sources and heat sinks.

b. The external design pressure of the containment shell is 3 psig.

This value is approximately 0.5 psig greater than the maximum external pressure that could be developed if the containment were sealed during a period of low barometric pressure and high temperature and, subsequently, the containment atmosphere were cooled with a concurrent major rise in barometric pressure. Vacuum i breakers are therefore not provided. l

c. The containment is designed as a seismic Class I structure.

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l 5-1 Amendment No. B5, i

i ADMINISTRATIVE CONTROLS l \

6.8.2.6 RECORDS Records of NPAD activities shall be maintained. Reports shall be prepared and distributed as indicated below:

a. The results of reviews, performed pursuant to Section 6.8.2.4.1 and Section 6.8.2.4.2, shall be reported to the Vice President - N00 at least monthly.

b. A report assessing the overall nuclear safety performance of Palisades shall be provided to senior Consumers Energy Company l l management annually. l 6.8.3 PLANT SAFETY AND LICENSING 6.8.3.1 FUNCTION The Plant Safety and Licensing staff shall review proposed changes in design or operation and such other matters as the PRC may assign to identify issues significant to nuclear safety and recommend nuclear safety improvements.

6.8.3.2 COMPOSITION The Plant Safety and Licensing staff responsible for the review function shall be an experienced technical staff meeting the qualifications of Section 6.3.

6.8.3.3 RESPONSIBILITIES The Plant Safety and Licensing staff may provide nuclear safety review I as delegated by PRC for: l

a. Procedures, programs and changes thereto identified in Specifications 6.4 and 6.5 and any additional procedures and changes thereto identified by the Plant General Manager as significant to nuclear safety,

b. All proposed tests or experiments.

c. All proposed changes or modifications to plant systems or equipment.

d. The Site Emergency Plan.

l 6-30 '

Amendment No. M, 86, H8, M7, H6, WG, W4, i

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ATTACHMENT 4  ;

l CONSUMERS ENFRGY COMPANY

, PALISADES PLANT DOCKET 50-255 FACILITY OPERATING LICENSE AND i TECHNICAL SPECIFICATIONS CHANGE REQUEST CHANGE IN COMPANY NAME i

j Existing Technical Specifications Pages 5-1 and 6-30 Marked to Show Proposed Change l

l 2 Pages

1 5.0 DESIGN FEATURES

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'5. I ELIE The Palisades reactor shall be located on 487 acres owned by Cesumees P== C=p=y Michigan appro$6hiimiifff6eYpfi~C'6aijishy on the eastern shore of Lake city limits of South Haven, Michigan. Figure 5-1 shows the plan of the site. The minimum distance to the boundary of the exclusion area as defined in 10 CFR 100.3 shall be 677 meters.

5.2 CONTAINMENT DESIGN FEATURES 5.2.1 Containment Structure

a. The containment structure completely encloses the primary coolant system to minimize release of radioactive material to the environment should a failure of the primary coolant system occur.

The prestressed, post-tensioned concrete structure provides ,

adequate biological shielding for both normal operation and  ;

accident situations and is designed for low leakage at a design  !

pressure of 55 psig and 283*F.

The principal design basis for the structure is that it be capable of withstanding the internal pressure resulting from a design basis loss-of-coolant accident. In this event, the total energy contained in the water of the primary coolant system is assumed to be released into the containment through a double-ended break of the largest primary coolant pipe coincident with a loss of normal and standby electrical power. Subsequent pressure behavior is determined by the engineered safety features and the combined influence of energy sources and heat sinks.

b. The external design pressure of the containment shell is 3 psig. l This value is approximately 0.5 psig greater than the maximum i external pressure that could be developed if the containment were sealed during a period of low barometric pressure and high temperature and, subsequently, the containment atmosphere were cooled with a concurrent major rise in barometric pressure. Vacuum breakers are therefore not provided.

c. The containment is designed as a seismic Class I structure.

5-1 Amendment No. 85,

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ADMINISTRATIVE CONTROLS  :

.. t 6.8.2;6 RECORDS Records of NPAD activities shall be maintained. Reports shall be  ;

prepared and distributed as indicated below:

a. The results of reviews, performed pursuant to Section 6.8.2.4.1 and Section 6.8.2.4.2, shall be reported to the Vice President - N00 at ,

least monthly.  !

b. A report assessing the overall nuclear safety performance of Palisades shall be .rr Cr;ry M _provided to senior managementCannually.

r r r r:

6.8.3 PLANT SAFETY AND LICENSING 6.8.3.1 FUNCTION The Plant Safety and Licensing staff shall review proposed changes in  !

design or operation and such other matters as the PRC may assign to identify issues significant to nuclear safety and recommend nuclear ,

safety improvements.

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6.8.3.2 COMPOSITION The Plant Safety and Licensing staff responsible for the review function shall be an experienced technical staff meeting the qualifications of Section 6.3.

6.8.3.3 RESPONSIBILITIES The Plant Safety and Licensing staff may provide nuclear safety review l as delegated by PRC for:

a. Procedures, programs and changes thereto identified in Specifications 6.4 and 6.5 and any additional procedures and changes thereto identified by the Plant General Manager as significant to nuclear ,

safety.  !

b. All proposed tests or experiments.

c. All proposed changes or modifications to plant systems or equipment.

d. The Site Emergency Plan.

l 6-30 Amendment No. M, SE, MS, M7, M6, W4, H4,