ML20091F219

Safety Evaluation Supporting Amend 142 to License DPR-20

ML20091F219
Person / Time
Site:	Palisades
Issue date:	03/27/1992
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20091F206	List: ML20091F203 ML20091F219
References
GL-91-01, GL-91-1, NUDOCS 9204200247
Download: ML20091F219 (3)

Text

- _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _

i d'po ot ouq'%

UNITED STATES 3.'

i NUCLEAR REGULATORY COMMISSION c, '

WAsHINoToN. D C. 20%6

,/

5 AF[TY [VAtUAT104 PilHL0f fICf Of JJVCU AR_ELACTOR fi[Cd1LAl1QS

((l ATED TO AMLt1DMEliT tJDd42_LQ JEILITY OPULAllRG_Lif1NSE t10. DPR-20 LO!W)MERS POWLR_(OMPANX LAll5ADES PtANT DQ 1ET NO. 50-255 1.O l.N1RJBpIT103 By letter dated Novecber 12, 1991, Consumers Power Cotpany (the licensee) requested amendment to ine 7echnical Specifications (TS) appended te facility Operating License No. DPR-20 for the Palisades Plant.

The proposed change would (1) move the withdrawal schedule of reactor vessel material surveillance capsules from the Palisades TS to its final safety analysis report (fSAR), (2) revise the withdrawal schedule to reflect changes in the accounting of the length of operating cycles, and (3) delay the withdrawal af capsule W-110 from the end of operating cycle (EOC) 9 to EOC 10.

Guidance or the proposed TS change was provided by Generic Letter (GL) 91-01, of Janut.ry 4, 1991, to all holders of operating licenses or construction permits for nuclear power reactors.

2.0 EVALUATION c

The capsule withdrewal schedule is a part of the surveillance requirement of the Pressure / Temperature limits for the reactor coolant system in the current standard TS.

Appendix H to 10 CFR Part 50 requires the sult.ittal to, and approval by, the tMC of any proposed withdrawal schedule before implementation.

The staff has determined that regulatory requirements for the withdrawal schedule in both TS and Appendix H are redundant and unnecessary.

As part of the TS improvement effort, the staff initiated Generic letter 91-01,

• Removal of the Schedule for the Withdrawal of Reactor Vessel Material Specimens from the Technical Specifications." Generic Letter 91-01 provides guidance for and basis on the removal of the withdrawal schedule from the TS.

When the withdrawal schedule is removed from the TS, GL 91-01 requires that the NRC-approved schedule should be maintained in the Update final Safety Analysis Report.

The staff finds the removal of the withdrawal schedule from the Palisades TS acceptable because the licensee has proposed to incorporate the capsule withdrawal schedule in the Palisades FSAR.

Palisades operating Cycle 9 ended in February 1992.

From Cycle 1 to Cycle 8, the licensee had used 0.8 EfPY per fuel cycle to calculate the approximate refueling outage when capsules should be removed.

The licensee proposed to change the fuel cycle length from 0.8 EFPY per cycle to 1.0 EFPY per cycle because Palisades has been operated close to 1.0 EFPY per cycle.

Also, starting Cycle 11, the licensee will change the fuel cycle length from 9204200247 920327 PDR ADOCK 05000255 p

PDR

12 months to 18 months which will result in 1.15 EfPY per cycle.

10 reflect the changes in the cycle accounting method, the licensee has proposed to revise the withdrawal schedule. The staff finds the revision to the withdrawal schedule acceptable because the licensee follows A51H Standards E

~

185-82, section 7.6.3.4, which specifies that the capsule withdrawals should be scheduled at the nearest vessel refueling date.

The specifications in AS1M E 185 are a part of reactor materials surveillance reon W ments in Appendix H to 10 CFR Part 50.

The licensee estimated that at EOC 9 and EOC 10 Palise-1 have been i

operated for about 8.99 EFPY and 9.95 EfPY, respectivel; aased on the current TS withdrawal schedule and ASIM E 185-02, capsule W-110 should be removed at EOC 9.

The licensee requested to delay the removal of capsule W-110 until E0C 10 because its removal will deprive the licensee of dosimetry data for Cycle 10.

The staff finds the delayed withdrawal schedule for W-110 acceptable because the witMrawal schedule satisfies Table 1 of ASTM E 185-92.

Based on the above evaluation, the staff concludes that the licensee's requests are acceptable because the proposed changes to Palisades TS satisfy GL 91-01 and Appendix H to 10 CFR Part 50, 3.0 STA1E EONSULTATION in accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment.

The State official had no comments.

4,0 ENVIROW((LTAL CONSIDERATION This amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and a chtnge in a surveillance requirement.

The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any ef fluents that may be released offsite, and that there is no signtficant increase in individual or cumulative occupational radiation exposure. The Commission has previously_ issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding (57 FR 4486).

Accordingly, this amndmeht meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b), no environmental inpact statement or environmental assessment need be prephred in_ connection with the issuance of this amendment.

LONCL USION 5.0 O

We have-concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not-be endangered by operation in the proposed manner, (2) such 4

activitiet vill be conducted in compliance with the Commission's regulations, and (3) +he issuance of the amendment will not be inimical to the common defense ar1 security or to the health and safety of the public.

Principal Coltributor: Jnha Tsao, DET/EMCB Date:

MarrS 27,1H2

4 Mr. Gerald B. Slade Consumers Power Company Palisades Plant Cc!

M. 1. Hiller, Esquire Gerald Charnoff, P.C.

Sidley & Austin Shaw, Pittman, Potts &

54th floor Trowbridge One First National Plan 2300 N. Street, N.W.

Chicago, Illinois 60603 Washington, D.C.

20037 Mr. Thomas A. McNish, Secretary Mr. David L. Brannen Consumers Power Company Vice President 212 West Michigan Avenue Palisades Generating Company Jackson, Michigan 49201 c/o Bechtel Power Corporation 1S740 Shady Grove Road Regional Administrator, Region til Gaithersburg, Maryland 20B77 U.5. Nuclear Regulatory Comission 799 Roosevelt Road Roy W. Jones Glen Ellyn, Illinois 60137 Manager, Strategic Program Development Jerry Sarno Westinghouse Electric Corporation Township Supervisor 4350 Northern Pike Covert Township Monroeville, Pennsylvania 1S146 36197 M-140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 4B913 Mr. Patrick H. Donnelly Director, Safety and Licensing Palisades Plant 27780 Blue Star Memorial Hwy.

Covert, Michigan 49043 Resident inspector c/o U.S. Nuclear Regulatory Comission Palisades Plant 27782 Blue Star Memorial Hwy.

Covert, Michigan 49043 Nuclear facilities and Environmental Monitor Section Office Division of Radiological Health Depertment of Public Health 3423 N. Logan Street P.-0. Box 30195 Lansing,-Michigan 30195 i

^ --

y[, anne h, UNIir o sTAtts v

y

(

NUCLE AR REGULATORY COMMISSION p.

E wAsm90 ton. o c. goos 6 Qmf..p

[QHiVNER$ POWER COMPANY DOCKET NO. 50-255 Pall $ADES PLAT {l AMENDMENT T0 FACILITY OPERATING LICENSE Amendment No. 142 License No. OPR-20 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Consumers Power Company (the licensee) dated November 12, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the appilcation, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii)-that such activities will be conductad in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.

The issuance of this amendment is in accordance with 10 CfR Part 51 of the Comission's regulations and all applicable requirements have been-satisfied.

2.

Accordingly, the license is amende<j by changes to the Technical Specifications as indicated in thr; attachment to the license amendment and Paragraph 2.C.2 of facility 'sperating License No. OPR-20 is hereby amended to read as follows:

ltchniea1 Spn1LtrLligni The Technical Specifications contained in Appendices A and 8, as revised through Antndment No.142, are hereby incorporated in the license.

The Itcensee shall operate the facility in accordance witn the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR Tile NUCLEAR REGULATORY COMMISSION W

L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects lil/lV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 27, 1992

(

1 1

ETACHMENT TQ_Ll[1RSE AMEtGENT NO.14.1.

LALLllTY OPERATING llCENSL140. DPR-20 QQiKET NO. 50-2M Revise Appendix A Tech W il Saccifications by removing the pages identified below and inserting the.;.cled pages. The revised pages are identified by the amendment number and contain marginal liner, indicating the area of change, fidQY1 INSERT 4-16 4-16 J

4-18 4-18 4-23 4-23 p

m

..---an--

~_._ ___ __ _ _ _._. _ _._ _._.___ _ _ _ _.

4.3 11EIDiS SVRVEllt AN([

FP_UC ABill1Y Applies to preoperational and inservice structural surveillance of the reactor vessel and other Class 1. Class 2 and Class 3 system components.

OBJECT 1y1

-To insure the integrity of the Class 1. Class 2 and Class 3 piping systems and components.

SPEC 1fICATIONS a,b,c,d - Delete 6 e.

The Inservice Inspection program shall be reevaluated as required by 10 CFR 50, Section 50.55a(g)(5) to consider incorporation of new inspection techniques that have been proven practical, and the contiusions _of the evaluation shall be used as appropriate to update the inspection program.

f.

Surveillance of the regenerative heat exchanger and primary coolant pump flywheels shall be performed as indicated i Table 4.3.2.

g.

A surveillance prograr to monitor radiation induced changes in the mechanical and impact properties of the reactor vessel materials shall be maintained as described in Section 4.5.3 of the FSAR.

P l

l l

l l

l l

4-16 i

Amendment No.Ey, J M, 142 i

J

4 4.3 11HLMLR'RERWEL (Cont'd)

Etill The inspection program specified places major phasis on the areas of highest stress concentration as detcrmined by 9 eral design tvaluation and experience with similar systems."'

in addition, that portion of the reactor vessel shell welds which will be subjected to a f ast neutron dose suf ficient to change ductility pt)perties will be inspected.

The inspections will rely primarily on ultrasonic methods utilizing up to date an al,wr ing equipment and trained personnel.

Preoperational inspections will establish base conditions by determining indications that might occur from geometrical or metallurgical sources and f rom discontinuities in weldments or plates which might cause undue concern on a postservice inspection. lo the extent applicable, based upon the existing design and construction of the plant, the requirements of Section XI of the Coa shall be complied with. Significant exceptions are detailed in the requests for relief which have received fiRC approvil and are contained in the Class 1, Cists 2 snd Class 3 tong Term Inspection

Plans, yelve It311ng 10 ensure the continued integrity of selected check valves which are relied upon to preclude a potential LOCA outside containment, special requirements for periodic leat tests are specified.

in addition a vpive disk position check for the LPSI check valves is specified following each use of the LPSI system for shutdown cooling. Thi'i position check ensure thht the four LPSI check valves heve reclosed upon cessatton of shutdcwn cooling flow.

Eti m 2 C.t.1 (1) fSAR, Secti 4.5.6 (2)

Deleted j

(3)

Systematic Evaluation program Topic V II.A, NRC letter to the licensee tranmitting the final topic evaluation dated liovember 9-1981.

4-18 Amendment No. fl. /2,130,142

JABLE 4.3.2 Hisceihneous Surveillance items Eautomeq.t Method Frecuency 1.

Regenerative Heat Exchanger

a. Primary Side Shell to Volumetric 5-Year Maximum Tube Sheet Welds Interval (100%)

b. Prtr..ary Hand Volumetric 5-Year Maximum Interval (100%)

2.

Primary Coolant Pump Volumetric 100% Upper flywheel Flywheels Cach Refueling l

l l

4-23 Amendment No. A(, 7S, 142 l

l

f alc

~

/

u%

z 0"

^ n UNITED STATES E

NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20%6 s*****/

SAFETY EVALUA_ TION _BY THE OFFICLOF NUCLEAR REACTOR dLGULATION

!![ LATED TO AMENDMEti No.142 TO FA(_IllTY OPERATING LLCENSE NO. DPR-10 LONSUMERS POWER COMPANY 2 ALLS _A_QES PL ANT A

E0CKET NO. 50-255

1.0 INTRODUCTION

By letter dated November 12, 1991, Consumers Power Company (the licensee) requested amendment to the Technical Specifications (TS) appended to facility Operating License No. DPR-20 for the Palisades Plant, The proposed change would (1) mort the withdrawal schedule of reactor vessel material surveillance capsules from the Palisades TS to its final safety analysis report (FSAR), (2) revise the withdrawal schedule to reflect changes in the accounting of the length of operating cycles, and (3) delay the withdrcwal of capsule W-110 from the end of operating cycle (E0C) 9 to E00 10.

Guidance on the proposed TS change was provided by Generic Letter (GL) 91-01, of January 4,1991, to all holders of operating licenses or construction permits for nuclear power reactors.

2.0 [1ALUAT10N The capsule withdrL al schedule is a part of the surveillance requirement of the Pressure /Tempetature Limits for the reactar coolant system in the currert standard TS.

Appendix H to 10 CFR Part 50 requires the submittal to, and approval by, the NRC of any proposed withdrawal schedule before implementation.

The staff has determined that regulatory requirements for the withdrawal schedule in both TS and Appendix H are redundant and unnecessar,,.

As part of the TS improvement effort, the staff initiated Generic Letter 91-01, " Removal of the Schedule for the Withdrawal of Reactor Ves:.el Material Specimens from the Technical Specifications," Generic Letter 91-01 provides guidance for and basis on the removal of the withdrawal schedule frcm the 15.

When the withdrawal schedule is removed from the TS GL 91-01 requires that the i1C-approved senedule should be maintained in the Update Final Safety Analysis Report. The staff finds the removal of the withdrawal schedule from the Palisades TS acceptable because the licensee has proposed to incorporate the capsule withdrawal schedule in the Palisades FSAR.

Palisades operating Cycle 9 ended in February 1992.

From Cycle I to Cycle 8, the licensee had used 0.8 EFPY per fuel cycle to calculate the approximate refueling outage when capsules should be removed.

The licensee proposed to change the fuel cycle length from 0.8 EFPY per cycle to 1 0 EFPY per cycle because Palisades bas been operated close to 1.0 EFPY per cycle.

Also, starting Cycle 11, the licensee will change the fuel cycle length from

. -. _ ~ _ -. - - -. - -. -. - - - -

., 12 months to 18 months which will result in 1.15 EFPY per cycle.

To reflect the changes in the cycle accounting method, the licensee has proposed to revise the withdrawal schedule. The staff finds the revision to the withdrawal schedule acceptable because the licensee follows ASTM Standards E 185-82, section 7.6.3.4, which specifies that the capsule withdrawals should be scheduled at the nearest vessel refueling date. The specifications in ASTM E 185 are a part of reactor materials surveillance requirements in Appendix H to 10 CFR Part 50.

The licensee estimated that at EOC 9 and EOC 10 Palisades will have been operated for about 8.99 EFPY and 9.95 EFPY, respectively.

Based on the current TS withdrawal schedule and ASTM E 185-82, capsule W-110 should be removed at-E0C 9.

The licensee requested to delay the removal of capsule W-110 until E0C 10 because its removal will deprive the licensee of dosimetry data for Cycle 10.

The staff finds the delayed withdrawal schedule for W-110 acceptable because the withdrawal schedule satisfies Table 1 of ASTM E 185-82.

Based on the above evaluation, the staff conclude; that the licensee's j

requests are acceptable because the proposed changes to Palisades TS satisfy GL 91-01 and Appendix H to 10 CFR Part 50,

3.0 STATE CONSULTATION

in accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment.

The State official had no comments.

4.0 [NVIRONMENTAt CONS 10ESATIp3 This amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and a change in a surveillance requirement. The staff has determined that the amendment involves no significant increase in the amounts, and no signi'icant change in the types, of any effluents that may be r91 eased offsite, and that there-is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that ttis amendment involves no significant hazards consideration and there has been no public comment on such finding (57 FR 4486). Accordingly, this amendment meets the eligibility criteria for categorical excl.usion set forth in 10-CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b), no-environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

5.0 CONCLUSION

i We have concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contrioutor: John Tsao, DET/EMCB Date:

March E 1992

- - - -