ML20053E423

Amends 59 & 64 to Licenses DPR-24 & DPR-27,respectively, Upgrading Surveillance Requirements for Hydraulic Snubbers & Making Administrative Changes

ML20053E423
Person / Time
Site:	Point Beach
Issue date:	05/25/1982
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20053E424	List: ML20053E423 ML20053E425 ML20053E427
References
TAC-10142, TAC-10143, TAC-11300, TAC-11321, NUDOCS 8206080029
Download: ML20053E423 (10)

Text

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ep,'o; UNITED STATES 8

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y WASHINGTON, D. C. 205S5 DESIG? TED ORIGINAL Certified By I 7 R-WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. OPR-24 1.

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

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 1,1981 as modified by letters dated January 15 and February 12, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.

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

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C.

There is reasonable assurance (1) that th'e activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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; and E.

The issuance of this an'endment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

e 8206080029 820525 PDR ADOCK 05000266 PDR

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-24 is hereby amended to read as follows:

B.. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective 120 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY COMt1ISSION 4

=

Robert A. Clark, Chief

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Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 25, 1982 l

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k UNITED STATES a

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WASHINGTON, D. C. 20555 DESIG TED ORIGINAL Certified B

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DOCKET NO. 50-301 POINT' BEACH NUCLEAR PLANT, UNIT N0' 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. DPR-27 1.

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

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 1,1981 as modified by letters dated January 15 and February 12, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of

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the Commission; C.

There is reasonable assurance (i) 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 conducted in compliance with the Commission'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; and E.

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

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Accordingly,-the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-27 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, ar revised through Amendment No. 64, are hereby in:ceporated in the license. The licensee shall operate tie facility in accordance with the Technical Specifications.

3.

This license amendment is effective 120 days from the date of its-issuance.

FOR THE NUCLEAR REGULATORY COMMISSION w

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a Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 25, 1982 t

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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. rf) TO FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 64 TO FACILITY OPERATING LICENSE NO. DPR-27

'00CKET NOS. 50-266 AND 50-301 i

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Revise Appendix A a'd follows:

, Remove Pages Insert Pages

-15.4.13-1 15.4.13-1 15.4.13-2 15.4.13-2 15.4.13-3 15.6.10-2 15.6.10-2 Table 15.4.1-1 Table 15.4.1-1 (continued)

(continued)

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15.4.13 Shock Suppressers (Snubbers)

Applicability Applies to the periodic inspection and testing requirements of safety related snubbers.

O Objective

> 1 To verify the operability of the snuhbers.

Specifications The following surveillance requirements apply to those snubbers listed in Table 15.3.13-1.

1.

All snubbers shall be visually inspected to verify cperability in:

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j accordance with the following schedule:

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Number of Snubbers Next Required

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Found Inoperable Inspection

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During Inspection Interval or During Inspection Incerval 0

18 mesths i 25%

1 12 months + 25%

2 6 months T 25%

3, 4 124 dsys 125%

5, 6, 7 62 days 1 25%

>8 31 ~ days 1 25%

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The required inspection interval shall not be lengthened more than one step at a ting.

2.

During each refueling shutdown, two representative snubbers shall be

'l functionally tested for operability. Tne hydraulic snubber functional

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• l test shall verify 1

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Activation (restraining action) is achieved within the specified i

range of velocity or acceleration in both tension and ecmpression.

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Snubber bleed, or release rate, where required, is within the 1

specified range in compresucr or tantion. For snubbers specifically I

required not to displace under continuous load, the ability of the

'i snubber to withstand load without dirplacerent shallha verified.

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i 15.4.13-1 Unit 1, Amendment No. 59 e

Unit 2-Amendment Nd.; 6,4 y

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L 15.4.13 Shock Suppressors (Snubbers) (Continued) c.

For each snubber found t.o be inoperable, an additional 10% of that type snubber shall be tested *:ntil no mere failures are found or all units have been tested.

3.

The initial inspection shall be perfor=ed within '6 =enths from the date of issuance of these specifications. For the pu.7 se of i

entering the schedule in Specificatien 15.4.13.1, it shall be assumed y,

that the facility had been on a 6 month interval.

4.

A record of the service life of each snubber, the date at which the designated service life commences and the installation and

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maintenance records on which the designated service life is based 2

shall be maintained. Concurrent with the next inservice visual inspection and at least once per 18 months thereafter, the install. tion

- 15.3.13-1 and maintenance records for each snuhber listed in Table shall be reviewed to verify that the indicated service life has not l

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beer. exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the

, snubber service life shall be reqvaluated or the snubber shall be replaced or reconditioned so as to extend its service life,beyond the I

date of the next scheduled service life review. This reevaluation replacement or reconditioning shall be indicated in the records.

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All safety related snubbers are visually inspected for overall integrity and operability. The inspection will include verification of proper orientation, adequate hydraulic fluid level and proper attachment of snubber to piping and structures. To further increase the assurance of snubber reliability, i

functional tests are performed once each refueling cycle on a representative 15.4.13-2 Unit 1-Amendment No. 59 Unit 2-Amendment No. 64

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sanple of snubbers. Tr.ese tests include stroking of the unit to verify proper piston movement, lock-up, and bleed within the acceptance criteria specified by the snubber manufacturers. Observed failures en these samples shall require testing of additional units. Snubbers rated at 50,000 lbs.

or greater need not be functionally tested at their full rated capacity.

The inspection frequency is based upon =aintaining a constant level of snubber protection. Thus, the required inspection interval varies inversely with the cbserved snubber failures. The nt=ber of inoperable snubbers found during a required inspection determines the time interval for the next required inspection. However, the results of such early inspections perfc=ned before the original required ti=e interval has elapsed (nominal time less 25%)

=ay not be used to lengthen the required inspection interval. Any inspection

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whose results require a shcrter inspection interval will override the previous schedule.

The snubbers selecte.1 fer the testing and inspection mentioned in Specification 15.4.13.2 above are chosen on a rotating basis such that over a period of eleven refueling cycles all accessible snubbers will have been tes.ed.

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15.4.13-3 Unit 1-Amendment NO. 59 Unit 2-Amendment NO. 64

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Test results, in units of microcuries, for leak test performed r

pursuant'to Specification"15'.4.12.

N.

Record of annual physical inventcry verifying accountability of sources subject to Specification 15.4.12.

O.

• Records of training and qualification for current plant NRC licensed staff and key persennel.

P.

• Records of in-service inspections performed pursuant to these technical specifications.

Q.

• Records of Quality Assurance activities required by the QA Manual.

R.

• Records of reviews performed pursuant to 10 CFR 50.59.

S.

• Records of meetings of the Manager's Supervisory Staff and the Off-Site Review Committee.

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• Records of Environmental Qualification which are covered under the provisions of paragraph 15.6.12.

U.

• Records of the service life of all snubbers in accordance with Specification 15.4.13.4.

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• Starred items will be permanently retained.

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Unit 1-Amendment No. 59 15.5.10-2 Unit 2-Amendment No. 64

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TABLE 15.4.1-1 (CONTINUED)

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' Channel Dercription Check Calibrate Test Remarks

-24.

Containment Pressure.

S R

M**

Narrow range containment pressure

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+3 psig excluded) i 25.

Stram Generator Pressure S***

R M***

.2b.

Turbine First Stage Pressure S**

R M**

l 27.

Emergency Plan Radiation Survey Q

R Q

Instruments

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Environmental 14cnitors M

N.A.

N.A.

29.. Overpressure. Mitigating S

R 30.

PORV Position Indicator S

R R

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PORV Block Valvo Position Q

R N.A.

Indicator J

32.

Safety Valve Position Indicator M

R N.A.

33.

PORV Operability N.A.

R H

Performance of a channel functional test but excluding valve operation.

34.

Subcooling Margin Monitor M

R N.A.

i 35.

Undervoltage on 4KV Dus N.A.

R M**

For Auxiliary Feedwater Pump Initiation 36.

Auxiliary Feedwater Flow Rate See Remat ;.s R

N.A.

Flow Rate indication will be checked at each unit startup and shutdown 37.

Degraded 4.16 KV Voltage S

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Loss of Voltage (4.16;KV)

S R

M**

38.

a.

b.

Loss of Voltage (4.16 KV)

S R

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39. 4160 V. Frequency N.A.

R N.A.

Unit 1-Amendamnt No. 38, #4 55, 59 l

Unit 2-Amendment No. 50, 55, 66,64

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