ML20032D504

Amends 52 & 58 to Licenses DPR-24 & DPR-27 Respectively, Making Minor Administrative Changes & Approving Revised Organizational Structure

ML20032D504
Person / Time
Site:	Point Beach
Issue date:	08/20/1981
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20032D505	List: ML20032D504 ML20032D506 ML20032D507
References
TAC-43742, TAC-43743, NUDOCS 8111170153
Download: ML20032D504 (17)

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UNITED ST ATEs y

i NUCLE 4R REGULATORY COMMISSION

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POINT BEACH M! CLEAR PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No. 52

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License No. DPR-24 i

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

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A.

The, applications for amendment by Wisconsir Electric Power Company (the dicensee) dated February 4,1361 and April 6,1981 s

as modtfied by letter dated June 22, 1981, cwply with the standards and requirements of the Atomic Energy Act of 1954, r

as amended (the Act) and the Commission's rules and regulations set forth in 10 CfR Chapter I; i

's B.

The facility will cperate in confonnity with the applications, the provisions of the Act, and'the rules and regulations of the Commission;

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C.

There is reasonable assurance (i) that the activities authorized by this< amendment :an tie conducted without endangering the health s

and safety of the public, and (ii) that such activities will be

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' conducted in compliance.with the Conission's regulations; D. i The issuance of this amendment will not be inimical to the common defense and security or t1 the health and safety of the public; t

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E.

The issuance' of this amendment is in accordance with 10 CFR Part 2

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51 of the Commission's regulations an'd all applicable requirements s

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.B of Facility Operating License No. DPR-24 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications containad in Appendices A and B, as revised through Amendment No. 52, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

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g/ Robert A. Clark, Chief L

Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 20, 1981

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UNITED STATES NUCLEAR REGULATORY COMMISSION 3

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WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-301 POINT BEACH Nbr. LEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. DPR-27 I

1.

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

A.

The applications for amendment by Wisconsin Electric Power

. Company (the licensee) dated February 4,1981 and April 6,1981 l

as modified by letter dated June 22, 1981, comply with the

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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 applications, the. provisions of the Act, and the rules and regulations of the Commission; l

C.

There is reasonable assdrance (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 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 Commibion'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.B 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, as revised through Amendment No. S8, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION P

4/ M cg' Operating Reactors Branch #3 Robert A. Clark, Chief Division of Licensing

Attachment:

Changes to the Technical l

Specifications j'

Date of Issuance: August 20, 1981 l

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3 ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 52 TO FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 58 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A as follows:

Remove Pages Insert Pages 15.2.3-6 15.2.3-6 15.3.2-3 15.3.2-3 15.4.9-1 15.4.9-1 15.4.9-2 15.4.9-2 15.5.1-1 15.5.1-1 Figure 15.6.2-1 Figure 15.6.2-1 Figure 15.6.2-2 Figure 15.6.2-2 Figure 15.6.2-3 Figure 15.6.2-3 Figure 15.6.2-4 Figure 15.6.2-4 15.6.3-1 15.6.3-1 15.6.3-2 15.6.5-2 15.6.5-2 l

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i power distribution, the reactor trip limit, with allowance for errors,(2) is always 1,elow the core safety limit as shown on Figure 15.2.1-1.

If axial peaks are greater than design, as indicated by diff nance between top and bottom power range nuclear detectors, the reactor trip limit 4

is automatically reduced. (6) (7)

The overpower, overtemperature and pressurizer pressure system setpoints-have been revised to include effect of reduced system pressure operation (including the effects of fuel densification). The revired setpoints as given above will not exceed the revised core safety limits as shown in Figure 15.2.1-1.

The overpower li=it criteria is that core power be prevented frem reaching a value at which fuel pellet centerline melting would occur. _The reactor is prevented from reaching the over,ower limit condition by action of the nuclear overpower and overpower t.T trips.

1 The high and low pressure reactor trips limit the pressure range in whien reactor operation is permitted. The high pressurizer pressure reactor trip setting is lower than the set pressure for the safety valves ( 2485 psi.g) such that the reactor is tripped before t'ta safety valves actuate.

i A

The low pressurizer pressure reactor trip trips the reactor in the unlikely event of a less-of-coolant accident.(4)

The low flow reactor trip protects the core against CNB in the event of either a decreasing actuel measured flow in the loops or a sudden loss 1

of power to one or both reactor coolant pumps. The set point specified is consistent with the value used in the accident analysis. (6) The low loop flow signal is caused by a conditien of less than 90% flow as measured by the loop flow instrumentation. The loss of power signal is caused by 15.2.3-6 Unit No.1 - Amendment No. 52 Unit No. _ 2 - Amendment No. 58

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D.

During power operation the requirements of 15.3.2-B and C may be modified ~

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o to allow the following components to be inoperable for a specified time.

If the system is not restored to meet the requirements of 15.3.2-B or C within the time period specified, the appropriate reactor (s) except as otherwise noted, shall be placed in the hot shutdown condition. If the requirements of 15.3.2-B or C are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the appropriate reactor (s) shall be placed in the cold shutdown condition.

1.

One of the two operable charging pumps associated with an operating reactor may be removed from service provided a charging pump associated with that svne reactor is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

One of the horic acid transfer pumps designated in B.2 or C.2 may be out of service provided a pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.

For the system piping and valve operability requiremencs (B.4 and C.4):

a.

The flow path from the boric acid tank to a reactor coolant system may be out of service provided the flow patn is restored l

to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

The flow path from the refueling water storage tank to the reactor coolant system may be out cf service provided the flow path is restored to operable status within one hour. If the flow path cannot be restcred to operable status within one hour, the 1

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reactor shall be placed in cold shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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15.3.2-3 Unit No.1 - Amendment No. 52 l

Unit No. 2 - Amendment No. 58 i

15.4.9 REACTIVITY ANCMAI.IES

< 0 Applicability i

Applies to potential reactivity anomalies.

cbjective

. To require evaluation of reactivity anomalies within the reactor.

Soecification Following a normalization of the computed bcron concentration as a function of burnup, the actual boren concentration of the coolant shall be periodically, compared with the predicted value. If the difference between the observed and predicted steady-state concentrations reaches the equivalent of one percent in reactivity, an evaluation as to the cause of discrepancy shall be made and reported to the Nuclear Regulatory Commission.

Basis r

To eliminate possible errors in the calculations of the initial reactivity of the core and the reactivity depletion rate, the predicted relation between fuel burn-up and the boren concentration necessary to maintain i

adequate centrol characteristics, must be adjusted (normalized) to accurately t

I reflect actual core conditien. When full power is reached initially, and with the centrol rod groups in the desized positions, the boren concentra-don is measured and the predicted curie is adjusted to this point. As power opera-don proceeds, the measured bcron concentration is compared with the predicted concentratien and the slope of the curve relating burn-up and reactivity is ecmpared with that predicted. Tr.is process of normalisation l

rhculd be completed after about 10% of the total core burn +up.

Thereafter, 15.4.9-1 Unit No. 1 - Amendment No. 52 Uni: No. 2 - Amendment-No. 58

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actual boron concentration can be-compared with prediction, and the r=activir/

0 status of the core can be continuously evaluated. Any reactivity anomaly greater than it would be unexpected, and its occurrence would be thoroughly investigated and evaluated.

l The value of it is considered a safe limit since a shutdown '.sargin of at least 1% with the most reactive rod in the fully withdrawn positicn is always maintained.

Reference FSAR - Section 3.2.1 15.4.9-2 Unit No. 1 - Amendment No. 52 Unit No. 2 - Amendment No. 58

15.5 OESIGN TEATimES 9

15.5.1 SITE Applicability Applies to the location and extent of the reacter site.

Objective To define those aspects of the site which affect the overall saf ety of the installation.

specification The Point Beach Nuclear Plant is located on property owned by Wisconsin 6;'ectric Power company at a site en the shore of Lake Michigan, approximately The minimum distance frem the 20 Mles scutheast of the city of Green Bay.

reactor containment center line to the site exclusion boundary as define.d in 10 CFR 100.3 is 1200 meters.

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15.5.1-1 Unit No.1 - Amendment No. 43, 52 Unit No. 2 - Amendment No. 48, 58

130ARD OF DIHEC10R.9 PRESIDENT WISCCNSIN El.ECTRIC POWER COMPANY OFF-SITE EXECUTIVE VICE PRESIDEt3T REVIEW WISCONSIN ELECTRIC POWER COMPANY OTilER COMMITTEE DEPARTMENTS DIRirTOR NUCLEAR POWEH DEPARTMENT cc

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NH MANAGER HAHAGER I I SUPERINTEHnENT NUCI. EAR OPERATIONS NUCI. EAR ENGINEERING QUAI.ITY AS9tiMNCE SECTIGN SECTION DIViri10N cc aa nn MANAGER'S SUPERVISORY STAFF MANAGEMENT ORGANIZATION CilART Figure 15.6.2-1 gy

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CHfMISTRf & IILALTH FHYSICS REACWR ENGlHEERIHQ INSTBDHI;ttf & COttipOI.

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Instrunentat!cn and cheeletry a Health Reactor Engineering Shift Supervisor Duty Technice!

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Llone group shif t suboup may 1e Idle Control Operator 3.

In edelnistrattwo matters & toutine HP that the minlaum requiremente for a one per ehlft-one pedlochamle t concerne the ser reporte directly to ti.e period of Line orat to onceed 2 howre In unit in order to acco edete unospecte3 (Il Sept.-Chantatry & loestth F1yelce.

two per ehlft-two mattere of redlological healtle & safety elasence of on-duty shif t crew seeers, smil.y deterntpatlon. Interpretation, or J11 ML proelded lemediate action is taken to

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fno - HRC Senior peactor Operator 8.lconse Three per ehlft-two Technice! Advloor shall t o treated to = HpC peactor C arator 1.Scense gunite l

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The Duty Technical Adelsor le located e elt on ten Unit 1 - Amendment No. 43, 52 coon.

minut. cell to the contro Unit 2 - Amendment No. 48s 58

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Superintendent System I

Security K. Fire Protection Superintendent of Insurance and Claims (NEL-PI A and 11ML)

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FIRE PROTECTION ORGANIZATION

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15.6.3 Facility Staff Quaf'fications 9

15.6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-197L for comparable positions or as clarified in 15.6.3.2 through 15.6.3.4.

15,6.3.2 Except as provided in 15.6.3.3, either the Superintendent Chemical and Health Physics or the Health Physicist shall meet the following

. requirements:

a.

The individual shall have a bachelor's degree or the equivalent in a science or engineering subject, including some formal training in radiation protection. For purposes of this paragraph,

" equivalent" is as follows:

(1) Four years of formal schooling in science or engineering; or (2)

Four years of applied radiation protection experience at a nuclear facility; or (3) Four years of operational or cechnical experience or training in nuclear power; or (4) Any combination of the above totalling four years.

b.

Except as provided in d., below, the individual shall have at least five years of professional experience in applied radiation protection. A master's degree in a related field is equivalent to one year of experience and a doctor's degree in a related field ia equivalent to two years of experience.

c.

Except as provided in d., below, at least three of the five years of experience shall be in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power plants.

l d.

If the individual has a bachelor's degree specifically in health physics, radiological health, or radiation protection, at least l

three years of professional experience is required; if the l

individual has a master's or a doctor's degree specifically in health physics, radiological health, or radiation protection, at least two y2ars of professional experience is required. This experience shall be in applied radiation protection in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power plants, i

15.6.3-1 Unit No.1 - Amendment No. 43, Unit No. 2 - Amendment No. 48, i

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15.6.3.3 In the event the position of Superintendent - Chemical and Health g

Physics or Health Physicist is vacated and neither the remaining individual nor the proposed replacement meets the qualifications of 15.6.3.2, but one of these individuals is determined to be otherwise well qualified, then concurrence of NRC shall be sought in approving the qualification of that individual.

15.6.3.4 The Duty Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transienra and sceidents. The Duty Technical Advisor shall also receive training in plant design and layout inJ1uding the capabilities of instrumentation and controls in the control room.

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l 15.6.3-2 Unit No. 1 - Amendment No. 52 Unit No. 2 - Amendment No. 58

I COMPOSITION 15.6.5.2.2 The Manager's Supervisory Staff shall be selected from the following:

Chairman: Manager - Nuclear Operations Member:

General Superintendent Member:

Superintendent - Operations Member:

Superintendent - Maintenance & Coastruction Member:

Superintendent - Engineering, Quality and Regulztory Member:

Superintendent - Chemistry and Health Physics Member:

Superintendent - Technical Services Member:

Superintendent - Instrumentation and Control Member:

Health Physicist Member:

Superintendent - Reactor Engineering Member:

Superintendent - Training-ALTERNATES 15.6.5.2.3 Alternate members shall be appointed in writing by the MSS Chairman to serve on a temporary basis; however, no more than two alternates shall participate in MSS activities at any one time.

MEETING FREQUENCY 15.6.5.2.4 The MSS shall meet at least once per calendar month and as convened by the MSS Chairman.

QUORUM 15.6.5.2.5 A quorum of the HSS shall consist of the Chairman and four members including alternates.

RESPONSIBILITIES 15.6.5.2.6 The Manager's Supervisory Staff shall:

a) Review existing and propcsed normal, abnormal and emergency operating procedures. Review maintenance procedures and proposed changes to these procedures and other procedures or changes thereto es determined by the Manager to affect plant operational safety.

(Re:

Section 15.6.7 for area of review.)

15.6.5-2 Unit No. 1 - Amendment No. 50, 52 i

l Unit No. 2 - Amendment No. 56, 58

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