ML20093C949
| ML20093C949 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/21/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093C953 | List: |
| References | |
| TAC-54200, TAC-54201, NUDOCS 8410110013 | |
| Download: ML20093C949 (13) | |
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. WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 t.i POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 27, 1984, complies with the.
standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Coranission'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 the Commission;
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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 requirehreats have been satisfied.
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2.
According1[,thelicenseisamendedbychangestotheTechnical 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 s
The-Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85
, are hereby incorporated in the license.- The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 20 days from the date of issuance.
FCR THE NUCLEAR REGULATCRY COMMISSION
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/pAlames R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 21, 1984 4
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NUCLEAR ' EGULATORY COMMISSION R
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WISCONSIN ELECTRIC POWER COMPANY 3
DOCKET NO. 50-301 e
POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO-FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (thelicensee)datedJanuary 27, 1984, 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 the Comission;
,s C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted with'out endangering the health,
and safety of the public, and (ii) that such activities will.be conducted 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;~
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of.the Commission's regulations and all applicable recuirements have been satisfied.
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2.
According1bthelicenseisamendedbychancestotheTechnical Specifications as indicated in the attachment : ) 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.89
, are hereby incorporated in the license.
The licensee shall operate the facility.in accordance with the Technical Specifications.
3.
This license amendment is effective 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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fMmes R. Miller, Chief
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Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 21, 1984 4
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. ?S' ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 85 TO FACILITY OPERATING LICENSE 'NO. DPR-24 AMENUilENT NO. 89 TO FACILITY OPERATING LICENSE NO. DPR-27
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DOCKET NOS. 50-266 AND 50-301 W
Revise Appendix A as follows:
Remove Page
- Insert Page 15-11 15-ii 15.1-1 15.1-1 15.1-2 15.1-2 15.6.5-3 15.6.5-3,
15.6.5-4 15.6.5-4 15.6.5-6 15.6.5-6 1.5. 6. 6-1 15.6.6-1 15.6.9-4 35.6.9-4 15.6.9-5 15.6.9-6 15.6.9-7 W
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TABLE OF CONTENTS (Contin'ued')
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Section Title Page 15.5 Design Features 15.5.1-1 15.5.1 Site 15.5.1-1 15.5.2 Containment 15.5.221 15.5.3 Reactor 15.5.3-1 15.5.4 Fuel Storage 15.5.4-1 15.6 Administrative Controls 15.6.1/2-1 15.6.1 Responsibility 15.6.1/2-1
- 15.6.2 Organization 15.6.1/2-1 Facility Staff Qualifications 15.6.3/4/5-1 15.6.3 15.6.4 Training-15.6.3/4/5-1 15.6.5 Review and Audit 15.6.3/4/5-1 15.6.6 Reportable Event Action 15.'6.6-1 l
15.6.7 Action To Be Taken If A Safety Limit Is Exceeded 15.6.7-1 15.6.8 Plant Operating Procedures 15.6.8-1 15.6.9.
Plant Reporting Requirements 15.6.9-1 15.6.10 Plant Operating Records 15.6.10-1 15.6.11 Radiation Protection Program 15.6:11-1 i
Unit 1 Amendment No. 22, 85 15-ii Unit 2 - Amendment No. 25, 89
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- 15. TECHNICAL SPECIFICATIONS AND BASES l
1 15.1 DEFINITIONS The definitions for frequently used terms which are applied to the Point Beach Nuclear Power Plant, Units No. 1 and 2, are stated below.
a.
Reportable Event A Reportable Event shall be any of those conditions specified in Section 50.73 to Title 10 Code of Federal Regulations (10 CFR) Part 50.
b.
Quadrant Power Tilt
_ Quadr. ant to average power tilt is expressed in percent as defined by the following equation:
100x(I power in any core quadrant
_1 average for all quadrants c.
Operability A system, subsystem, train, component,- or device shall be operable or have operability when it is capable of performing its function (s) as analyzed in the safety analysis report; Implicit in this definition is the assumption that necessary instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment required for the system, subsystem, train, component or device to perform its function (s) are capable of performing their related support function (s).
Unit 1 - Amendment No. O, 2, 85 Unit 2 - Amendment No. /S, S, 89 15.1-1
d.
"d'ontainment Integrity *
' Containment integrity is defined to exist when:
1)
All non-automatic containment isolation valves and blind 9-flanges are closed as required.
2)
The equipment hatch is properly closed.
3)
At least one door in each personnel. air lock is properly closed.
4)
All automatic containnent isolation valves are operable or are secured closed.
5)
The uncontrolled containment leakage satisfies Specifica-tion 15.4.4.
e.
Protective Instrumentation Logic l
1)
Analog Channel An analog channel is an arrangement of components and,, ;.. -
modules as required to generate a single protective action signal when required by a plant condition. An analog l
channel loses its identity where ~ single action signals are combined.
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- Containment isolation valves are discussed in FFDSAR Section 5.2.
Unit 1 - Amendment No. $3, E0,85 Unit 2 - Amendment No. !S, EE,89 15.1-2
4 b)
Review all proposed tests and experiments related to safety and the results thareof whdn applicable, c)
Review all proposed changes to Technical Specifications.
d), Review all proposed changes or modifications to plant systems or equipment where clianges would require a change in. operating or emergency procedures or that affect nuclear safety.
e)
Periodically review plant operations for industrial and nuclear safety hazards.
f)
Investigate violations or suspected violations of Technical Specifications, such investigations to include reports, evalua,-
tions, and recomendations to prevent recurrence, to the Exec-uti've Vice. President and to the Chairman of the Off-Site Review Committee.
g)
Perform special reviews and investigations and prepare reports thereon as requested by the Chairman"of the Off-Site Review Committee.
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h)
Investigate, review, and report on all_ repo table events.
l 1)
Cause to be ' conducted periodic drills on emergency proce~dures, including evacuation (partial or complete) of the site and,.
check adequacy of communications with off-site support groups.
j)
Review the Facility Fire Protection Program and implementing procedures at least once per 24 months.
AUTHORITY 15.6.5.2.7 a) The Supervisory Staff shall serve as advisory to the Manager -
Nuclear Operations.
Unit 1 - Amendment No. A3,85 Unit 2 - Amendment No. JE,89 15.6.5-3 L
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4 b)
The Supervisory Staff shall, recommend to the Manager approval U.or disapproval of proposals.under items a) through d) above.
In the event of disagreement between a majority of the Super-
"visory Staff and decisions by the Manager, the course' of action will be determined by the Manager and the disagreement. recorded
.in the Staff minutes.
Records of the disagreement will be included in the minutes sent for review to the Off-Site Review Committee and the Executive Vice President.
c)
The Supervisory Staff shall make tentative recommendations-as
-to whether or not proposals considered by the Staff involve unreviewed safety questions. These recommendations shall be-subject to review and further recommendations by the Off-Site Review Committee. Minutes shall be-kept'of all meetings-of ",
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the Staff and copies shall be sent to the Executive Vice Presi-dent and to the Chairman of the Off-Site Review Committee.
d)
The Supervisory Staff shall review and approve the contents'. -
of a report for each reportable event. This repor.t shall be prepared and submitted pursuant to the requirements of Section i
50.73 to 10 CFR Part 50. Copies of all such reports shall be submitted to the Executive Vice President and to the Off-Si.te Review Committee.
RECORDS 15.6.5.2.8 The Manager's Supervisory Staff shall maintain written minutes of each meeting and copies shall be provided to the Executive Vice President and Chairma.', Off-Site Review Committee.
Unit 1 - Amendment No f3, 85
'15.6.5-4 Unit 2 - Amendment No. AS, 89 i
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'MEETIfiG FREQUENCY ~
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15.6.5.3.5- -Th,e OSRC'shall1 meet at least o'nce per calendar quarter during the i -
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- initial year of facility ~ operation following fuel-loading and at least twice per ' year at approximately six month intervals thereafter.
QUORUM' p
15.6.5.3.6 A quorum of OSRC r..sall consist of the Chairman or his' designated alternate and three members.
No more than a minority of the quorum chall have 1-p
_ line responsibility for operation of the facility.
REVIEW
-15.6.5.3.7 The OSRC shall review:
a)
- The safety evaluations for 1) changes to procedures, equipment or systems, and 2) tests or experiments completed under th.e j
provision of 10 CFR, Section 50.59, to verify that such actions did not constitute an unrevi'ewed safety question.
b)
Proposed changes to procedures, equipment or systems which f_.-
involve an unreviewed safety question.as defined in 10 CFR, Section 50.59.
c)
Proposed tests or experiments which involve an.unreviewed; safety question as defined in 10 CFR Section 50.59.
d)
Proposed changes in Technical Specifications or Licenses.
I e)
Violations of applicable statutes, codes, regulations, orders,
' Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f)
Significant operating abnormalities or deviations from normal t
and expected performance of plant equipment that affect e
r nuclear safety.
g)
All reportable events.
Unit 1 - Amendment No.19, 85
~ Unit 2 - Amendment No. M, 89 15.6.5-6
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- 15.6'6 REPORTABLE EVENT ACTION Specificatiok c
Thelfollowing a,ction.shall be'taken for Reportable Events:
A.
The: Commission shall be notified and a report submitted pursuant to the: requirements:of Section 50.73 to 10 CFR Part 50, and B.
Each Reportable Event shall be reviewed by the Manager's Supervisory Staff (MSS) and submitted to the Off-Site Review Committee (OSRC) and the Vice President.- Nuclear Power.
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9-Unit 1 - Amendment No. 43, 85 Unit 2 - Amendment No. 48,89 15.6.6-1 w-v--
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15.6.9.2 DELtTED 15.6.9.3 Unique Reportina Requirements The'following written reports shall be submitted to the Director, Office of Nuclear Reactor Regulation, USNRC:
A.
Each integrated leak test shall be the subject of a summary technical report, including results of the local leak rate tests and isolation valve leak rate tests since the last report. The report shall include an& lysis and interpreta-tions of the results which demonstrat,e compliance with specified leak rate limits.
B.
DELETED C.
Submission of a report within 60 days after January 1 and "
after July 1 each year for the six-month period or fraction thereof, ending June 30 and December 31 containing:
Unit 1 - Amendment No.19,85 Unit 2 - Amendment No. E3,89 15.6.9-4 (NEXT PAGE IS 15.6.9-8)
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