ML20245J081
| ML20245J081 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/17/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20245J086 | List: |
| References | |
| DPR-66-A-136 NUDOCS 8903060161 | |
| Download: ML20245J081 (10) | |
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' UNITED STATES
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- g-NUCLEAR REGULATORY COMMISSION 7
- ti WASHINGTON, D. C. 20655 -
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t-i DUQUESNE' LIGHT COMPANY-OHIO EDISON COMPANY' PENNSYLVANIA POWER COMPANY
-DOCKET NO. 50-334
. BEAVER VALLEY POWER STATION,~ UNIT NO.'1
' AMENDMENT:TO-FACILITY OPERATING LICENSE Amendment'No. 136 License No. DPR-66 1
' 1. -
The Nuclear Regulatory Comission (the.Comission) has found that':
A.
The. application for amendment by Duquesne Light. Company, et al.
(thelicensee)datedApril7,1987,supplementdatedMay6,1988and revision dated November 1, 1988, comply with'the standards and requirementsoftheAtomicEnergy-Actof1954,as. amended ~(theAct)'
and the Comission'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; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon.
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 Comission's regulations and-all applicable requirements have been satisfied.
9 8903060161 890217 T
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. 2.
Accordingly, paragraph 2.C(5) of Facility Operating License DPR-66 is amended to read as follows:*
(5) The' licensee shall implement and maintain in effect all provisions of the approved' fire protection program as described in the Updated Final Safety Analysis Report (UFSAR) for the facility, subject to the following provision: the licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a
' Tire.
3.
Accordingly, the license is further amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.' 136, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
4.
This license amendment is effective on issuance, to be implemented withir:
60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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John Stolz, D rector.
V Project Directorate I-4 Division of Reactor Projects 1/II Office of Nuclear Reactor Regulation Attachments:
1.
Page 4 of License 2.
Changes to the Technical Specifications Date of Issuance: February 17, 1989 i
Page 4 is attached, for convenience, for the composite license to
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reflect this change.
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(3) Less Than Three Loop Operation Duquesne Light Company shall not operate-the. reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of the TechnicalSpecifications,AppendixA)withlessthanthree'(3) reactor coolant loops in operation until safety analyses for less than three loop operation have been submitted by the licensees and approval for less than three loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.
(4) Steam Generator Water Rise Rate Except for the purpose of performing secondary side flow stability tests, Duquesne Light Company shall, whenever the secondary side water level in a steam generator.is below the level of the feed-water sparger, limit the secondary side water level rise rate in each steam generctor to less than 1.2 inches per minute and shall reduce the rise rate to within this limit within two (2) minutes.
For the purpose of conductirg this test, the limiting cor.dition for operation specified in Specification 3.7.1.2 of the Technical Specifications, Appendix A, shall be modified to allow power lockout of the auxiliary feedwater pumps. This condition shall be removed by i
amendment of this license when Duquesne Light Company demonstrates to the satisfaction of the Commission that secondary side flow instability (water hammer) does not result in unacceptable consequences.
(5) Fire Protection Program The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report (UFSAR) for the facility, subject to the following provision: the licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
l Amendment No. 4,%,M,M,M,W,h,136
ATTACHMENT TO LICENSE AMENDMENT NO. 136 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove TS Pages Insert TS Pages 3/4 3-46 3/4 3-46 3/4 3-47 3/4 3-48 3/4 3-48a 3/4 7-35 3/4 7-36 3/4 7-37 3/4 7-38 3/4 7-39 3/4 7-40 3/4 7-41 3/4 7-42 3/4-7-43 3/4 7-44 3/4 7-45 B 3/4 3-3 B 3/4 3-3 B 3/4 7-7 8 3/4 7-7 6-2 6-2 6-5 6-5 6-23 6-23
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- INSTRUMENTATION BASES 3/4.3'.3.5 REMOTE SHUTDOWN INSTRUMENTATION The~ OPERABILITY-of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required-in the event control room habitability is lost and is consistent with General Design' Criteria 19 of 10 CFR 50.
I 3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine ' detection system ensures Lthat sufficient capability is available to promptly detect and initiate protective action in the avant of an accidental chlorine release.
The chlorine detection system will protect the control room operators by. initiating control room isolation in a. timely manner to assure the chlorine concentration in.the control room does not exceed the toxicity limit of 15 ppm by volume within 2
minutes following detection.
This capability is required to_ protect control room personnel..and is consistent with'the recommendations of Regulatory Guide 1.95, " Protection of Nuclear. Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975.
3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATIQH l
The OPERABILITY of the accident monitoring instrumentation ensurer, that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an i
accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97,
" Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident,"
December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
BEAVER VALLEY - UNIT 1 B 3/4 3-3 Amendment No.D,W,136
PLANT SYSTEMS BASES 3/4.7.13 AUXILIARY RIVER WATER SYSTEM The operability of the ARWS ensures that sufficient cooling capacity is available to bring the reactor to a cold shutdown condition in the event that a barge explosion at the station's intake structure or any other extremely remote event would render all of the normal IJVER WATER SYSTEM supply pumps inoperable.
1 I
i BEAVER VALLEY - UNIT 1 B 3/4 7-7 Amendment No.h 136
(
r ADMINISTRATIVE CONTROLS.
6.2.2 UNIT STAFF-The' unit organization shall be subject to the following:
a.
Each on duty shift shall be composed of at least theeminimum-shift crew composition shown'in Table 6.2-1.
b.
At least one licensed Operator shall be in the control _ room when fuel is in the reactor.
c.
At least two licensed Operators shall be in the control room-during reactor
- startup, scheduled Lreactor shutdown-and during recovery from reactor trips.
d.
An individual qualified in radiation protection' procedures shall be onsite when fuel is in the reactor.
e.
ALL CORE ALTERATIONS after the initial fuel loadingsshall be-directly _ supervised by either a ' licensed Senior-Reactor Operator or Senior Reactor, Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
Administrative procedures shall be developed and implemented to limit 'the working hours of unit staff who perform safety-related functions; senior reactor operators, reactor,
operators, radiation control technicians, auxiliary operators, meter and_ control repairman, and all personnel actually performing work on safety related equipment.
The objective shall be to have operating personnel work a normal 8-hour
- day, 40-hour week while the plant.is operating.
- However, in the event that unforseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
a.
An individual should not be permitted to work more'than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
b.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour
- period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.
I l
BEAVER VALLEY - UNIT 1 6-2 Amendment No.%, M0, W,136
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility and Radiation Protection staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971-for comparable positions, except for the Radiological Control Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the technical advisory engineering representative who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC)
FUNCTION 6.5.1.1 The OSC shall function to advise the Plant Manager on all matters related to nuclear safety and shall provide review capability in the areas of:
a.
nuclear power plant operations b.
radiological safety c.
maintenance d.
nuclear engineering e.
nuclear power plant testing f.
technical advisory engineering g.
chemistry h.
quality control i.
instrumentation and control COMPOSITION 6.5.1.2 The Plant Safety Review Director is the OSC Chairman and shall appoint all members of the OSC.
The membership shall consist of a
minimum of'one individual from each of the areas designated in 6.5.1.1.
OSC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions.
The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 and the maintenance individual shall meet the qualifications of Section 4.2.3.
BEAVER VALLEY - UNIT 1 6-5 Mendment No. iJ. TSO,136
-4
[.
(
- ^ ADMINISTRATIVE CONTROLS a.
ECCS Actuation,' Specifications 3.5.2 and 3.5.3.
b.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
c.
Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
d.
Seismic event analysis, Specification 4.3'.3.3.2 e.
Sealed source leakage in excess of limits, specification 4.7.9.1.3.
f.
Miscellaneous reporting requirements specified in the Action 1 Statements for Radiological Effluent Technical-Specifications.
g.
Containment Inspection Report, Specification 4.6.1.6.2.
l h.
Steam Generator Tube Inservice Inspection Results Report,I-Specification 4.4.5.5.
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five (5) years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of-principal maintenance activities, inspections,- repair and replacement of principal items'of equipment related to nuclear safety.
c.-
All Reportable Events.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of reactor tests and experiments.
f.
Records of changes made to Operating Procedures.
g.
Records of radioactive shipments.
h.
Records of sealed source leak tests and results.
i.
Records of annual phyaical inventory of all sealed source material of record.
BEAVER VALLEY - UNIT 1 6-23 Amendment No. '84, %2, M,136