ML20206M083
| ML20206M083 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/12/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206M090 | List: |
| References | |
| NUDOCS 8608200453 | |
| Download: ML20206M083 (3) | |
Text
_ _ _ _ _
h UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION 5
j WASHINGTON, D. C. 20555
\\...../
DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated October 8,1984, and revised by letter dated February 3,1986, 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 application, the provisions of the Act, and the rules and regulations of the Comission; 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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is 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:
$0$$$f0812 0334 PDq
(?) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.105, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective on issuance, to be implemented no later than 60 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Lester S/ Nbenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: August 12, 1986
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.105 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pa g Insert Pages 3/4 4-32 3/4 4-33 B 3/4 4-11 3/4 3-51 3/4 3-51 3/4 3-52 3/4 3-52 1
3/4 6-20 3/4 6-20 6-13 6-13 i
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.12 All reactor coolant system vent valves, powered from emergency buses, shall be OPERABLE
- and closed ** for each vent path from the following locations:
a.
Reactor Vessel Head b.
Pressurizer Steam Space APPLICABILITY:
MODES 1, 2, 3 and 4 1
ACTION:
a.
With at least one vent path from each of the above locations OPERABLE and one or more power operated vent valves inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable valve (s) is maintained closed with power removed or with the manual isolation valve closed.
Power operation may continue until the next scheduled outage, at which time all reactor coolant system vent valves shall be OPERABLE prior to entry into MODE 1.
The provisions of Specification 3.0.4 are not applicable.
b.
With all vent paths from one of the above locations inoperable, maintain the inoperable valves closed with power removed or with the manual isolation valves
- closed, restore at least one of the inoperable vent paths to OPERABLE status within 30 days, or, be in HOT STANDBY within 6
hours and in COLD SHUTDOWN within the i
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With all vent paths from both of the above locations inoperable, maintain the inoperable valves closed with power removed or close the manual isolation valves, and restore at least one vent path.from one of the above locations to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS
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4.4.12 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months by:
BEAVER VALLEY - UNIT 1 3/4 4-32 Amendment No.105 c--
n-
REACTOR COOLANT SYSTEM SURVEILLANCF_ REQUIREMENTS (Continued) 1.
Verifying all manual isolation valves in each vent path are locked or sealed in the open position.
2.
Cycling each valve in the vent path through at least one complete cycle of full travel from the control room.
3.
Verifying flow through the reactor coolant system vent path to the Pressurizer Relief Tank.
For purposes of this specification an inoperable vent valve is defined as:
a valve which exhibits leakage in excess of Specification 3.4.6.2
- limits, or cannot be opened and closed on demand, or does not have its normal emergency power supply OPERABLE.
These valves may be operated for required venting operations and leak testing in Modes 3 and 4.
BEAVER VALLEY - UNIT 1 3/4 4-33 Amendment No.105
REACTOR COOLANT SYSTEM BASES 3/4.4.12 REACTOR COOLANT SYSTEM VENTS Reactor Coolant System Vents are provided to exhaust noncondensible and/or steam from the primary system that could inhibit natural gases circulation core cooling.
The OPERABILITY of at least one reactor coolant system vent path from the reactor vessel head and the pressurizer steam
- space, ensures the capability exists to perform this function.
The valve redundancy of the reactor coolant system vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply or control system does not prevent isolation of the vent path.
The
- function, capabilities, and testing requirements of the reactor systems are consistent with the requirements of coolant system vent Item II.B.1 of NUREG-0737,
" Clarification of TMI Action Plan Requirements", November 1980.
l I
BEAVER VALLEY - UNIT 1 B 3/4 4-11 Miendment No.105
TABLE 3.3-11 5
5 ACCIDENT MONITORING INSTRUMENTATION Mw
$r TOTAL NO.
MINIMUM CHANNELS M
OF CHANNELS OPERABLE K
I C
1.
Pressurizer Water Level 3
2 e
2.
Auxiliary Feedwater Flow Rate 1 per steam 1 per steam r
generator generator 3.
Reactor Coolant System Subcooling Margin Monitor 1
0 4.
PORV Accoustical Detector Position Indicator 2/ valve
- 1/ valve S.
PORV Limit Switch Position Indicator 1/ valve 0/ valve Y
6.
PORV Block Valve Limit Switch Position Indicator 1/ valve 0/ valve 7.
Safety valve Accoustical Detector Position Indicator 2/ valve
- 1/ valve w
8.
Safety Valve Temperature Detector Position Indicator 1/ valve 0/ valve 2
1 9
Contalment Sump Wide Range Water Level 2
0 k
10.
Containment Wide-Range Pressure R
E '
E One Detector Active, Second Detector Passive CD u,
m TABLE 4.3-7 M
N ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS P
Q CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION C
3 1.
Pressurizer Water Level M
R 2.
Auxiliary Feedwater Flow Rate S/U(1)
R 3.
Reactor Coolant System Subcooling Margin M
R 4.
PORV Accoustical Detector Position Indicator M
R w
5.
PORV Limit Switch Position Indicator M
R h
6.
PORV Block Valve Limit Switch Position Indicator M
R 7.
Safety Valve Accoustical Detector Position Indicator M
R 8.
Safety Valve Temperature Detector Position Indicator M
R k
9.
PORV Control Pressure Channels (PT-RC-444, 445)
M R
a 2
10.
Containment Sump Wide-Range Water Level M
R 5
11.
Containment Wide-Range Pressure N/A R
2 D
e (1) Channel check to be performed in conjunction with Surveillance Requirement 4.7.1.2.a.9 u
following an extended plant outage.
CONTAINMENT SYSTEMS 1
3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two separate and independent wide-range containment hydrogen analyzers shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACTION:
a.
With one wide-range hydrogen analyzer inoperable, l
restore the inoperable analyzer to OPERABLE status within 30 days or be in HOT STANDBY within the next 12
- hours, b.
With both wide-range hydrogen analyzers inoperable, restore at least one wide-range hydrogen analyzer to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS i
4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by:
a.
Performing a
CHANNEL CALIBRATION using sample gases containing:
1.
One volume percent hydrogen, balance nitrogen, and 2.
Four volume percent hydrogen, balance nitrogen.
BEAVER VALLEY - UNIT 1 3/4 6-20 Amendment No.105
ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two (2) members of the plant management staff, at least one (1) of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the OSC and approved by the Plant Superintendent within 14 days of implementation.
6.8.4 A Post-Accident monitoring program shall be established, implemented, and maintained:
A program which will provide the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples following an accident.
The program shall include the following:
(i)
Training of personnel, (ii)
Procedures for sampling and analysis, and (iii)
Provisions for maintenance of sampling and analysis equipment.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of
~
Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
STARTUP REPORTS 6.9.1.1 A sumary report of plant startup and power escalation testing will be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfomance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details requested in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or comencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
BEAVER VALLEY - UNIT 1 6-13 Amendment No. 191, 105
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