ML20129D176
| ML20129D176 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/10/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20129D178 | List: |
| References | |
| NUDOCS 8507290696 | |
| Download: ML20129D176 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY
_P_ENNSYLVANIA POWER COMPANY DOCKET NO. 50 334 BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 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 Ifcensees)
I dated March 21, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the i
l Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will o>erate in conformity with the application, the provisions of tie Act, and the rules and regulations of the Comission; C.
Thereisreasonableassurance(f)thattheactivitiesauthorized 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.
l 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license l
amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows!
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-2 (2)LTechnicalSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 95, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technicai Specifications.
3.
This amendment is effective upon issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION JO W.!kbh< j Operating Reactors Branch #1-Steven A. Varga, Chief 1
Division of Licensing i
Attachment:
Changes to the Technical l
Specifications i.
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Date of Issuance: July 10, 1985 1
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 95 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages V
V XII XII XVIIa XVIIa 3/4 1-16 3/4 1-16 l
3/4 5-8 3/4 5-9 3/4 12-8 3/4 12-8 B3/4 1-2 83/4 1-2 B3/4 5-2 B3/4 5-2 6-25 6-25 6-26
, _ _... _ ~, _ _ _ _ _ _.
t INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4.4.2 SAFETY VALVES - SHUTD0WN...............................
3/4 4-5 l
3/4.4.3 SAFETY VALVES - 0PERATING..............................
3/4 4-6 1
i 3/4.4.4 PRESSURIZER............................................
3/4 4-7 3/4.4.5 STEAM GENERATORS.......................................
3/4 4-8 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems..............................
3/4 4-11 O pe ra tiona l L ea ka g e....................................
3/4 4-13 Pressure Isolation Va1ves..............................
3/4 4-14a 3/4.4.7 CHEMISTRY..............................................
3/4 4-15 3/4.4.8 SPECIFIC ACTIVITY......................................
3/4 4-18 3/4.4.9 PRESSURE / TEMPERATURE LIMITS, Reactor Coolant System.................................
3/4 4-22 Pressurizer............................................
3/4 4-27 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components..................
3/4 4-28
_3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS...........................................
3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - Tavg 350*F.........................
3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,yg <
350*F.........................
3/4 5-6 3/4.5.4 BORON INJECTION SYSTEM Boron Injec ti on Ta n k...................................
3/4 5-7 3/4.5.5 (Moved to 3.1.2.8.b )
BEAVER VALLEY - UNIT 1 V
Amendment No. 95
INDEX BASES SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS.............................................
B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS..............................
B 3/4 5-1 3/4.5.4 BORON INJECTION SYSTEM...................................
B 3/4 5-1 3/4.5.5 (Moved to Bases Section 3/4.1.2) 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT......................................
B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLINGSYSTEMS.....................
B 3/4 6-2 4
3/4.6.3 ' CONTAINMENT ISOLATION VALVES.............................
B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTR0L..................................
B 3/4 6-3 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROLSYSTEM...................
B 3/4 6-3 BEAVER VALLEY - UNIT 1 XII Amendment No. 95
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INDEX ADMINISTRATIVE COh*IROLS SECTION PACE ANNUAL RADIOLOGICAL ENVIRONMENTAL REP 0RI....................
6-18 SDiI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT............. 6-21 6.9.2 SPECIAL REPORTS......................................
6-22 6.10 RECORD RETENTION......................................
6-23 6.11 RADIATION PROTECTION PR0 CRAM..........................
6-25 6.12 HIGH RADIATION AREA...................................
6-25
,5.13 (Deleted )
_6_.14 PROCESS CONTROL PROGRAM (PCP).........................
6-27 6.15 0FFSITE DOSE CALCULATION MANUAL.......................
6-27 6.16 MAJOR CHANCES TO RADI0 ACTIVE WASTE TREATMENT SYSTDiS..
6-28 6.17 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.........
6-31 BEAVER VALLEY - UNIT 1 XVIIa Amendment No. 95
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REACTIVITY CONTROL SYSTEMS i
BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 as required by Specification 3.1.2.2.As a minimum, the following borated wa A boric acid storage system with:
l a.
1.
A minimum contained volume of 11,336 gallons, i
2.
Between 7000 and 7700 ppm of boron, and 3.
A minimum solution temperature of 65'F.
b.
The refueling water storage tank with:
1.
A contained volume between 439,050 gallons and 441,100 gallons of borated water, 2.
A boron concentration between 2000 and 2100 ppm, and 3.
A minimum solution temperature of 43*F.
APPLICABILITY:
MODES 1, 2, 3 & 4.
_ ACTION:
With the boric acid storage system inoperable, restore the storage a.
system 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 at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1%
ak/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the boric acid storage system to OPERABLE status within the next 7 days or be 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 />.
b.
With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 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 4.1.2.8 Each borated water source shall be demonstrated OPERABLE:
BEAVER VALLEY - UNIT I 3/4 1-16 Amendment No. 95
TABLE 4.12-1 (Continued) t
_ TABLE NOTATION The LLD is the smallest concentration of radioactive materi a.
sample that will be detected with 95% probability with 5% probabil-
"real" signal.ity of falsely concluding that a blank observation represents For a particular measurement system (which may include radiochemical separation):
4*
Ib LLD l
=
(E)(V)(2.22)(Y)exp(-AaT) where:
LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);
S
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is the standard deviation of the background counting rate or b
of the counting rate of a blank sample as appropriate (as counts per minute);
E is the counting efficiency (as counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radienuclide; AT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environ-mental samples, not plant effluent samples).
The value of S used in the calculation of the LLO for a h
detection systenrshall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclide determined by gama-ray spectrometry, the back-ground shall include the typical contributions of other radionuclides normally present in the samples (e.g.,
potassium-40 in milk samples).
AT should be used in the calculations. Typical values of E, V, Y and BEAVER VALLEY - UNIT 1 3/4 12-8 Amendment No. 95
3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) (Continued) fuel cycle.
beginning and near the end of each fuel cycle is adequate value since this coefficient changes slowly due principally to the reduction in RCS baron concentration associated with fuel burnup.
3/4.1.1.5 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be nede critical with the Reactor Coolant System average temperature less than 541'F.
limitation is required to ensure 1) the moderator temperature coefficient is This within its analyzed temperature range, 2) the pressurizer is capable of be in an OPERABLE status with a steam bubble, 3) the reactor pressure vessel is above its minimum NDTT temperature and 4) the protective instrumentation is within its normal operating range.
3/4.1.2 BORATION SYSTEMS:
available during each mode of facility operation.The boron injection The com perform this function include 1) borated water sources, 2)ponents required to separate flow paths, 4 charging pumps, 3) systems, and 6) an emer)gency power supply from OPERABLE and redundant boron injection systems are provided to e capability in the event an assumed failure renders one o ble.
safety from injection system failures during the repair period. c reactivity considerations while operating isThe required volume of w 424,000. gallons.
The associated technical specification limit on the refueling water storage tank has been established at 441,100 the NPSH requirements of the ECCS system. gallons to account for reactivity con The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA.
- 1) sufficient water is available within containment to permit cooling flow to the core, and 2) the reactor will remain suberitical in the cold condition following mixing of the RWST and the RCS water volumes with all assumptions are consistent with the LOCA analysis. control rods in These BEAVER VALLEY - UNIT 1 B 3/4 1-2 Amendment No. 95
EMERGENCY CORE COOLING SYSTEMS s
BASES BORON INJECTION SYSTEM (Continued)
The analysis of a main steam pipe rupture is performed to demonstrate that the following criteria are satisfied:
1.
Assuming a stuck rod cluster control assembly, with or without offsite power, and assuming a single failure in the engineered safeguards, there is no consequential damage to the primary system and the core remains in place and intact.
2.
Energy release to containment from the worst steam pipe break does not cause failure of the containment structure.
3.
Radiation doses are not expected to exceed the. guidelines of the 10CFR100.
The limits on injection tank minimum volume and boron ensure that the assumptions used in the steam line break analysis are met.
concentration to the time at which precipitation of a 7700 ppm boric acid s occur without benefit of the building heating system.
Verifying the recirculation flow path and stagnant piping temperatures, when the Boron Injection Flow Path temperature is less than 120*F and greater than 65'F, by menitoring the ambient air temperatures in the building areas containing that piping provides assurance that baron precipitation will not occur.
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l BEAVER VALLEY - UNIT 1 B 3/4 5-2 Amendment No. 95
ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM i
Procedures for personnel radiation protection shall be prepared consistent l
with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HICH RADIATION AREA 6.12.1 In lieu of the " control device'! or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 arem/hr but less than 1000 arem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiological Work Permit
- or Radiological Access Control J
Permit.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made af ter the dose rate level in the area has been established and personnel have been made knowledgeable of them.
An individual qualified in radiation protection procedures who c.
is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform pariedic radiation surveillance at the frequency specified by a facility health physics supervisor in the Radiological Work Permit or Radiological Access Control Permit.
6.12.2 The requirements of 6.12.1, above, also apply to each high radiation area in which the intensity of radiation is greater than 1000 mram/hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shif t Superviso'r on duty and/or a facility health physics supervisor.
Health physics personnel, or personnel escorted by health physics personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
BEAVER VALLEY - UNIT 1 6-25 (next page is 6-27) f Amendment No. 95
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