ML20052E046
| ML20052E046 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/27/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052E048 | List: |
| References | |
| NUDOCS 8205100039 | |
| Download: ML20052E046 (14) | |
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UNITED STATES 4
NUCLEAR REGULATORY COMMISSION
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MSHINGTON, D. C. 20555 h, ~ n VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. DPR-32 1.
The Nuclear Regulatory Comission (.the Commission) has found that:
A.
The applications for amendment by Virginia Electric and Power Company (the licenseel dated December 28, 1979 and February 26, 1980, comply with the standards and requirements of the Atcmic 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 applications, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (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 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 8205100039 820427 PDR ADOCK 05000280 P
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. 2.
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-32 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised througn Amendment No. 77 are hereby incorporated in the license. The licensee shall
~~erate the facility in accordance with the Technical ecifications.
3.
This license amendment is effective as of the date of its issuance.
F THE NU E REGULATORY COMMISSION Jaa u A Ref S even A.
- arga, Operating Reactors (B anch #1 Divisicn of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 27,1982
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UNITED STATES NUCLEAR REGULATORY COMMISSION 2,f.)n[?E
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WASHINGTON, D. C. 20$55 i'\\l
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING L ICENSE Amendment No. 78 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Virginia Electric and Power Company (the licenseel dated December 29, 1979 and February 26, 1980 comply Lith 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 appifcations, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance til that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (111 that such' activities _will be conducted in compliance with the Commission's regulations;
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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 requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-37 is hereby amended to read as follows:
B.
Technical Sp'cifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 78, 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 NUCL ARo EGULATORY COMMISSION
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.a Operating Reactors r ch #1 Division of Licensi
Attachment:
Changes to the T,echnical Specifications N
Date of Issuance: April 27,1982 l
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 77 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 78 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 3.6-1 3. 6-1 3.6-2 3.6-2 3.6-3 3.6-3 3.6-4 3.6-4 3.6-5 3.6-5 3.6-6 4.8-1 4.8-1 4.8-2 4.8-2 4.8-3
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TS 3.6-1 3.6 TURBINE CYCLE Applicability Applies to the operating status of the Main Steam and Auxiliary Feed Systems. '
objective To define the conditions required in the Main Steam System and Auxiliary Feed System for protection of the steam generator and to assure the capability to remove residual heat from the core during a loss of station power.
Specification A
Lunit,'s_ Reactor Coolant System temperature or pressure shall not exceed 350*F or 450 psig, respectively, or the reactor shall not be critical unless the five main steam line code safety valves associated with each steam generator in unisolated reactor coolant loops are operable.
B.
To assure residual heat removal capabilities, the following conditions shall be met prior to the commencement of any unit operation that would establish reactor coolant system conditions of 350*F and 450 psig which would preclude operation of the Residual Heat Removal System.
Amendment Nos. 77 & 78
TS 3.6-2 1.
Two motor driven auxiliary feedwater pumps shall be operable and one of three auxiliary feedwater pumps for the opposite unit shall be operable.
2.
A minimum of 96,000 gal of water shall be available in the tornado missile orotected condensate storage tank to supply emergency water to the auxiliary feedwater pump suctions. A minimum of 60,000 gal of water shall be available in the tornado protected condensate storage tank of the opposite unit to supply emergency water to the auxiliary feedwater pump suction of that unit.
3.
All main steam line code safety valves, associated with steam generators in unisolated reactor coolant loops, shall be operable.
C.
Prior to reactor power exceeding 107., the steam driven auxiliary feedwater pump shall be operable.
D.
System piping, valves, and control board indication required for the operation of the components enumerated in Specification B. 1, 2, 3.
and C shall be operable.
E.
The iodine - 131 activity in the secondary side of any steam generator, in an unisolated reactor coolant loop, shall not exceed 9 curias. Also the specific activity of the secondary coolant system shall be 6 0.10 pCi/cc DOSE EQUIVALENT I-131.
If the specific activity of the secondary coolant system exceeds 0.10 pCI/cc DOSE EQUIVALENT I-131, the reactor shall be shut down and cooled to 500*F or less within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after detection and in the Cold Shutdown Condition within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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knendment Nos. 77 4 78
TS 3.6-3 F.
With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two motor driven feedwater pumps and one steam driven feedwater, pump) 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 shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
G.
The requirements of Specification B2 above may be modified to allow utilization of protected condensate storage tank water with the auxiliary steam generator feed pumps provided the water level is maintained above 60,000 gallons, sufficient replenishment water is available in the 300,000 gallon condensate storage tank, and replenishment of the protected con-densate storage tank is commenced within two hours after the cessation of protected condensate storage tank water consumption.
Basis A reactor which has been shutdown from power requires removal of core residual heat. While reactor coolant temperature or pressure is greater than 350*F or 450 psig, respectively, residual heat removal requirements are normally satis-fled by steam bypass to the condenser.
If the condenser is unavailable, steam can be released to the atmosphere through the safety valves, power operated relief valves, or the 4 inch decay heat release line.
The capability to supply feedwater to the generators is normally provided by the operation of the Condensate and Feedwater Systems.
In the event of complete loss of electrical power to the station, residual heat removal would continue to be assured by the availability of either the steam driven auxiliary j
feedwater pump or one of the motor driven auxiliary feedwater pumps and the i;
Amendment Nos. 77 & 78
TS 3.6-4 110,000 gallen condensate storage tank.
In the event of a fire which would render the auxiliary feedwater pumps inoperable, residual heat removal would continue to be assured by the availability of either the steam driven auxiliary feedwater pump or one of the motor driven auxiliary feedwater pumps fror the opposite unit.
A minimum of 92,000 gallons of water in the 110,000 gallon condensate tank is sufficient for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of residual heat removal following a reactor trip and loss of all off-site electrical power.
If the protected condensate storage tank level is reduced to 60,000 gallons, the immediately available replenishment water in the 300,000 gallon condensate tank can be gravity-feed to the protected tank if required for residual heat removal. An alternate supply of feedwater to the auxiliary feedwater pump suctions is also available from the Fire Protection System Main in the auxiliary feedwater pump cubicle.
The five main steam code safety valves associated with each steam generator have a total combined capacity of 3,725,575 pounds per hour at their individual set pressure; the total combined capacity of all fifteen main steam code safety valves is 11,176,725 pounds per hour. The ultimate power rating steam flow is 11,167,923 pounds per hour. The combined capacity of the safety valves required by Specification 3.6 always exceeds the total steam flow corresponding to the maximum steady-state power than can be obtained during one, two, or three reactor coolant loop operation.
The availability of the auxiliary feedwater pumps, the protected condensate storage tas.k. and the main steam line safety valves adequately assures that suf ficient residual heat removal capability will be available when required.
Amendment Nos. 77 & 78
TS 3.6-5 The limit on steam generator secondary side iodine - 131 activity is based on limiting inhalation thyroid dose at the side boundary of 1.5 rem after a postulated accident that would result in t:he release of the entire contents of a unit's steam generators to the atmosphere.
In this accident, with the halogen inventories in the steam generator being at equilibrium valves, I-131 would contribute 75 percent of the resultant thyroid dose at the site boundary; the remaining 25 percent of the dose is from other isotopes of iodine. In the analysis, one-tenth of the contained iodine is assumed to reach the site boundary, making allowance for plate out and retention in water droplets.
The inhalation thyroid dose at the site boundary is given by:
Dose (Rem) = (C) (X/Q) (D / ) (B.R. )
(.75) (P.F.)
where:
C = steam generator I-131 activity (curies)
X/Q = 8.14 x 10- sec/m 0
Dd A = 1.48 x 10 rem /Ci for I-131 g
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B.R. = breathing rate, 3.47 x 10 m /sec.
from TID 14844 P.F. = plating factor, 10 Assuming the postulated accident, the resultant thyroid dose is 1.5 rem.
The steam generator's specific iodine - 131 activity limit is calcular.ed by dividing the total activity limit of 9 curies by the water volume of a steam generator. A full power, with a steam generator water voume of 47.6 M, the specific iodine - 131 limit would be.18 pCi/ce; at zero power, with a steam generator water volume of 101 M, the specific iodine - 131 limit would be
.089 pCi/ce.
Amendment Nos. 77 & 78
TS 3.6-6 The limitations on secondary system specific activity ensure that the resul-cant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.
References FSAR Section 4 Reactor Coolant System FSAR Section 9.3 Residual Heat Removal System FSAR Section 10.3.1 Main Steam System FSAR Section 10.3.2 Auxiliary Stecm System FSAR Section 10.3.5 Auxiliary Feedwater Pumps FSAR Section 10.3.8 Vent and Drain Systems FSAR Section 14.3.2.5 Environmental Effects of a Steam Line Break.
Amendment Nos. 77 a.78 r
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TS 4.8-1 4.8 AUXILIARY FEEDWATER SYSTEM Applicability Applies to periodic testing requirements of the Auxiliary Feedwater System.
Objective To verify the operability of the auxiliary steam generator feedwater pumps and their ability to respond properly when required.
Snecification A.
Tests and Frequency 1.
Each motor driven auxiliary steam generator feedwater pump shall.
be flow tested for at least 15 minutes on a monthly basis to demonstrate its operability.
2.
The turbine driven auxiliary steam generator feedwater pump shall be flow tested for at least 15 minutes on a monthly basis to demonstrate its operability.
3.
The auxiliary steam generator'feedwater pump discharge valves shall be exercised on a monthly basis.
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Amendment Nos. 77 & 78 l
TS 4.8-2 4a.
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to temperature and pressure exceeding 350*F and 450 psig respectively, the motor driven auxiliary feedwater pumps shall be flow tested from the 110,000 gallon above ground condensate storage tank to the steam generators.
4b.
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> af ter achieving reactor criticality, the steam turbine driven auxiliary feedwater pump shall be flow tested from the 110,000 gallon above ground condensate storage tank to the steam generators.
5.
During periods of extended reactor shutdown, the testing requirements of Specification A. 1, 2, and 3 may be modified as follows:
Only one of the three auxiliary steam generator feedwater a.
pumps shall be flow tested for at least 15 minutes on a monthly basis to demonstrate its operability provided the required components are tested prior to startup.
b.
The auxiliary steam generator feedwater pump discharge valves of the pump tested in 5a shall be exercised on a monthly t
basis provided all the discharge valves are tested prior to startup.
B.
Acceptance Criteria These tests, except the system flow test, shall be considered satisfactory if j
control board indication and subsequent visual observation of the equipment demonstrate that all components have operated and sequenced properly.
j Amendment Nos. 77 & 78 f.
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TS 4.8-3 The system flow test shall be considered satisfactory if the control board indication demonstrates that flow paths exist to each steam generator.
Basis On a monthly basis the auxilia ry steam generator feedwater pumps will be tested to demonstrate their operability by recirculation to the 110,000 Gallon Condensate Storage Tank.
The capacity of any one of the three feedwater pumps in conjunction with the water inventory of the steam generators is capable of maintaining the plant in a safe condition and sufficient to cool the unit down.
Proper functioning of the steam turbine admission valve and the ability of the feedwater pumps to start will demonstrate the integrity of the system.
Verification of correct operation can be made both from instrumentation within the Main Control Room and direct visual observation of the pumps.
References FSAR Section 10.3.1 Main Steam System FSAR Section 10.3.2 Auxiliary Steam System l
Amendment Nos. 77 8 78 i
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