ML20107J246
| ML20107J246 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/12/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20107J247 | List: |
| References | |
| NUDOCS 8411090432 | |
| Download: ML20107J246 (11) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 5.'*.,I C
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WASHINGTON. D. C. 20555 s,
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.98 License No. DPR-32 r
1.
The Nuclear Regulatory Comission (the Comission) has found that:
f A.
The application for amendment by Virginia Electric and Power Company (the licens'ee) dated April 5,1984, 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; L
B.
The facility will operate in confonnity with the application, 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 q
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 I
have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spe".Fications 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:
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8411090432 841012 l
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(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 98, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Thislicenseamendmentiseffectiveasofthedateofits! issuance.
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F THENUCLEAR'R(GULATORYCOMMISSION r g abe,Chie OperatingReactorsBra(V e
nth #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 12,198k
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as esco UNITED STATES
,., f,i NUCLEAR REGULATORY, COMMISSION j
WASHINGTON, D. C. 20555 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. DPR-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated April 5,1984, 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 confamity 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 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
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. (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendnent No.97, 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 NUCLEAR REGULATORY COMMISSION II h
e a ga, if Operating Reactor anch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 12,198d i
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0.
98 FACILITY OPERATING LICENSE NO. DPR-32 i
AMENDMENT NO.
FACILITY OPERATING LICENSE N0. DPR-37 I
97 i
DOCKET NOS. 50-280 AND 50-281 i
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 3.6-6 e
TS 3.6-1 3.6 TURBIE CYCII 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 stea; generator and to assure the capa-bility to remove residual heat from the core during a loss of station power.
Specification A.
A unit's Reactor Coolant System temperature or pressure shall not l
exceed 350*F or 450 psig, respectively, or the reactor shall not be critical unless the five main steam line code safety valves asso-ciated with each steam generator in unisolated reactor coolant loops are operable.
B.
To assure residual heat removal capabilities, the following condi-tions shall be met prior to the cournencement 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.
1.
Two motor driven auxiliary feedwater pumps shall be operable, and one of three auxiliary feedwater pumps for the opposite unit shall be available*.
- Available means (1) operable except'for automatic initiation instrumentation, (2) offsite or emergency power source may be inoperable in cold shutdown, cad (3) it is capable of being used with the opening of the cross-connect.
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TS 3.6-2 2.
'A minimum of 96,000 gallons of water shall be available in the l
tornado missile protected condensate storage tank to supply emergency water to the auxiliary feedwater pump suctions.
A minimum of 60,000 gallons of water - shall be available in the l
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 oper-able.
C.
Prior to reactor power exceeding 10%, the steam driven auxiliary feedwater pump shall be operable.
D.
System piping, valves, and control board indication required for the f
operation of the components enumerated in Specifications 3.6.B.1, 3.6.B.2, 3.6.B.3 and 3.6.C shall be operable with the system piping, f
valves, and control board indication required for the operation of the opposite unit auxiliary feedwater pump available*.
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E.
The iodine - 131 activity in the secondary side of any steam gene-rator, in an unisolated reactor coolant loop, shall not exceed 9 curies.
Also, the specific activity of the secondary coolant system shall be 5 0.10 pCi/cc DOSE EQUIVAI.ENT I-131.
If the specific activity of the secondary coolant system exceeds 0.10 pCi/cc DOSE EQUIVAI.ENT 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 hcurs.
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- Available means (1) operable except for automatic initiation instrumentation,
(2) offsite or emergency power source may be inoperable in cold shutdown, and s
(3) it is capable of being used with the opening of the cross-connect.
Amendment No. 98 and 97 I
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TS 3.6-3 F.
With one auxiliary -feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two motor driven feedvater pumps and one-steam driven feedwater p"sp) to operable status ;ithin 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 Specifications 3.6.B.1 and 3.6.D above con-cerning the opposite unit's auxiliary feed water pumps and associated piping, valves, and control board indications may be modified - to allow the following components to be unavailable.
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1.
The opposite unit's auxiliary feed water pumps may be unavail-able for a period not to exceed 7 days provided immediate attention is directed to making repairs.
If not available within 7 days, be in at least hot shutdown 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 next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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The system piping, valves, and control board indication for operation of the opposite unit's auxiliary feed water pumps may be unavailable for a period not to exceed 7_ days provided immediate attention is directed toward making repairs.
If not available within 7 days, be in at least hot shutdown within j
l-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 next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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The requirements of Specification 3.6.B.2 above may be modified to i
allow utilization of protected condensate storage tank water with the auxiliary steam generator feed pumps provided the water level is l
maintained above 60,000 gallons, sufficient replenishment water is
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available in the 300,000 gallon condensate storage tank, and replen-ishment of the protected condensate storage tank is commenced within two hours after the cessation of protected condensate storage tank l
water consumption.
Basis A reactor which has been shutdown from power requires removal of core residual heat.
While reactor coolant temperature or pressure is > 350*F or 450 psig, respectively, residual heat removal requirements are normal-Amendment No. 98 and 97 s
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TS 3.6-4 The capability to supply feedwater t.o the generators is normally provided by the operation of the Condensate and Feedwater Systems.
In the event of complete loss at electrical power to the station, residual heat removal would continue to be assured by the availability of either the l
steam driven auxiliary feedwater pump or one of the motor driven auxil-i f ary feedwater pumps and the 110,000 gallon 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 from the opposite unit.
t A minimum of 92,000 gallons of water in the 110,000-gallon condensate taak i.t 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 offsite electrical power.
If the protected t
condensate storage tank level is reduced to 60,000 gallons, the immedi-ately available replenishment water in the 300,000-gallon condensate tank 3
can be gravity-fed 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 gene-rator 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 stea:n 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 tank, and the main steam line safety valves adequately assures that sufficient residual heat removal capability will be avail-able when required.
Amendment No. 98 and 97
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TS 3.6-5 I
The availability of the auxiliary feedwater pumps, the protected condensate storage tank, and the main steam line safety valves adequately assures that sufficient resHual heat removal capability will be avail-able when required.
The - limit on steam generator secondary side iodine - 131 activity is-based on limiting inhalation thyroid dose at the site boundary of 1.5 rem after a postulated accident that would result in the 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% of the resultant thyroid dose at the site boundary; the remaining 25% 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, ma' king allcwance for plate out i
t and retention in water droplets.
The inhalation thyroid dose at. the site boundary is given by:
Dose (rem) = (C) (X/Q) (D=/AT) (B.R.)
(.75)-(P.F.)
where: C = steam generator I-131 activity (cu, ries) l
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X/Q = 8.14 x 10 sec/m 8
i D=/At = 1.48 x 10 rem /Ci for I-131
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m /sec from TID 14844 j
B.R. = breathing rate, 3.47 x 10 P.F. = plating factor, 10 Assuming the postul.ited accident, the resultant thyroid dose is 1.5 rem.
The steam generator's specific iodine - 131 activity limit is calculated by dividing the total activity limit of 9 curies by the water volume of a steam generator.
At full power, with a steam generator water volume of 3
l 47.6 M, th'e specific iodine - 131 limit would be.18 pCi/ce; at zero 3
power, with a steam generator water volume of 101 M, the specific iodine - 131 limit would be.089 pCi/cc.
The limitation on secondary system specific activity ensures that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.
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l TS 3.6-6 REFERENCES FSAR Section 4, Reactor Coolant System FSAR Section 9.3, Residual Heat Removal System FSAR Section 10.3.1, Main Steam System-
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FSAR Section 10.3.2, Auxiliary Steam System FSAR Section 10.3.5, Auxiliary Feedwater System FSAR Section 10.3.8, Vent and Drain Systems FSAR Se ', ion 14.3.2.5, Environmental Effects of a Steam Line 3reak Amendment No. 98 and 97
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