ML20126D821
| ML20126D821 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/14/1992 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126D824 | List: |
| References | |
| NUDOCS 9212280176 | |
| Download: ML20126D821 (13) | |
Text
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UNITED STATES ni NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D C. 20006
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VIRGINIA ELECTRIC AND POWER COMPANY QQ[KET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.171 License No. DPR-32 1.
The Nuclear Regulatory Commission (the CommissP has found that:
A.
Tha application for amendment by Virginia Electric and Power Company (the licensee) dated July 28, 1992,. complies with the standards and requirements of the Atomic Energy' Act of 1954, as.
amended (the Act) and the Commission's rules and regulations set i
forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application,lthe provisions of-the Act, and the rules and regulations of the Comission; C.
There is reasonable ass'urance (i)'th'at 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.compiiance with the Commission'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-l 51 of the Commission's regulations and-all applicable requirements have been satisfied.
l 1
4 9212280176 921214 PDR ADOCK 05000200-P.
. 2.
Accordingly, the
- ense 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 Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 171, 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 its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGut.ATORY COMMISSION i rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 14, 1992
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i UNITED STATES n
I NUCLEAR REGULATORY COMMISSION
?o WASHINGTON, D.C. 20665 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 170 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 July 28, 1992, 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; 8.
The facility will operate in conformity with the_ application, the provisions of the Act, and the rules and regulations of the Comission; There is reasonable assurance (1)d without endangering the health C.
that the activities authorized by this amendment can be conducte 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.
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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. OPR-37 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 170, 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 its date of issuance and shall be implemented within 30 days.
FOR THE NVCLEAR REGULATORY COMMISSION H>rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 14, 1992
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AII&CHMENT TO LICENSE AMENDMENT AMENDMENT NO.171 TO FACillTY OPERATING LICENSE NO. DPR-32 AMENDMENT NO.170 TO FACILITY OPERATING LICENSE NO. OPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paaes TS 3.7-1 TS 3.7-1 TS 3.7-20a TS 3.7-20a TS 3.11-1 TS 3.11-1 TS 3.11-2 TS 3.11-2 TS 3.11-2a TS 4.1-1 TS 4.1-1 TS 4.1-9 TS 4.1-9 TS 4.9-1 TS 4.9-1
TS 3.71 3.7 INSTRUMENTATION SYSTEMS Ooerational Safety Instrumentation Anollemhllig Applies to reactor and safety features instrumentation systems.
Objectives To tovide for automatic initiation of the Engineered Safety Features in the event that principal process variable limits are exceeded, and to delineate the conditions of the plant instrumentation and safety circuits necessary to ensure reactor safety.
Soecification A.
For on line testing or in the eveht of a subsystem Instrumentation channel failure, plant operation at rated power shall be permitted to continue in accordance with TS Tables 3.7-1 through 3.7 3.
B.
The reactor trip system instrumentation channels and interlocks shall be operable as specified in TS Table 3.71.
C.
The Engineered Safeguards Actions and Isolation Function Instrumentation channels and interlocks shall be operable as specified in TS Tables 3.7 2 and 3.7-3 respectively.
D.
The Engineered Safety Features initiation instrumentation sotting limits shall be as stated in TS Table 3.7-4.
E.
The explosive gas monitoring instrumentation channel shown in Table 3.7 5(a) shall be OPERABLE with its alarm setpoint set to ensure that the limits of Specification 3.11.A.1 are not exceeded.
1.
With an explosive gas monitoring instrumentation channel alarm setpoint less conservative than required by the above l
specification, declare the channel inoperable and take the action shown in Table 3.7 5(a).
Amendment Nos. 171, 170
TABLE 3.7-5(2)
EXPLOSIVE GAS MONITORING INSTRUMENTATION 1
IArimum Total No.
OPERABLE Instnament of Channels Channe!s '
Action
- 1. Waste Gas Holdup System Explosue Gas Mondonng System Oxygen Monitor 1
1 1
Acton 1 - With the number of channels OPERABLE less than required by the minimum OPERABLE channels requeement, operaton of th:s waste gas holdup system may continue provided grab samples are collected (1) at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> dunng degassing operatons to the waste Das decay tank and (2) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operabons. Samples sha3 be analyzed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after co8ectiott E
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TS 3.11 1 3.11 RADIOACTIVE GAS STORAGE l
Aco!!cability Applies to the storage of radioactive gases.
Obiective To establish conditions by which gaseous waste containing radioactive materials may be stored.
Soecification A.
Erpfosive Gas Mixture 1.
The concentration of oxygen in the waste gas holdup system shall be limited to less inan or equal to 2% by volume whenever the hydrogen concentration could exceed 4% by volume.
a.
With the concentration of oxygn in the waste gas holdup system greater than 2% by voit out less than or equal to 4% by volume, reduce the c,, en concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
With the concentration of oxygen in the waste gas holdup system greater than 4% by volume, immediately suspend all additions of waste gases to the affected tank and reduce the concentration of oxygen to less than or equal to 4% by volume, then take the action in 1.a above.
c.
With the requirements of action 1.a above not satisfied, immediately suspend all additions of waste gases to the affected tank until the oxygen concentration is restored to less than or equal to 2% by volume, and submit a special report to the Commission within the next 30 days outlining the following:
(1)
The cause of the waste gas decay tank exceeding the 2% oxygen limit.
(2)
The reason why the oxygen concentration could not be returned to within limits.
1 Amendment Nos. 171, 170
I TS 3.112 (3)
The actions taken and the time required to return the oxygen concentration to within limits.
2.
The requirements of Specification 3.0.1 are not applicable.
B.
Gas Storace Tanks 1.
The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 24,600 curies of noble gases (considered as Xe 133).
2.
With the quantity of radioactive materialin any gas storage tank exceeding the above limit, immediately suspend all aadition of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limits.
3.
The requirements of Specification 3.0.1 are not applicable.
fla11S Explosive Gas Mixture Specification 3.11.A is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining oxygen below the concentration that will support combustion at any concentration of hydrogen provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR 50.
Gas Storage Tanks The tanks included in Specification 3.11.8 are those tanks for which the quantity l of radioactivity contained is not limited directly or Indirectly by another Technical i
Specification to a quantity that is less than the quantity which provides l
assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem in an event of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Amendment Nos. 171, 170
I TS 3.;12a l I
Re.stricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rern. This is consistent with Branch Technical Position ETSB 115 in NUREG 0800, July 1981.
s Amendment Nos. 171, 170 l
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TS 4.1-1 4.1 OPERATIONAL SAFETY REVIEW Acolicabiliiv Applies to items directly related to safety limits and limiting conditions for operation.
Objective To specify the minimum frequency and type of survell lance to be applied to unit equipment and conditions.
Soecification A.
Calibration, testing, and checking of instrumentation channels and interlocks shall be performed as detailed in Tables 4,1-1,4.1-1 A, and 4.1-2.
B.
Equipment tests shall be conducted as detailed below and in Table 4.1 -2 A.
1.
Each Pressurizer PORV shall be demonstrated OPERABLE:
a.
At least once per 31 days by performance of a channel functional test, excluding valve operation, and i
b.
At least once per 18 months by performance of a j
channel calibration.
l 2.
Each Pressurizer PORV block valve shall be demonstrated l
OPERABLE at least once per 92 days by operating the valve through one complets cycle of full travel.
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Amendment Nos. 171, 170
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TABLE 4.1-1 A EXPLOSIVE GAS MONITORING INSTRUMENTATION REQUIREMENTS CHANNEL CHANNEL CilANNEL l
CHANNEL DESCRIPTION CHECK _
CALIBRATION FUNCtONAL TESI 1.
Waste Gas Holdup System Explosive Gas Monitoring System D
O(1)
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Oxygen Monitor 1
(1)
The channel calbration shall include the use of standard gas samples containing a norninal:
1.
one volume percent oxygen, balance r& ogen, and 2.
four volurne percent oxygen, balance nitrogen D-Daay g
M-Monthly g
O-Quarterty 3,
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TS 4.91 4.9 RADIOACTIVE GAS STORAGE MONITORING SYSTEM Acolicability Applies to the periodic monitoring of radioactive gas storage.
Objective To ascertain that waste gas is stored in accordance with Specification 3.11.
Soecificatiort A.
The concentration of oxygen in the waste gas holdup system shall be determined to be within the limits of Specification 3.11.A by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitor required to be OPERABLE by Table 3.7 S(a) of Specification 3.7.E.
B.
The quantity of radioactive material contained in each gas storage tank shall be determined to be within the limits of Specification 3.11.8 at least once per month when the specific activity of the primary reactor coolant is s 2200 pCi/gm dose equivalent Xe 133. Under the conditions which result in a specific activity > 2200 pCl/gm dose equivalent Xe-133, the l
waste gas decay tanks shall be sampled once per day.
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Amendment Nos. 171, 170-
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