ML20052B017
| ML20052B017 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/25/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052B018 | List: |
| References | |
| NUDOCS 8204290575 | |
| Download: ML20052B017 (7) | |
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UNITED STATES y
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WASHINGTON. D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UN11 NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. DPR-32 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (.the licensee) dated February 19, 1982, 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 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 comon l
defense and security or to the health and safety of the public; and l
l 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 820429 05 75
l i 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 unended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 76, 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 GULATORY COMMISSION
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ev arga, C Operating Reactors nch #1 Division of Licensi
Attachment:
Changes to the Technical l
Specifications Date of Issuance:
" arch 25,1982
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gf UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. DPR-37 l
l 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated February 19, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, l
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 (.1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (til 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 1
1 l
2.
Accordingly, the license is amended hy changes to the Technical Specifications as indicated in the attachment to this license mnendment, and paragraph 3.8 of Facility Operating License No. DPR-37.is herehy amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 77.,.are herehy 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 e
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fMev 2n Operating Reactors nch #1 Division of Licensi
Attachment:
Changes to the Technical Specifications Date of Issuance: " arch 25,1982
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 76 TO FACILITY OPERATING LICENSE NO. OPR '
AMENDMENT NO. 77 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revt.se Appendix A as follows:
Remove Pages Insert Pages 3.1 -15a 3.1 -15a 3.1-17 3.1-17 e
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TS 3.1-15n 2.
Th1 cpici;fic cetivity-of the. rehetor coolant chall he limitad to < 1.0 pCi/cc DOSE EQUIVALENT-131 whenever the reactor is critical or the average temperature is greater than 500*F.
3.
The requirements of D-2 above may be modified to allow the specific activity of the reactor coolant >1.0 pCi/cc DOSE EQUIVALENT I-131 but less than 10.0 pCi/cc DOSE EQUIVALENT I-131.
Following shutdown, the unit may be restarted and/or operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that operation under these circumstances shall not exceed 10 percent of the unit's total yearly operating time. With the specific activity of the reactor coolant >1.0 pCi/cc DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding 10.0 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. With the total cumulative operating time at a primary coolant specific activity >1.0 pCi/cc DOSE EQUIVALENT I-131 exceeding 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />.in any consecutive 4
6 inonth period, prepara and submit a Special Report to the NRC, Regional Administrator, Region II within 30 days Indicating the number of hours above this limit.
4.
If the specific activity of the reactor coolant exceeds 1.0 tici/cc DOSE EQUIVALENT I-131 or 100/E p/C1/ce, a report shall be prepared and submitted to the Commission pursuant to Specification 6.6.2.b(2). This 1
report shall contain the results of the specific activity analysis
, together with the following information:
a.
Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which.the limit was exceeded, b.
Fuel burnup by core region, c.
Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which.the limit was exceeded, d.
History of degassing operations, if any, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded, and e.
The time duration when the specific activity of the primary coolant exceeded 1.0 pC1/cc DOSE EQUIVALENT I-131.
Amendment Nos. 76 & 77
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TS 3.1-12 boundary would be 0.30 Rem whole body and 0.28 Rem thyroid. Thus, these doses are well below the' guidelines suggested in.10CFR100.
Permitting startup and/or~ reactor operation to continue for limited time
- periods with the reactor coolant's specific activity > 1.0 pCi/cc but 410.0 pCi/cc DOSE EQUIVALENT I-131 accomodates possible iodine spiking phenomenon which may occur following changes iii thermal power. Operation within these
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limits must be restricted to no more than 10 percent of the unit's yearly operating time'since the activity levels allowed may slightly increate the 2 f
hour thyroid dose at the site boundary.following a postua ted steam generator A
tube rupture. The basis for tiie 500*F temperature contained in the Specification is that the saturation pressure corresponding to 500*F,'680.8 psia, is well below the~ pressure at which the atmospheric. relief valves on the secondary side could be actuated. Measurement of E will be performed at least twice annually. Calculations required to determine E will consist of the following: 1.
E shall be the average (weighed in pr6 portion to the concentration of each radionuclide in the react 6'r coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of' the total non-f odine activity in the coolant.-
2.
A determination of the beta and gamma decay energy per disintegration of each nuclide determined in (1) above by applying known decay energies and schemes.
3.
A calculation of E by appropriate weighing of each nuclide's bara and gam =a energy with its concentration as detemined in (1) above.
, Amendment flos. 76 & 77