ML20057A336
| ML20057A336 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/01/1993 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057A337 | List: |
| References | |
| NUDOCS 9309140033 | |
| Download: ML20057A336 (10) | |
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I VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 182 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 March 15, 1993, as supplemented April 21, 1993, 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 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 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
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of the Comission's regulations and all applicable requirements have been satisfied.
9309140033 930901 PDR ADDCK 05000280 P
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachmen, 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 through Amendment No. 182, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION l
e bert N. Berkow, Director l
Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: september 1, 1993
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 182 i
License No. DPR-37 I
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company i
(the licensee) dated March 15, 1993, as supplemented Api P 21, 1993, complies with the standards and requirements of the Atomic Energy l
Act of 1954, as amended (the Act) and the Comission's rules and l
regulations set forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the Comission; I
C.
There is reasonable assurance (1) that the activities authorized by j
l this amendment can be conducted without endangering the health and i
l 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 I
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, i
and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 182, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the i
Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION A
Hdrbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
Attachment:
l Changes to the Technical Specifications Date of Issuance: September 1, 1993 l
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l ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
182 TO FACILITY OPERATING LICENSE NO. OPR-32 AMENDMENT NO.
182 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
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Remove Paaes Insert Paaes TS 3.16-5 TS 3.16-5 TS 3.23-1 TS 3.23-1 TS 3.23-2 TS 3.23-2 l
TS 3.23-3 TS 3.23-3 TS 3.23-4 TS 3.23-4 j
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TS 3.16-5 The diesel generators function as an on-site back-up system to supply the emergency buses. Each emergency bus provides power to the following operating Engineered Safeguards equipment:
A.
One containment spray pump i
B.
One charging pump C.
One low head safety injection pump i
D.
One recirculation spray pump inside containment 1
E.
One recirculation spray pump outside containment l
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One containment vacuum pump i
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One motor-dnven auxiliary steam generator feedwater pump i
H.
One motor control center for valves, instruments, control air compressor, fuel oil pumps, etc.
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Control area air conditioning equipment - four air recirculating units, two water chilling units, one service water pump and two chilled water circulating pumps J.
One charging pump service water pump for charging pump intermediate seal coolers and lube oil coolers K.
One charging pump cooling water pump for charging pump seal coolers.
i Amendment Nos.182 and 182 l
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TS 3.23-1 l
3.23 MAIN CONTROL ROOM AND EMERGENCY SWITCliGEAR ROOM l
VENTILATION AND AIR CONDITIONING SYSTEMS Anoticability Applies to the Main Control Room (MCR) and Emergency Switchgear Room (ESGR) Air Conditioning System and Emergency Ventilation System.
Objective To specify requirements to ensure the proper function of the Main Control Room and Emergency Switchgear Room Air Conditioning System and Emergency Ventilation System.
Soecification A.
Both trains of the Main Control Room and Emergency Switchgear Room Emergency Ventilation System shall be OPERABLE whenever either unit is above COLD SHUTDOWN.
B.
With one train of the Main Control Room and Emergency Switchgear Room Emergency Ventilation System inoperable for any reason, return the inoperable train to an OPERABLE status within 7 days or 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 following 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
C.
The Main Control Room and Emergency Switchgear Room Air Conditioning System shall be OPERABLE as delineated in the following:
- 1.
Chiller Refrigeration Units a.
Three main control room and emergency switchgear room chillers must be OPERABLE whenever either unit is above COLD SHUTDOWN.
This interim specification is necessary until the air conditioning system modifications are completed. Following completion of the permanent modifications, a revised air conditioning system specification will be submitted.
Amendment Nos.182 and 182 4
TS 3.23-2 b.
The three OPERABLE chillers are required to be powered from three of the four emergency buses with one of those chillers capable of bemg powered from the fourth emergency bus.
c.
If one of the OPERABLE chillers becomes inoperable or is
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not powered as required by Specification 3.23.C.1.b, return an inoperable chiller to OPERABLE status within seven (7) days or bring both units to HOT SHUTDOWN within the next six (6) hours and be 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 />.
d.
If two of the OPERABLE chillers become inoperable or are not powered as required by Specification 3.23.C.1.b, retum an inoperable chiller to OPERABLE status within one (1) hour or bring both units to HOT SHUTDOWN within the next six (6) hours and be in COLD SHUTDOWN within the fo!!owing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
2.
Air Handling Units (AHU) a.
Unit 1 air handling units,1-VS-AC-1,1-VS-AC-2,1-VS-AC-6, and 1-VS AC-7, must be OPERABLE whenever Unit 1 is above COLD SHUTDOWN.
1.
If one Unit 1 AHU becomes inoperable, return the in-operable AHU to OPERABLE status within seven (7) days or bring Unit 1 to HOT SHUTDOWN within the next six (6) hours and be 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 />.
b.
Unit 2 air handling units,2-VS-AC-8,2-VS-AC-9,2-VS-AC-6, and 2-VS-AC-7 must be OPERABLE whenever Unit 2 is above COLD SHUTDOWN.
1.
If one Unit 2 AHU becomes inoperable, return the in-operable AHU to OPERABLE status within seven (7) days or bring Unit 2 to HOT SHUTDOWN within the next six (6) hours and be 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 />.
Amendment Nos.182 and 182
TS 3.23-3 Basis i
When the supply of compressed bottled air is depleted, the Main Control Room and Emergency Switchgear Room Emergency Ventilation System is manually started to continue to maintain the control room pressure at the design positive r
pressure so that leakage is outleakage. One train of the main control room emergency ventilation consists of one fan powered from an independent emergency power source.
The Mair, Control Room and Emergency Switchgear Room Emergency' Ventilation System is designed to filter the intake air to the control room pressure envelope, which consists of the control room, relay rooms, and emergency switchgear rooms during a Icss of coolant accident.
l High efficiency particulate air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of radio-iodine to the control room.
The in-place test results should indicate a system leaktightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99.5 percent removal of DOP particulates. The laboratory carbon sample test results should indicate a radioactive methyliodide removal efficiency of at least 95 percent for expected accident conditions. The control room dose calculations assume only 90 percent iodine removal efficiency for the air passing through the charcoal fitters. Therefore,if the efficiencies of the HEPA filters and charcoal adsorbers are as specified, at the temperatures, flow rates and velocities within the design values of the system, the resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR Part 50.
If the system is found to be inoperable, there is no immediate threat to the control room, and reactor operation may continue for a limited period of time while repairs are being made. If the system cannot be repaired within the specified time, procedures are initiated to establish conditions for which the filter system is not required.
Amendment Nos.182 and 182
TS 3.23-4 1
The Main Control Room and Emergency Switchgear Room Air Conditioning System cools the main control room, the control room annex and the Units 1 and 2 emergency switchgear rooms. The existing air conditioning system includes three chillers (1-VS-E-4A,48, and 4C) and eight air handling units (1-VS-AC-1,2, 6,7 and 2-VS-AC-6,7,8, and 9).
Interim modifications were completed on the Main Control Room and Emergency Switchgear Room Air Conditioning System to address interim failure and increased cooling requirements for the emergency switchgear rooms. Permanent modifications will include replacement of the main control room and emergency switchgear room air handling units (AHU) and installation of additional chiller capacity to restore original design flexibility.
Units 1 and 2 main control room and emergency switchgear room AHUs havel been replaced in the initial phases of the permanent modification, restoring redundancy to the AHU portion of the original system design. As a result, the following main control room and emergency switchgear room equipment is!
required to operate to maintain design temperature under maximum heat load conditions:
Two chillers One Unit 1 MCR AHU and one Unit 1 ESGR AHU One Unit 2 MCR AHU and one Unit 2 ESGR AHU The existing chiller configuration requires that the three chillers in MER-3 (1-VS-E-4A,4B, and 4C) be OPERABLE so that in the event of a total Loss of Offsite Power to the station and the single failure of an emergency bus or a chiller, two chillers remain available. Installation of the two additional chillers in MER-5 (1-VS-E-4D and 4E) will provide operational flexibility. Any three of the five installed chillers, powered from separate emergency buses with one of those capable of being powered from the fourth emergency bus, will ensure two chillers are available to maintain design temperature under maximum heat load conditions.
This operational flexibility is necessary to complete the permanent modification of the existing chillers.
In addition to the equipment restrictions above, a fire watch will be required during this interim period in MER-3 to address Appendix R considerations.
Amendment Nos.182 and 182
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