ML20248A004
| ML20248A004 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/30/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248A008 | List: |
| References | |
| NUDOCS 8906080042 | |
| Download: ML20248A004 (11) | |
Text
_
.Q>
- h UNITED STATES E
NUCLEAR REGULATORY COMMISSION I
o j
WASHINGTON, D, C. 20555
\\ *.../
VIRGINIA ELECTRIC AND POWER COMPANY l
DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1
-l AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 129
{
License 140. 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 20, 1989, 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 (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 i
defense and security or to the health and safety of the public; i
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-32 is hereby amended to read as follows:
I
+.a 8906080042 890530 ADOCK0500gO PDR P
. (B)' Technical Specifications The Technica1' Specifications contained in Appendix A, as revised through Amendment No.129, 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 A
H rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 30, 1989 l
6
<;j r
o,.
UNITED STATES
-E-NUCLEAR REGULATORY COMMISSION o'
.n e._
wAswsworow, o.c.rosos b
VIRGINIA ELECTRIC AND POWER COMPANY--
DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 129 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 March 20, 1989, 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 m
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 l
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:
I
~
c j
1 l.=
(B) Technical Specifications The Technical Specifications-contained in Appendix A,-
as revised through Amendment No.129, are hereby e
. 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 T
I H rbert N. Berkow, Director Project' Directorate 11-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 30, 1989
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
129 FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO.
129 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET N05. 50-280 AND 50-281 Revise Appendix A as follows:
Recove Pages Insert Pages TS 3.14-2 TS 3.14-2 TS 3.23-1 TS 3.23-1 TS 3.23-2 TS 3.23-2 TS 3.23-3 TS 3.23-4 TS 3.23-5
__._____m_
f.)
.TS 3.14-2 b.
Flow to and from the component cooling heat exchangers required by Specification 3.13.
e I
3.
At least two circulating water pumps are operating or are operible.
4.
At least two emergency service water pumps are operable; these two pumps will service both units simultaneously.
5.
Two service water flowpaths to the charging pump service water subsystem are operable.
6.
Two service water flowpaths to the recirculation spray subsystems are operable.
B.
There shall be an operating service water flow path to and from one operating main control and emergency switchgear rooms air conditioning 1.
condenser and at least one operable service water flow path to and from at least one operable main control and emergency switchgear rooms air I conditioning condtnser whenever fuel is loaded in reactor core.
Refer to {
Section3.23.Cforairconditioningsystemoperabilityrequirementsabove-[
cold shutdown.
C.
The requirements of Specifications A-5 and A-6 may be modified to allow unit operation with only one operable flow path to the charging pump service water subsystem and to the recirculation spray subsystems.
If the affected systems are not restored to the requirements of Specifi-cations A-5 and A-6 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in a hot shutdown condition.
If the requirements of Specifications A-5 and A-6 are not met within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be Amendment Nos. 129 and 125 1
(
.c 15 3.23 1 3.23 MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM VENTILATIO CONDITIONING SYSTEMS Anolicability Applies to the main control room (MCR) and emergency switchgear room (ESGR) and air conditioning system and emergency ventilation system.
Obiective To specify requirements to ensure the proper function of the main control and emergency switchgear room air conditioning system and emergency ventilation system.
Specification A.
Both trains of the main control and emergency switchgear rooms' emergency ventilation system shall be operable whenever either unit is above cold shutdown.
B.
With one train of the main control and emergency switchgear room emergency ventilation system inoperable for any reason, return the inoperable train to a 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 and emergency switchgear room air conditioning system shall be operable as delineated in the following:
l 1.
Chiller Refrigeration Units j
a.
Chillers 1-VS-E-4A, 48, and 40 must be operable whenever either unit is above Cold Shutdown.
This interim specification is necessary until the air conditioning system modifications scheduled for the End of cycle 10 on Unit I and cycle 10 on Unit 2
are completed.
Following completion of the permanent modifications, a revised air conditioning system specification will be submitted.
Amendment Nos. 129 and 129
TS 3.23-2 b.
If fLn.g chiller becomes inoperable, return-the 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 />.
2.
Air Handlina Units (AHU) a.
Unit I 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 MCR AHU becomes inoperable, return the inoperable AHU to operable status within seven (7) days or bring Unit I 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 />.
2.
If one Unit 1 ESGR AHU becomes inoperable, bring Unit I 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 MCR AHU becomes inoperable, return the inoperable AHU to operable status within seven (7) days or bring Unit 2 to Hot Shutdon 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 />.
2.
If one Unit 2 ESGR AHU becomes inoperable, 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.129 and 129
TS 3.23-3 c.
Unit 1
ESGR AHU drive. motors, 1-VS-FM0-6A, 1-VS-FMO-6B, 1-VS-FM0-7A, and 1-VS-FM0-78 must be operable whenever Unit 1 is above Cold Shutdown.
1.
If a Unit 1 ESGR AHU drive motor becomes inoperable, return the inoperable drive motor to operable status within seven (7) days or bring Unit I to Hot Shutdown within 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.
Unit 2
- motors, 2-VS-FM0-6A, 2-VS-FM0-68, 2-VS-FM0-7A, and 2-VS-FM0-7B must be operable whenever Unit 2 is above Cold Shutdown.
1.
If a Unit 2 ESGR AHU drive motor becomes inoperable, return the inoperable drive motor to operable status within seven (7) days or bring Unit 2 to Hot Shutdown within 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 />.
Basis 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 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 main control 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 LOCA.
Amendment Nos.129 and 129
TS 3.23-4 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 particulate.
The laboratory carbon sample test. results should indicate a radioactive methyl iodide 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 filters. 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.
System operating restrictions will be imposed on the modified MCR and ESGR air conditioning system until the permanent upgrade is implemented.
The restrictions will supplement the current Technical Specification limiting conditions for operation. The basis for the operating restrictions is as follows:
The modified system will require the operation of two chillers, two of the four MCR air handling units, and four ESGR air handling units to maintain design temperatures under maximum heat load conditions.
Taking credible single failures into consideration requires that redundant equipment be available during operation.
As such, the interim limiting conditions for operation will require that three chillers and eight air handling units be operable when at power Amendment Nos.129 and 129
-n.
~
TS 3.23-5 l
operation.
Further, the interim limiting conditions for operation will require that both drive motors on each ESGR air handling unit be operable.
In addition to the equipment restrictions above, a fire watch will be required during this interim period in both unit's ESGR and MER #3 to address Appendix R considerations.
I a
1 l
l l
l 1
i i
l I
I l
l
)
1 4
Amendment Nos.129 and 129
. - - - _ _ _ _ _ _ _ _ _ _ _ _ _._ - - _ _ - - -