ML20217N367
| ML20217N367 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/09/1997 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217N373 | List: |
| References | |
| NUDOCS 9708260139 | |
| Download: ML20217N367 (27) | |
Text
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@ *Uo 3
t UNITED STATES j
,j NUCLEAR REEULATURY CCMMISSION t
WASHINGTON D.C. 20046-0001 e
I, WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.174 License No. DPR-24 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 30, 1996, as supplemented on November 26 and December 12, 1996, and February 13. March 5.
April 2. April 16. May 9, June 3. June 13 (two), and June 25, Encr9y Act of 1954, as amended (the Act)quirements of the Atomic 1997, complies with the standards and re
, 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 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, nnnh 9708260139 970709 DR ADOCK 050002 6 1
2 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-24 is hereby amended to read as follows:
B,
' Technical Soecifications The Technical Specifications contained in A)pendices A and B as revised through Amendment No.174, are here)y incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
In addition, the license is amended to add paragraph 3.K to Facility Operating License No. DPR-24 as follows:
K.
Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.174, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions.
3.
This license amendment is effective immediately upon issuance.
The Technical 5)ecifications are to be implemented prior to any recuired restart of Jnit I and in no case longer than 45 days from the cate of issuance.
Implementation includes incorporating changes to Technical Specification requirements for the service water system, component cooling water systems, and control room ventilating system as detailed in an application dated September 30, 1996, as supplemented on November 26 and Decembcr 12, 1996 February 13, March 5. April 2. April 16 May 9.
June 3. June 13 (two), and June 25, 1997, and evaluated in the staff's safety evaluation attached to this amendment. This amendment is authorized contingent on compliance with commitments provided by the licensee to meet the dose limits associated with Title 10. Code of Federal Regulations, Part 50, Appendix A, General Design Criterion (GDC) 19 by: (1) submitting a license amendment application including supporting analyses and evaluations by February 27, 1998, that contains the proposed methods for compliance with GDC 19 dose limits under accident conditions based on system design and without reliance on the use of potassium iodide and/or supplied air breathing apparatus, and (2) implementing the proposed changes within 2 years of the date that NRC approval for the proposed license amendment is granted.
Additionally, this amendment is authorized contingent on comaliance with commitments provided by the licensee to operate Point Beach iuclear Plant in accordance with its service water system analyses and approved procedures. S)ecifically, each unit will utilize only one component cooling water leat exchanger until such time as analyses are completed and the service water system reconfigured as necessary to allow operation of one or both units with two heat exchangers in service.
If two component cooling water heat exchangers are required in one or both units for maintaining acceptable component cooling water temperature prior to completion of necessary analyses to allow operation in the required configuration, the service water system will be considered ~1n an unanalyzed condition. declared inoperable. 'and action taken as specified by Technical Specification 15.3.0.B except-for short periods of time as necessary to effect procedurally controlled changes i
in system-lineups and unit operating conditions.
FOR THE NUCLEAR REGULATORY COMMISSION f
&4umA-i Linda L, Gundrum, Project Manage'r Project Directorate-111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Attachments:
1.
Pages 4a and 5 of the License
- l 2.
A3pendix C - Additional Conditions i
3.
C1anges to the Technical Specifications Date of issuance:
July 9, 1997 l
i 1
- Pages 4a and 5 and Appendix C of the license are attached, for convenience.
for the composite license to reflect this change.
1 d.
_ _.-~. _ _ _.
t.
Wisconsin Electric Power Company 4a-i i
H.
Wisconsin Electric shall implement and r. n tain in effect i
all provisions of the approved fire protn 61on program as described in the Final Safety Analysis Report for the facility and as approved in the SER' dated August 2. 1979 (and Supplements dated October 21, 1980, January 22, 1981, and July 27. 1988) and the safety evaluation issued January 8, 1997, for technical Specification Amendment No. 170, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior a) proval of the Commission only if those clanges would not adversely affect the j
ability to achieve and maintain safe shutdown in the event of a fire.
j I.
Secondary Water Chemistry Monitorina Proaram The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
1.
Identification of a sampling schedule for the critical parameters and control points for these parameters; 2.
Identification of the procedures used to quantify parameters that are critical to control points:
3.
Identification of procest sampling points 4.
Procedure for the recording and management of data:
5.
Procedures defining corrective actions for off control point chemistry condition; and 6,
A procedure for identifying the authority i
responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.
.J.
The licensee is authorized to repair Unit 1 steam generators by replacement of major components. Repairs shall be co!. ducted in-
-accordance with the licensee's comitments identified in the Commission approved Point Beach Nuclear Plant Unit No.1 Steam Generator Repair Report dated August 9. 1982-and revised March 1.
1983 and additional-commitments identified in the staff's related Safety Evaluation.
K.
Additional Conditions I
-The Additional Conditions contained in Appendix C.' as revised through Amendment No. 174,- are hereby incorporated into this license. The l
11censee shall operate the facility in accordance with the Additional Conditions.
4 4
3 Point' Beach Unit 1 Amendment No. 174
Wisconsin Electric Power Company 5-4.
The issuance of this amended license is without prejudice to subsequent licensing action which may be taken by the Cormiission with regard to the on-going rulemaking hearing on the Interim Acceptance Criteria for Emergency Core Cooling Systems (Docket No. RM 50 1)..
5, This amended license is effective as of the date of issuance, and shall expire at midnight on October 5, 2010.
FOR THE ATOMIC ENERGY COMMISSION Original Signed By A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing 4
Attachments:
1, Appendix A - Technical Specifications 2.
Appendix B - Environmental Technical Specifications 3.
Appendix C - Additional Conditions l
Date of Issuance: October 5, 1970 Point Beach Unit 1 Amendment No. 174
y rt.wu u ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-24 Wisconsin Electric Power Company shall comply with the following conditions and the schedules noted below:
Amendment Implementation Number 6dditional Conditions Date 174 This amendment authorizes changes to Technical (1) February 27.
Specification requirements for the service water 1998.
system, component cooling water systems, and control room ventilating system as detailed in (2) Two years from an application dated September 30. 1996, as date amendment is supplemented on November 26 and December 12.
approved.
1996. February 13. March 5. April 2. April 16.
May 9. June 3. June 13 (two), and June 25. 1997, and evaluated in the staff's safety evaluation attached to this amendment.
This amendment is authorized contingent on compliance with comitments provided by the licensee to meet the i
dose limits associated with Title 10. Code of Federal Regulations. Part 50. Appendix A.
General Design Criterion (GDC) 19 by:
(1) submitting a license amendment application including supporting analyses and evaluations by February 27. 1998, that contains the proposed methods for compliance with GDC 19 dose limits under accident conditions based on system design and without reliance on the use of potassium iodide and/or supplied air breathing apparatus, and (2) implementing the 3roposed changes within 2 years of the date that 1RC approval for the proposed license amendment is granted.
174 This amendment is authorized contingent on immediately compliance with commitments provided by the licensee to operate Point Beach Nuclear Plant in accordance with its service water system analyses and approved procedures. Specificall each unit will utilize only one component cooling water heat exchanger until such time as analyses are completed and the service water system reconfigured as necessary to allow operation of one or both units with two heat exchangers in service.
If two component cooling water heat exchangers are required in one or both units for maintaining acceptable component cooling water temperature prior to completion of necessary analyses to allow operation in the required configuration, the service water system will be considered in an unanalyzed condition, declared inoperable, and action taken as specified by TS 15.3.0.B except for short periods of time as necessary to effect procadurally controlled changes in system lineups and unit operating conditions.
Point Beach Unit 1 C-1 Amendment No. 174
t>* "884g k
UNITED STATES g
}
NUCLEAR RECULATERY COMMISSION s*
WASHINGTON, D.C. aset64eH
%..,g WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50 301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENTTOFACILITYOPERATINGLICEkSE Amendment No. 178 l
License No. DPR 27 l
l 1.
The Nuclear Regulatcry Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated September 30, 1996, as supplemented on November 26 and December 12, 1996. February 13, March 5. A25, 1997,pril 2.
April 16. Hay 9. June 3. June 13 (two), and June complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comis31on's rules and regulations set forth in 10 CFR Chapter 1:
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 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.
J
2-2.
Accordii11y, the license is amended by cha'iges to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of facility Operating License No. DPR 27 is hereby amended to read as follows:
B.
Technic'al Soecifications The Technical Specifications contained in A)pendices A and B, as revised through Amendment No.178, are here3y incorporated in the license. The licensee shall operate the facility in accordance l
with the Technical Specifications.
l l
1 i
in addition, the license is amended to add paragraph 3.J to facility Operating License No. DPR 27 as follows:
J.
Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 178, are hereby incorporated into this license.
The-licensee shall operate the-facility in accordance with the Additional Conditions.
3.
This license amendment is effective imediately upon issuance.
The Technical Specifications are to be implemented prior to restart of Unit 2 following refueling outage R22.
g Implementation includes incorporating changes to Technical Specification requirements for the service water system, component cooling water systems, and control rein ventilating system as detailed in an application dated September 30, 1996, as supplemented on November 26 and December 12, 1996. February 13, March 5. A25, 1997. pril 2 April 16, May 9.
June 3, June 13 (two), and June and evaluated in the staff's safety evaluation attached to this amendment.
This amendment is authorized contingent on compliance with commitments provided by the licensee, to meet the dose limits associated with Title 10, Code of federal Regulatfons, Part 50, Appendix A, General Design Criterion (GDC) 19 by:
(1) submitting a license amendment application including supporting analyses and evaluations by February 27, 1998, that contains the proposed methods for compliance with GDC 19 dose limits under accident conditions based on system design and without reliance on the use of potassium iodide and/or supplied air breathing apparatus, and (2) implementing the proposed changes within 2 years of the date that NRC approval for the proposed license amendment is granted.
Additionally, this amendment is authorized contingent on com)11ance with commitments provided by the licensee to operate Point Beach iuclear Plant in accordance with its service water system analyses and approved procedures.
S>ecifically, each unit will utilize only one component cooling water leat exchanger until such time as analyses are completed and the service water system reconfigured as necessary to allow operation of one or both units with two heat-exchangers in service.
3 If two component cooling water heat exchangers are required in one or both units for maintaining acceptable component cooling water temperature prior to completion of necessary analyses to allow operation in the recuired configuration, the service water system will be l
considerec in an unanalyzed condition, declared ino>erable and actioh taken as specified by Technical Specification 15.3.0 B except for short periods of time as necessary to effect procedurally contrnlled changes in system lineups and unit operating conditions.
FOR THE NUCLEAR REGULATORY COMMISSION
'S Linda L. Gundrum, Project Manager Project Directorate 111 1 Division of Reactor Projects
!!!/IV Office of Nuclear Reactor Regulation-Attachments:
1.
A)ges 4 and 5 of the License
- Pa pendix C Additional Conditions 2
3.
C1anges to the Technical Specifications Date of Issuance: July 9, 1997
- Pages-4 and 5 and Appendix C of the license are attached, for convenience, for the composite license to reflect this change.
)
Wisconsin Electric Power Company 4-G.
$afety iniection Loaic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's ap)lication for amendment dated April 27, 1979, as l-supplemented 14ay 7.1979. In the interim period until the power supply modification has been completed. Should any DC powered safety injection actuation channel be in a failed condition for greater than one hour, the unit shall thereafter be shut down using normal procedures and placed in a block permissive condition for safety injection actuation.
H.
Wisconsin Electric shall implement and maintain in effect all
>rovisions of the approved fire protection program as described in the rinal Safety Analvs SERdatedAugust1.isReportforthefacilityandasapprovedinthe 1979 (and Supplements dated October 21,1980.
January 22, 1981, and July 27 1988) and the safety evaluation issued January 8.--1997, for Technical Specification Amendment No.174, subject to the following provision:
The licensee may make changes to the approved fire protection pr ram without prior approval of-the Commission on if those changes would not adversely affect the abi ity to achieve and maintain safe shutdown in the event of a fire.
I.
Secondary Water Chemistry Monitorina Procram The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
1.
Identification of a sampling schedule for the critical parameters and control points for these parameters:
2.
Identification of the procedures used to quantify parameters that tre critical to control points:
3.
Identification of process sampling points 4
Procedure for the recording and management of data:-
5.
Procedures defining corrective actions for off control point chemistry condition: and 6.
A procedure for identifying the authority responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.
J.
Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No.178, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional--
Conditions.
l-Point Beach Unit 2 Amendment No. 178 e
Wisconsin Electric Power Company 5-4.
The issuance of this amended license is without prejudice to subsequent licensing action which may be taken by the Comission with regard to the on-going rulemaking(hearing on the Interim Acceptance Criteria for Emergency Core vooling Systems Docket No. RM 50 1).
i 4
e 5.
This amended license is effective as of the date of issuance, and shall expire at midntght on March 8, 2013.
FOR THE ATOMIC ENERGY COMMISSION Original Signed By A. Giantusso. Deputy Director for Reactor Projects Directorate of Licensing Attachments:
1.
Appendix A Technical Specifications 2.
Appendix B Environmental Technical Specifications 3.
Appendix C Additional Conditions l
l Date of Issuance: March 8. 1973 Point Beach Unit 2 Ameri.hent No.178
hF F Lillf l b b ADDITIONAL CONDITIONS OPERATING LICENSE ND. DPR 27 Wisconsin Electric Power Company shall comply with the following conditions on the schedules noted below:
Amendment implementation
. Number Additional Conditions Date 178 This amendment authorizes changes to Technical (1) February 27.
Specification requirements for the service water
- 1998, system, component cooling water systems, and control room ventilating system as detailed in (2) Two years from an application dated September 30,1996, as date amendment is supplemented on November 26 and December 12.
approved.
1996. Februare n March 5. April 2. April 16.
May 9. June A M,t 13 (two), and June 25, 1997, and evaluate 1 Y th) staff's safety evaluation attached to this w :1dment. This amendment is authorized contingent on compliance with
-commitments provided L.y the licensee to meet the dose limits associated with Title 10 Code of Federa? Regulatfons. Part 50, A General Design Criterion (GDC) ppendix A.
19 by:
(1) submitting a license amendment application including supporting analyses and evaluations by February 27, 1998, that contains the proposed methods for compliance with GDC 19 dose limits under accident conditions based on system design and without reliance on the use of potassium iodide and/or supplied air breathing apparatus, and (2) implementing the proposed changes within 2 years of the date that NRC approval for the proposed license amendment is granted, 178 This amendment is authorized contingent on Immediately compliance with commitments provided by the licensee to operate Point Beach Nuclear Plant in accordance with its service water system analyses and approved procedures, Specifically, each unit'will utilize only one component cooling water heat exchanger until such time as analyses are completed and the service water system reconfigured as necessary to allow operation of one or both units with two heat exchangers in service, If two component cooling water heat exchangers are required in one or both units for maintaining acceptable component cooling water temperature prior to completion of necessary analyses to allow operation in the required configuration, the service water system will be considered in an unanalyzed condition, declared inoperable and action taken as specified by TS 15.3.0.B except for short periods of time as necessary to effect procedurally controlled changes in system lineups and unit operating conditions.
Point Beach Unit 2 C1 Amendment No. 178
)
ATTACHMENT TO LICENSE AMENDMENT NOS. 174 AND 178 TO FAClllTY OPERATING LICENSE NOS. DPR 24 AND DPR-27 DOCKET NOS. 50 266 AND 50 301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified b amendment number and contain vertical lines indicating the area of change. y REMOVE INSERT l
15.3.3 3 15.3.3 3 15.3.3 4 15.3.3 4 15.3.3 5 15.3.3 5 15.3.3 6 15.3.3 6 15.3.3 9 15.3.3 9 15.3.3 5 15.3.3 10 15.3.3.11 15.3.7 15.3.7 1 15.3.7 t 15.3.7 2 15.3.7 J 15.3.7 3 15.3.12-1 15.3.12 1 15.4.11-2 15.4.11 2 15.5.2 1 15.5.2 1*
15.5.2 2 15.5.2 2
- 0verleaf page provided to maintain document completeness.
No changes on this page.
B.
Containment Coolina and lodine Removal Systems 1.
A reactor shall not be made critical, except for low temperature physics tests, unless the following conditions associated with that reactor are met:
a.
'Thesprayadditivetankcontainsnotlesstilan2675 gal,of i
solution with a sodium hydroxide concentration of not less than 30% by weight.
b.
Two containment spray pumps are operable, c.
Four accident fan. cooler units are operable.
d.
All valves and piping, associated with the above components and required to function during accident conditions, are operable.
2.
During power operation, the' requirements of 15.3.3.B 1 may be modified to allow any ONE of the-following limitations (a.
b., or c.) to be in effect at any one time.
If the system is not restored to meet the requirements of 15.3.3.B 1 within the time period specified. the reactor shall be placed in the hot shutdown condition within six hours and in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
a.
One or two accident fan coolers may be out of service provided the fan coolers are restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The remaining accident fan coolers shall be operable.-
b.
One containment spray pump may be out of service provided the pump is restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The remaining containment spray pump shall be operable, c.
Any valve required for the functioning of the system during accident conditions may be inoperable provided repairs are completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Prior to initiating repairs, all valves in the system that provide the cuplicate function-
=shall be operable.
(Exception:
If.a spray pump is removed from service per b. above, valves associated with that train-may be removed from service for the period specified_ for the pump.)
Unit 1 - Amendment No. % 9. 174 Unit 2 - Amendment No. M3.178 15.3.3 3
C.
Comnonent Coolino System 1.
A reactor shall not be made critical unless the following conditions are met:
a.
The two component cooling pumps assigned to that unit are operabl,e.
b.
Either the com>onent cooling heat exchanger associated with I
the unit togetler with one of the shared spare heat exchangers are operable or the two shared spare heat i
exchangers are operable for single unit operation.
Three i
component cooling heat exchangers are operable for two unit I
operation.
c.
All valves interlocks and piping associated with the above components, and required for the functioning of the system during accident conditions, are operable.
2.
During power operation, the requirements of 15.3.3.C-1 may be modified to allow one of each of the following conditions at any one time.
If the system is not restored to meet the conditions of 15.3.3.C 1 within the time period specified, the reactor shall be placed in the hot shutdown condition.
If the requirements of 15.3.3.C 1 are not satisfied 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 placed in the cold shutdown condition, a.
One of the assigned component cooling pumps may be out of service provided a pump is restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
l b.
One of the required heat exchangers may be out of service provided repairs can be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Unit 1 - Amendment No, M 9. 174 Unit 2 - Amendment No. % 3. 178 15.3.3 4
D, Service Water System 1.
A reactor shall-not be made critical unless the following-conditions are met:
a.
Six service water ptaps are operable, b.
All necessary valves, interlocks and piping required for the functioning of the Service Water System during accident conditions for the unit which is to be made critical are also operable.
- Unit:1'- Amendment No. M6.174 Unit 2 Amendment No. M 8. 178 g
15.3.3 5 4
a rt
2.
During power operation, the requirements of 15.3.3.0 1 may be modified to allow the following conditions, if the system is not restored to meet the conditions of 15.3.3.D.1 within the time
)eriod specified. the affected reactor (s) will be placed in the lot shutdown condition within six hours and in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
a.
One of the six required service water pumps may be out of service provided a pump is restored to operable status within 7 days.
A second s'ervice water pump may be out of service provided a pump is restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. A third service water pump may be out of service provided two pumps are restored to operable status I
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, b.
The service water ring header continuous flow)ath may be out of service for a period of 7 days.
If less tian four service water pumps are operable, service water system flow shall be evaluated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of less than four service water pumps being operable.
If it is determined that any equipment will not receive sufficient flow, the applicable LCOs for the affected equipment shall be entered.
These LCOs can be exited if system realignment is completed to
-achieve the required flow rates for the affected equipment.
c.
Any or all automatic isolation valves required during accident conditions may be out of service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided at least four service water pumps are operable.
This LCO can be exited provided the lines are isolated with a seismically qualified isolation valve or the valves are restored to operable status, d.
The containment fan cooler outlet motor operated vaives may be open for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided at least five service water pumps are operable.
This LC0 can be exited provided the valves are returned to the closed position or the flowpath is isolated.
B.R111 The normal procedure for starting the reactor is, first, to heat the reactor coolant to near operating temperature, by running the reactor coolant pumps.
The reactor is then m
- boron in the coolant.ge critical by withdrawing control rods and/or diluting
- With this mode of start up, the energy stored in the reactor coolant during the approach to criticality is substantially equal to that during power operation and therefore to be conservative most engineered
. safety system components and auxiliary cooling systems, shall be fully operable.
During low temperature physics tests there is a negligible amount of stored energy in the reactor coolant, therefore an accident comparable in severity to the Design Basis-Accident is not possible, and the engineered safety systems are not required.
Unit 1 - Amendment No. M 3. 174 Unit 2 - Amendment No. M7.178 15.3.3 6 j
minimum volume and boron concentration ensure that:
(1) sufficient water is available within containment to permit recirculation cooling flow to the core:
(2) the reactor will remain subtritical in the cold condition (68 to 212 degrees F) following a small break LOCA assuming complete mixing of the RWST.
RCS spray additive tank, containment spray system piping and ECCS water volumes with all control rods inserted except the most reactive control rod assembly'(ARI-1): (3) the reactor will remain subtritical in the cold condition following a large break LOCA (i)reak flow area greater than 3 ft')
assuming complete mixing of the RWST. RCS ECCS water and other sources of water that may eventually reside in the sump post LOCA with all control rods l
assumed to be out (AR0): and (4) long term subcriticality is maintained fo11osing a steamline break assuming ARI 1 and fuel failure is precluded.
The containment cooling function is provided by two independent systems: (a) fan coolers and (b) containment spray which, with sodium hydroxide addition, provides the iodine removal function.
During normal power operation, only three of the four fan coolers are required to remove heat lost from equipment and piping within the containment."' In the event of a Design Basis Accident, any one of the following combinations will provide sufficient cooling to reduce containment pressure: (1) four fan coolers. (2) two containment spray pumps. (3) two fan coolers plus one containment spray pump."' Sodium hydroxide adoition via one spray pump reduces airborne iodine activity sufficiently to limit off site doses to acceptable values.
One or two fan coolers are permitted to be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during power operation.
Specification 15.3.3.B.2.c requires valves that provide the duplicate function be operable prior to initiating repairs on an inoperable valve.
For the specific case of the containment spray pump discharge (SI 860) valves. SI-860A and SI-8600 provide duplicate functions. Valves SI 860B and SI 860C are not required for system operability.
Hence, prior to removing valve SI 860A from service, valve S1 8600 must be operable and vice versa.
The component cooling system is different from the other systems discussed above in that the components are so located in the Auxiliary Building as to be accessible for repair after a loss of coolant accident, The component cooling water pump together with one component cooling heat exchanger can accommodate the heat remov61 load on one unit either following a loss of coolant accident.
or during normal plant shutdown.
If during the post-accident phase the component cooling water supply is lost, core and containment cooling could be maintained until repairs were effected.")
Unit 1 - Amendment No. %9. 174 I
Unit 2 - Amendment No. M B. 178 15.3.3-9
A total of six service water pumps are installed, only three of which are l
required to operate during the injection and recirculation phases of a postulated loss of coolant accident.'" in one unit together with a hot shutdown or normal operation condition in the other unit.
For either reactor to be critical, six service water pumps must be operable.
i The allowed outage time for a single service water pump is 7 days.
The allowed outage time for two or three service water pumps is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, if more thar,one service water pump is inoperable, the 7 day allowed outage time starts when the first pump is declared inoperable and the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed l
outage time for the second and third pum)s is cumulative starting from the time the second pump is declared inopera)1e.
Therefore, the total time that two or three pumps are inoperable during the period that LCO 15.3.3.D.2.a is in effect must not exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
All pumps must be restored to operable status within 7 days of the first pump being declared inoperable.
Specifications 15.3.3.D.2.c requires four and 15.3.3.D.2.d requires five service water pumas to be operable to provide sufficient flow for accident mitigation when t1ese specifications are in effect.
The service water ring header continuous flowpath LC0 requirement (TS 15.3.3.0.2.b) applies anytime continuity of the flowpath in the service water ring header is interrupted. This includes isolation of any part of the ring header.
This LC0 recognizes that one as)ect of redundancy in the service water system is the ability to isolate a breat in the system and still maintain ability to provide required flow to supported equi > ment.
This capability is impaired anytime the continuous flowpath of tie ring header is blocked.
The 7 day allowed outage time is based on the fact that a piping failure must occur to cause a subsequent problem with system operability.
Piping failures are not considered as the single failure for system functionality during an accident.
TS 15.3.3,D 2.b requires that service water system flow is evaluated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if less than four service water pumps are operable.
This is necessary to ensure that all required equipment will receive sufficient flow in this condition.
If it is determined that any equipment will not receive sufficient flow, the applicable LCOs for the affected equipment shall be entered.
These LCOs can be exited if system realignment is completed to achieve the required flow rates for the affected equipment.
Unit 1 - Amendment No. 49,174-Unit 2 - Amendment No M3.178 15.3.3-10 J
Entry into the applicable LCOs for the affected equipment is also required when any part of the service water ring header is removed from service.
For example. if the north header is removed from service, all Technical Specification required equipment required for operation should be or have already been switched to the south header.
The containment accident fan cooler inoperability requires entry into the applicable LC0 for Unit 2 (TS 15.3.3.B.2.a which is 72 bours) when the header is removed from service.
if Unit 2 is already in a shutdown condition where containment accident fan cooler operability is not required, no LC0 would apply.
Unit I would be subject to the 7 day allowed outage time for the loss of the service water ring header continuous flowpath. The 7 day allowed outage time is based on l
approximate repair time for system piping and the possibility that a mechanical failure in another part of the system could result in a loss of service water system function.
The containment fan cooler service water outlet motor operated valves consist of two fully redundant valves that are automatically opened in response to a safetyinjectionsignal.
Either valve is capable of passing the full flow required of all four fan cooler units in accident mode.
At various time, these valves are opened to allow testing of the containment fan coolers or adjustment of the system flow rates.
If one or both of these motor operated valves are open in a unit, there may be insufficient service water flow if an accident occurs in the other unit and single failure occurs. Therefore, in this case, the other unit is in a limiting condition for operation because relaxation of single failure is necessary.
That unit would be considered the "affected unit" and hence the valves must be closed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the affected unit must be shut down.
If the valves are o)en in both units, they would both be considered "affected" until such time tlat the motor operated valves were closed for a unit, at which time the affected unit would be the unit with the closed valves. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed time is consistent with the relaxation of single failure and allowed outage time associated witn a loss of redundancy for the service water system.
For the case of single unit o)eration, the valves for the operating unit may be open without limitation if tie valves for the shutdown unit are in the shut position or the flowpath is isolated. The flowpath is considered isolated if total flow would not exceed the expected flowrate in the non accident unit during accident conditions.
References FSAR Section 3.2.1 FSAR Section 6.2 FSAR Section 6.3.2 FSAR Section 6.3 FSAR Section 9.3.2 FSAR Section 9.6.2 Unit 1 - Amendment No. 174 Unit 2 - Amendment No. 178 15.3.3 11 j
J
15.3.7 AUXILIARY ELECTRICAL SYSTEMS Acolicabilitv I
Applies to the availability of off site and on site electrical power for plant power operation and for the operation of plant auxiliaries.
l Objective To define those conditions of electrical power availability necessary (1) to I
provide for safe reactor operation, and (2) to provide for the continuing l
availability of engineered safeguards.
Soecification l
A.1 Under normal conditions neither one nor both reactors shall be made l
critical unless the following conditions are met:
a.
At least two 345 KV transmission lines are in service, b.
The 345/13.8 KV and the 13.8/4.16 KV station auxiliary transformers associated with the reactor (s) to be taken critical are in service; or one 345/13.8 KV station auxiliary transformer and the associated 13.8/4.16 KV station auxiliary transformer (s) are in service with the gas turbine operating.
c.
4160 Volt unit supply buses A03 and A04 for the unit to be taken critical are energized from their normal supply.
d.
Both units' B03/B04 bus tie breakers are open with control power removed.
e.
A fuel supply of 11.000 gallons is available in each tank which is being relied upon to supply any operable emergency diesel generator (s),
f.
Four of the five safety related station batteries and all four of the main DC distribution systems are operable, g.
Four battery chargers are operable with one charger carrying the DC loads on each main DC distribution bus:
001. D02. D03 and D04, h.
120 VAC Vital Instrument Buses Y01 Y02 YO3, YO4. Y101 Y102.
Y103, and Y104 for the unit (s) to be taken critical are energized from a safety related inverter, 1.
Foroneorbothunitstobemadecritical,thenormalpowersupplyl and a standby emergency power supply to all the 4100/4B0 Volt safeguards buses shall be operable and the buses are energized from their normal supply, Unit 1 - Amendment No. M 1. 174 Unit 2 - Amendment No. % 5, 178 15.3.7 B.1 During power operation of one or both reactors, the requirements of l
15.3.7.A.1 may be modified to, allow the following arrangements of systems and components:
'a.
If the 345 KV lines are reduced to only one, any operating reactor (s) must be promptly reduced to, and limited to, 50% power.
If all 345 KV lines are lost, any operating reactor (s) will be reduced to supplying its auxiliary load, until one or more 345 KV transmission lines are again avail *ble, b,
If both 345/13.8 KV auxiliary transformers are out of service and only the gas turbine is operating, only one reactor will remain operating and it will be limited to 50% power.
The second reactor will be placed in the hot shutdown condition.
i c.
If the 13.8/4.16 KV auxiliary transformers are reduced to only one, the reactor associated with the out of service transformer must be placed in the hot shutdown condition, j
d.
With a unit in cold or refueling shutdown or defueled, 803 and B04, for that shutdown unit, may be tied together through their common tie breaker for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the required redundant decay heat removal in the shutdown unit and the required redundant shared engineered safety features for the other unit are operable.
If the tie breaker cannot be opened or the conditions of 15.3.7.B.1.e met within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the operating unit shall be placed in the hot shutdown condition within 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, e.
With a unit defueled, B03 and B04, for that shutdown unit, may be tied together through their comon tie breaker in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided:
1)
An evaluation is performed to show that the loads that remain or can be energized by the buses will not cause a potential overload of_the associated diesel generator. The applicable Limiting Conditions for Operation of the equipment removed from service shall be entered for the operating unit.
Unit 1 Amendment No. M1,174
. Unit 2 - Amendment No. M 6, 178 15.3.7 2
2)
A single train of spent fuel cooling is adequate to cool the spent fuel pool.
3)
The required redundant shared engineered safety features for the other unit are operable.
f.
The normal power supply or standby emergency power supply to Unit 1 A05/B03 or Unit 2 A06/B04 may be out of service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the required redundant l
standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or after entry into this LCO and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter, if the normal power supply is out of service, an operable i
emergency diesel generator is supplying the affected 4160/480 Volt buses. After 7 days, both units will be placed in hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, g.
The normal power supply or standby emergency power supply to Unit 1 A06/B04 or Unit 2 A05/B03 or both may be out of service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the required redundant standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or after entry into this LC0 and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.
If the normal power supply is out of service, an operable emergency diesel generator is supplying the affected 4160/4B0 Volt buses. After 7 days, both units will be placed in hot shutdown j
within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, h.
The normal power supply or standby emergency power supply to Unit 1 A05/B03 and Unit 2 A05/B03, or Unit 1 A06/B04 and Unit 2 A06/B04 may be out of service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the required redundant standby emergency power supplies are started within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before or after entry into this LCO and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.
If the normal power supply is out of service, an operable emergency diesel Unit 1 - Amendment No, M1,174 Unit 2 Amendment No MG,178 15.3.7-3
15.3.12 CONTROL ROOM EMERGENCY FILTRATION Ano11cability Applies to the operability of the control room emergency filtration.
Obiective To specify functional requirements of the control room emergency filtration during power operation and refueling operation.
Soecification l
l 1,
Except as specified in 15.3.12.3 below, the control room emergency filtration system shall be operable at all times during power operation and refueling operation of either unit.
2.
a.
The results of in place cold DOP and halogenated hydrocarbon l
tests, conducted in accordance with Specification 15.4.11, on HEPA filter and charcoal adsorber banks shall show a minimum of 99% D0P removal and 99% halogenated hydrocarbon removal, b.
The results of laboratory charcoal adsorbent tests, conducted in accordance with Specification 15.4.11. shall show a minimum of 99% l removal of methyl iodide.
If laboratory analysis results for in-place charcoal indicate less than 99% methyl iodide removal, this l
specification may be met by replacement with charcoal adsorbent which has been verified to achieve 99% minimum removal and which l
bas been stored in sealed containers, and retesting the charcoal adsorber bank for halogenated hydrocarbon removal, c.
The results of fan testing, conducted in accordance with specification 15.4.11, shall show operation within 110% of design flow.
4 Unit 1 Amendment No, MO,174 Unit 2 - Amendment No M B, 178 15.3.12-1
_c.
Halogenated hyrirocarbon testing of the charcoal adsorber bank shall be performed after each complete or partial replacement of charcoal adsorbers or after any structural maintenance of the adsorber housing.- Halogenated hydrocarbon testing shall be at design velocity 1 20%.
d.
Laboratory sample analysis of in place charcoal adsorbent shall be performed at least once per year for standby service or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and, as a minimum, shall be
)
conducted at velocities within 20% of design.1.75 mg/m' inlet iodide concentration. 95% relative humidity and 30*C (86T),
e.
Fans shall be tested at least once per year or after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation since the previous test, and following fan maintenance or repair.
BASH The control room emergency filtration system is designed to filter the control room atmosphere and makeup air to the control room during control room isolation conditions. The control room emergency filtration is normally isolated and not in operation and testing more frequently than that specified is not required to insure operability or performance.
If the efficiencies of HEPA and charcoal adsorbers are as specified, the resulting control room' doses during accident conditions will be lesc than allowable levels in Criterion 19 of Appendix A to 10 CFR 50. The charcoal adsorbent laboratory sample analysis is performed in accordance with ASTM 03803 89. " Standard Test Method-for Nuclear Grade Activated Carbon,"
Unit 1 - Amendment No, M9.174 Unit 2 - Amendment No; MB, 178-15.4.11-2
15.5.2 00NTADestT Appitcability Applies to those design features of the Contalment Systen relating to
<>perational and public safecy.
Objective To define the significant design features of the reactor containment structure.
Specifications A.
Reactor Contaiemment l
1.
The reactor containment completely encloses the entire reactor and Ranctor Coolant Systen and ensures that an acceptable upper limit for leakage of radioactive natorials to the environment is not onceeded even if gross failure of the Rasctor Coolant Systen occurs. The structure provides biological shielding for both nomal and accident situations.
2.
The containment structure is designed for an internal pressure of 60 pais, plus the loads resulting fran an earthquaka producing
.083 in the vertical and 0.123 in the horizontal planes simultaneously. The containment is also structurally designed to withstand an extemal pressure 2.0 poi higher than the internal pressure.II)
R.
penetrations 1.
All penetrations through the containment reinforced concrete pressure barrier for pipe, electrical conductors, ducts and access hatches are prorided with double barriers against laakage.(2) 15.5.2-1 Y
2.
The ar'wtically actuated containnent isolation valves are designt to close upon high pressure in the containment (setpoint no higher than 6 psig) and on a safety injection signal. The actuation system is designed such that no single component failure will prevent containment isolation if re, quired.
C.
Containment Systems 1.
The containment vessel has an internal spray system which is capable of providing a distributed borated water spray of at least 1200 gpm.
During the initial period of spray operation sodium hydroxide would be added to the spray water to increase the removal of iodine from the containment atmosphere.")
2.
The containment vessel has an internal air recirculation system which consists of four ventilation fans and air coolers capable of a total heat removal capability of 41.700 Btu /sec under conditions l following a loss of coolant accident.")
References:
")
FSAR Section 5.1.2.2 FSAR Section 5.1.2.6 FSAR Section 6.4
")
FSAR Section 6.3 Unit 1 - Amendment No.174 Unit 2 - Amendment No. 178 15.5.2-2 N
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