ML20080N288
| ML20080N288 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 03/03/1995 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080N289 | List: |
| References | |
| NPF-37-A-070, NPF-66-A-070, NPF-72-A-061, NPF-77-A-061 NUDOCS 9503060212 | |
| Download: ML20080N288 (22) | |
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UNITED STATES g-j NUCLEAR REGULATORY COMMISSION 4
WASHINGTON, D.C. 2006 Hoot
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. 1
-AMENDMENT TO FACILITY OPERATINu LICENSE Amendment No. 70 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 31, 1993, as supplemented on July 19, 1994,.
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulaticns 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 Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health i
and safety of the public, and (ii) _that such activities will be conducted in compliance 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 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-i cations as indicated in the attachment to this license amendment, and
. paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:
9503060212 950302 PDR ADOCK 05000454 P
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Technical Soecifications The Technical Specifications contained in Appendix A as revised i
through Amendment No. 70 -and the Environmental Protection Plan l
contained in Appendix B, both of which are attached hereto, are hereby incorporated into.this license. The licensee.shall operate the facility in accordance with the Technical Specifications and
.the Environmental Protection Plan.-
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3.
This license amendment.is. effective as of the date of-its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ~
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V RC Georg
. Dick, Jr., Project Manager
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Project Directorate III.
Division of Reactor Projects - III/IV-Office of Nuclear Reactor Regulation Attachment-Changes to the Technical Specifications-Date of Issuance: March 3, 1995 l
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UNITED STATES 1
j-NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3066H001
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r COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-455 1
BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70
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License No. NPF-66 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 31, 1993, as supplemented on July 19, 1994, 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 1; B.
The facility will operate in conformity with the application, the provb fons of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security cr to the health and safety of the pe511c; and E.
The issuance of this amendment is in accordance with 10 CFR.
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:
i
. -. (2)
Technical Specifications The. Technical Specifications contained in Appendix A (HUREG-Ill3),
as revised through Amendment No. 70 and revised by Attachment 2--
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to NPF-66, and the Environmental Protection Plan contained in r
Appendix B, both of which were attached to License No. NPF-37,-
dated February 14, 1985, are hereby incorporated into this
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license. Attachment 2 contains a revision to Appendix A_which is i
hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, I
3.
This license amendment is effective as of the date of its issuance.
'l FOR THE NUCLEAR REGULATORY COMMISSION 1
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George F. Dick, Jr, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Attachmer.t:
Changes to the Technical Specifications Date of Issuance: March 2, 1995
' ATTACHMENT TO LICENSE AMENDMENT NOS. 70 AND 70 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 -
~ Revise the Appendix A Technical Specifications by removing the pages fi.
identified below and inserting the attached pages. The revised pages are
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identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paoes Insert Paaes 3/4 7-16 3/4 7-16 3/4 7-18 3/4 7-18 8 3/4 7-5 B 3/4 7-5 B 3/4 7-6 B 3/4 7-6.
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FV PLANT SYSTEMS g
3/4.7.6 CONTROL ROOM VENTILATION' SYSTEM LIMITING CONDITION FOR OPERATION i-3.7.6 Two independent Control Room Ventilation Systems shall be OPERABLE.
APPLICABILITY: All MODES.
ACTION:
MODES 1, 2, 3 and 4:
With one Contrcl Room Ventilation System inoperable due to an a.
inoperable chiller unit restore the inoperable system to OPERABLE status within 30 days or, be in at least HOT STANDBY 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one Control Room Ventilation System inoperable for reasons other j
than an inoperable chiller unit restore the inoperable system to OPERABLE status within 7 days or, be in at least HOT STANDBY 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MODES 5 and 6:
With one Control Room Ventilation System inoperable, restore the a.
inoperable system to OPERABLE status within 7 days or either 1) ll initiate and maintain operation of the remaining OPERABLE Contro Room Ventilation System in the makeup mode or 2 suspend CORE ALTERATIONS, positive reactivity additions and m)ovement of irradiated fuel.
b.
With both Control Room Ventilation Systems inoperable, or with the OPERABLE Control Room Ventilation System, required to be in the
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makeup mode by ACTION a. not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS, positive reactivity additions, or movement of irradiated fuel.
i SURVEILLANCE REQUIREMENTS 1
1 4.7.6 Each Control Room Ventilation System shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying *that the control room air a.
temperature is less than or equal to 90 F; b.
Atleastonceper31daysonaSTAGGEREDTESTBASISbyinitiating$PA from the control room flow through the Emergency Makeup System H filters and charcoal a,dsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; and flow i
through the recirculation charcoal adsorber for 15 minutes.
l At least once per 18 months or (ds)orber housings, or (2) follow c.
1 after any structural maintenance on the HEPA filter or charcoal a painting fire or chemical release in any ventilation zone communi-catingwIththeEmergencyMakeupSystemfilterplenumby:
1 1)
Verifying that the cleanup system satisfies the in-place penetration testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.5.a, C.S.c 4
and C.5.d of Regulatory Guide 1.52, Revision 2, March,1978, and the system flow rate is 6000 cfm 10% for the i
Emergency Makeup System; BYRON - UNITS 1 & 2 3/4 7-16 AMENDMENT N0. 70 i
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' PLANT-SYSTEMS SilRVE1LLANCE REQUIREMENTS (Continued) f.
After each complete or partial replacement.of a HEPA filter bank, by verifying that the cleanup system satisfies the in-place penetration testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a 00P test aerosol while operating the. Emergency Makeup System at a flow rate of 6000 cfm i 10%; and 3
g.
After each complete or partial replacement of a charcoal adsorber bank in the Emergency Makeup System by verifying that the cleanup system satisfies the in-place penetration testing acceptance-criteria of less than 0.05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the -
system at a flow rate of 6000 cfm i 10%.
h.
At least once per 18 months or (1) after any structural maintenance on-the charcoal adsorber housings, or (2) following painting,he fire or chemical release in any ventilation zone communicating with t recirculation charcoal adsorber by:
(1) Verifying that the recirculation charcoal adsorber satisfies the in-place penetration testing acceptance criteria of less than 2%
total bypass and uses the test procedure guidance in Regulatory Positions C.5.a, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978 and the system flow rate is 49,500 cfm i 10% for the -
recirculationcharcoaladsorber; (2)
Verifying, within 31 days after removal,le-from thethat a laboratory an%. lysis of a representative carbon samp recirculation charcoal adsorber obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52 Revision 2, March 1978, for a methyl iodide penetration of less,than 1% when tested at a temperature of 30*C and a relative humidity of 70%; and (3) Verifying a system flow rate of 49,500 cfm i 10% for the Recirculation Charcoal Adsorber when tested in accordance with ANSI N510-1980.
i.
After each complete or partial replacement of a charcoal adsorber bank in the Recirculation Charcoal Adsorber System by verifying that the cleanup system satisfies the in-place penetration testing acceptance criteria of less than 0.1% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test operating at a system flowrate of 49,500 cfm i 10%. gas while i
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After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of Recirculation Charcoal Adsorber operation by verifying within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2, March 1978 meets thelaboratorytestingcriteriaofRegulatoryGuide1.52, Revision 2, March 1978 for a methyliodide penetration of less than 1% when tested at a temperature of 30*C and a relative humidity of 70%.
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At least once per 18 months, by verifying that each Control Room Ventilation System has the capability to remove the required heat load.
BYRON - UNITS 1 & 2 3/4 7-18 AMENDMENT NO. 70
PLANT SYSTEMS BASES CONTROL ROOM VENTILATION SYSTEM (Continued) design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Cri-terion 19 of Appendix A,10 CFR Part 50. ANSI N510-1980 will be used as a procedural guide for surveillance testing.
The surveillance requirement to verify that each control room ventilation system has the capability to remove the required heat load, as determined by the original heat capacity verification test, consists of a combination of testing and calculations. The 18-month frequency is appropriate since significant degradation of the control room ventilation system is slow and not expected over this time period, 3/4.7.7 NON-ACCESSIBLE AREA EXHAUST FILTER PLENUM VENTILATION SYSTEM The OPERABILITY of the Non-Accessible Area Exhaust Filter Plenum Ventilation System ensures that radioactive materials leaking from the ECCS equipment within the pump rooms following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the safety analyses.
ANSI N510-1980 will be used as a procedural guide for surveillance testing.
3/4.7.8 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip, and 100-kip capacity manufactured by Company "A" are of the same type. The same design mechanical snubbers manufactured by Company "B" for the purposes of this specification would be of a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber loca-tion and size and of systems affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall be determined and approved by the Onsite Review and Investigative function. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.
Tine addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with t
Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant level of snubber protection during an earthquake or severe transient.
There-fore, the required inspection interval varies inversely with the observed BYRON - UNITS 1 & 2 8 3/4 7-5 AMEN 0 MENT N0. 70
PLANT SYSTEMS BASES SNUBBERS (Continued) snubber failures on a given type and is determined by the number of inoperable snubbers found during an inspection of each type.
In order to establish the inspection frequency for each type of snubber on a safety-related system, it was assumed that the frequency of snubber failures and initiating events is constant with time and that the failure of any snubber on that system could cause the system to be unprotected and to result in failure during an initiating event.
USNRC Generic Letter 90-09 " Alternate Requirements for Snubber Visual Inspection Intervals and Corrective Actions" provides information necessary to establish a method of extending or shortening the subsequent visual inspection frequency based upon the failure rates from the previous inspection.
The acceptance criteria are to be used in the visual inspection to determine OPERABILITY of the snubbers.
For example, if a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.
To provide assurance of snubber functional reliability at least 10% of each type of snubber shall be functinnally tested at least once per 18 months with an additional 10% tested for each functional testing failure.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the, applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
BYRON - UNITS 1 & 2 B 3/4 7-6 AMEN 0 MENT N0. 70
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COMMONWEALTH EDIS0N COMPANY t
DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT N0. 1 l
q AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. NPF-72 1.
The Nuclear Regulatory Commission-(the Commission) has found that-i A.
The application for amendment by Commonwealth Edison Company (the-licensee) dated August 31, 1993, as supplemented on July 19, 1994,-
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 I
provisions of the Act, and the rules and regulations of the i
Commission; C.
There is reasonable assurance (i) that the activities authorized i
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 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; l
and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable 1
requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specift-
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cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. NPF-72 is hereby amended to read as follows.
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Technical Specifications The Technical Specifications contained in. Appendix A as revised through Amendment No. 61 and the Environnental. Protection Plan contained in Appendix 8, both of'which are attached hereto, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
g FOR THE NUCLEAR REGULATORY COMMISSION S4 7 6
Ramin R. Assa, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation l
Attachment:
I Changes to the Technical
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Specifications l
Date of Issuance: March 2, 1995 l
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UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20006 4 001 s,...../
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l
h Amendment No.'61 License No. NPF-77
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1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 31, 1993, as supplemented on July 19, 1994, l
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 frrth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; j
l D.
The issuance of this amendment wil? 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-77 is hereby l
amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendix A as. revised through Amendment No. 61 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License j
No. NPF-72, dated July 2, 1987, are hereby incorporated-into this license. The licensee shall operate the facility in accordance-l with the Technical Specifications and the Environmental Protection i
- Plan, j
3.
This license amendment is effective as of the date if its issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION E r Ramin R. Assa, Project Manager.
Project Directorate III-2 Division of Reactor Projects - III/IV i
Offica of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications j
l Date of Issuance:
March 2, 1995 I
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a 8TTACHMENT TO LICENSE AMENDMENT NOS. 61 AND 61 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77.
DOCKET NOS. STN 50-456 AND STN 50-457 l'
Replace' the following pages of the Appendix "A" Technical' Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area.of change.
Pages marked with an asterisk are'provided.for convenience only.
Remove Paaes Insert Paaes i
- 3/4 7-13
- 3/4.7-13 3/4 7-14 3/4 7-14 3/4 7-16a 3/4 7-16a i
- B 3/4 7-3
- B 3/4 7-3 B 3/4 /-4 8 3/4 7-4 B 3/4 7-5 B 3/4 7-5 i
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. PLANT SYSTEMS 3/4.7.5' ULTIMATE HEAT SINK (Essential Service Cooling Pond)
LIMITING CONDITION FOR OPERATION 3.7.5 The essential service cooling pond (ESCP) shall be OPERABLE with:
A minimum water level at or above elevation 590 f t. Mean Sea Level, a.
USGS datum, and b.
An essential service water pump discharge water temperature of less than or equal to 98'F APPLICABILITY: MODES 1, 2, 3, and 4 ACTION:
With the requirements of the above specification not satisfied, be in at least HOT STANDBY 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 />.
SURVEILLANCE REQUIREMENTS 4.7.5.1.
The ESCP shall be determined OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average water temperature and water level to be within their i
limits.
i 4.7.5.2 The ESCP shall be determined OPERABLE at least once per 18 months by the performance of a hydrographic survey to verify:
a.
That the ESCP bottom elevation is less than or equal to 584 feet.
b.
That the ESCP slopes exhibit no excess degradation.
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BRAIDWOOD - UNITS 1 & 2 3/4 7-13
PLANT SYSTEMS-
' 3 /4. 7.'6 CONTROL ROOM VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6 Two independent Control Room Ventilation Systems shall be OPERABLE.
APPLICABIllTY: All MODES.
ACTION:
MODES 1, 2, 3 and 4:
a.
With one Control Room Ventilation System ino)erable due to an inoperable chiller unit, restore the inopera)1e system to OPERABLE status within 30 days or be in at least HOT STANDBY 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one Control Room Ventilation System inoperable for reasons other than an inoperable chiller unit, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MODES S and 6:
l a.
With one Control Room Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days or either 1) initiate and maintain operation of the remaining OPERABLE Control Room Ventilation System in the makeup mode or 2) suspend CORE ALTERATIONS, positive reactivity additions and movement of irradiated fuel.
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b.
With both Control Room Ventilation Systems inoperable, or with the OPERABLE Control Room Ventilation System, required to be in the I
makeup mode by ACTION a. not capable of being powered by an OPERABLE k
emergency power source, suspend all operations involving CORE l
ALTERATIONS, positive reactivity additions, or movement of irradiated
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fuel.
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SURVEllLANCE RE0VIREMENTS 4.7.6 Each Control Room Ventilation System shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying *that the control room air a.
temperature is less than or equal to 90 F; I
b.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the Emergency Makeup System HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; and flow through the recirculation charcoal adsorber for 15 minutes.
1 c.
At least once per 18 months or (1) after any structural maintenanca on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release ir, any ventilation zone communi-cating with the Emergency Makeup System filter plenum by:
1)
Verifying that the cleanup system satisfies the in-place penetration testing acceptance criteria of less than 0.05% and uses the test nwdie guidance in Regulatory Positions C.S.a.
J C.5.c, and C.5.t. of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 6000 cfm i 10% for the -
Emergency Makeup System;
'BRAIDWOOD - UNITS 1 & 2 3/4 7-14 AMENDMENT N0. 61
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L PLANT SYSTEMS
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SURVEILLANCE REQUIREMENTS (Continued)
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'a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978 meets the' laboratory testing criteria'of Regulatory Guide 1.52, Revision 2,
. March 1978 for a methyl _ iodide penetration of less than 1% when tested at a temperature 'of 30*C and a relative humidity of 70%.
L k.
At least once per 18 months, by verifying that 'each Control Room Ventilation System has the capability to remove the required heat load.
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l BRAIDWOOD - UNITS 1 & 2 3/4 716a AMENDMENT N0. 61
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PLANT SYSTEMS'
- p BASES
,3/4.7.1.5 ' MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures'that no more than one steam generator will blowdown in.the event of a steam line:
rupture.
This restriction is required to: (1) minimize the positive reactivity; effects of the Reactor Coolant System cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the Surveillance Requirements are consistent with the assumptions used in the safety analyses.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressura and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70*F and of 60*F and are sufficient' 200 psig are based on a steam generator RTNDT to prevent brittle fracture.
3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Component Cooling Water System ensures.that sufficient cooling capscity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM l
The OPERABILITY of the Essential Service Water System ensures that-l sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. ' The redundant cooling l
capacity of this system, assuming a single failure, is consistent with the i
assumptions used in the accident conditions within acceptable limits.
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3/4.7.5 ULTIMATE HEAT SINK
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The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to hither 1) provide normal
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cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.
i The limitations c<n minimum water level and maximum temperature are based
'l on providing a 30-day cooling water supply to safety related equipment without j
exceeding their design basis temperature and is consistent with the recommenda-tions of Regulatory Guide 1.27, "Vitimate Heat Sink for Nuclear Plants,"
l March 1974.
2 BRAIDWD00 - UNITS 1 & 2 8 3/4 7-3
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' PLANT SYSTEMS BASES p
3/4.7.6 CONTROL ROOM VENTILATION SYSTEM The OPERABILITY of the Control Room Ventilation Syst;em ensures that: (1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for operations personnel during and following all credible accident conditions. Operation of the system with the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
The OPERtBILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Cri-terion 19 of Appendix A, 10 CFR Part 50. ANSI N510-1980 will be used as a-procedural guide for surveillance testing.
The surveillance requirement to verify that each control room ventilation l
system has the capability to remove the required heat load, as determined by the original heat capacity verification test, consists of a combination of I
testing and calculations. The 18-month frequency is appropriate since significant degradation of the control room ventilation system is slow and not expected over this time period.
3/4.7.7 NON-ACCESSIBLE AREA EXHAVST FILTER PLENUM VENTILATION SYSTEM The OPERABILITY of the Non-Accessible Area Exhaust Filter Plenum Ventilation System ensures that radioactive materials leaking from the ECCS
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equipment within the pump rooms following a LOCA are filtered prior to reaching the environment.
The operation of this system and the resultant effect on offsite dosage calculations was assumed in the safety analyses. ANSI N510-1980 will be used as a procedural guide for surveillance testing.
3/4.7.8 SNVBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is main-tained during and following a seismic or other event initiating dynamic loads.
Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured by Company "B" for the purposes of this specification would be of a different type, as would hydraulic snubbers from either manufacturer.
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A list of individual snubbers with detailed information of snubber loca-tion and size and of systems affected shall be available at the plant in accor-dance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Onsite Review and Investigative Function.
The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location BRAIDWOOD - UNITS 1 & 2 B 3/4 7-4 Amendment No. 6
PLANT SYSTEMS BASES i
SNVBBERS (Continued) as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant level of snubber protection during an earthquake or severe transient.
Therefore, the required inspection interval varies inversely with the observed snubber failures on a given type and is determined by the number of inoperable snubbers found during an inspection of each type.
In order to establish the inspection frequency for each type of snubber on a safety-related system, it was assumed that the frequency of snubber failures and initiating events is constant with l
time and that the failure of any snubber on that system could cause the system j
to be unprotected and to result in failure during an initiating event. USNRC Geneiic Letter 90-09 " Alternate Requirements for Snubber Visual Inspection Intervals and Corrective Actions" provides information necessary to establish a method of extending or shortening the subsequent visual inspection frequency based upon the failure rates from the previous inspection.
The acceptance criteria are to be used in the visual inspection to deter-mine OPERABILITY of the snubbers.
For example, if a fluid port of a hydraulic 1
snubber is found to be uncovered, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.
To provide assurance of snubber functional reliability at least 10% of each type of snubber shall be functionally tested at least once per 18 months with an additional 10% tested for each functional testing failure.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed' to qualify the snubber for the applicable design conditions at either the com-pletion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal
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replaced, spring replaced, in high radiation area, in high temperature area, i
BRAIDWOOD - UNITS 1 & 2 B 3/4 7-5 Amendment No. 61