ML17326B197
| ML17326B197 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/11/1986 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8602210569 | |
| Download: ML17326B197 (67) | |
Text
Docket Nos.:
50-315 and 50-316 FPg gy 1986 LICENSEE:
FACILITY:
SUBJECT:
Indiana and Michigan Electric Company Donald C.
Cook Nuclear Plant, Units I and 2
SUMMARY
OF MEETING HELD ON JANUARY 13,
- 1986, WITH INDIANA AND MICHIGAN ELECTRIC COMPANY TO DISCUSS BASIS FOR ACCEPTABLE PROVISIONS OF TECHNICAL SPECIFICATIONS FOR FIRE PROTECTION, ENGINEERED SAFETY FEATURES VENT
- SYSTEM, CONTAINMENT SUMP LEVEL INSTRUMENTATION, AND CONTAINMENT ISOLATION VALVES.
The staff met with the licensee on January 13, 1986, in the second of a series of meetings to discuss and resolve outstanding problems with the Technical Specifications.
The list of meeting attendees in enclosed as Enclosure 1.
The licensee made the presentation from the viewgraphs enclosed as Enclo-sure 2.
The specific agenda items covered in the meeting are listed on the first page of Enclosure 2.
There were no specific decisions made at the meeting; the licensee will formalize their submittals and include the necessary supporting documentation to justify any proposed changes.
In addition to the presentation materials in Enclosure 2, the licensee requested that the hourly fire watch patrol requirements be clarified to indicate that the hour would be +255 as is the case for Technical Specification Section 4.0.2.
The action statement for 3.7.9.3 indicates that the Roving Fire Watch Patrol is defined in the Bases section.
The licensee was advised to submit a revision to the Bases section to resolve the issue.
The licensee is also aware of the approach used in the Perry Technical Specifications where the fire protection Technical Specifications were included in a separate "plan" which was referenced in the license or Technical Specifications.
The licensee indicated they may follow this course in order to simplify the Technical Specifications.
Enclosures:
As stated cc:
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Mr. John Dolan Indiana and Michigan. Electric Company PPB 1 1 1S86 Donald C.
Cook Nuclear Plant CC:
Mr. M. P. Alexich Yice President Nuclear Operations American Electric Power Service Corporation I Riverside Plaza
- Columbus, Ohio 43215 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 W.
G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident-. Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, DC 20036 Mayor, City of Bridgeman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 The Honorable John E. Grotberg United States House of Representatives Washington, DC 20515 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 J. Feinstein American Electric Power.
Service Corporation l Riverside Plaza
- Columbus, Ohio 43216
ENCLOSURE 1
TECHNICAL SPECIFICATION AND REGULATORY REQUIREMENTS MEETING JANUARY 13, 1986 Name D. Wigginton J.
Shapaker K. S.
West J.
Hayes C. Tink1er S.
Brown K. Toth H. Young M. Ackerman J. Feinstein W. Harvey T. Anderson B. Svensson L. Gibson Or anization NRR/PWR¹4 NRR/PSB NRR/PSB NRR/PSB NRR/PWR-A NRR/FOB AEP AEP AEP AEPSC AEPSC D.C.
Cook D.C.
Cook D.C.
Cook
'H URE 2 AGENDA 1.
Control Room Ventilation 2.
Spent Fuel Pool Ventilation 3.
Ventilation System Testing Requirements a.
ANSI N510-1975 vs.
1980 b.
Air Distribution Test c.
Charcoal Testing After Painting, Fire, etc.
4.
Containment isolation 5.
Main Steam Stop Valve Testing 6.
Air Lock Testing 7.
Containment Sump Level Instrumentation
CONTROL ROOM PRESSURE BOUNDARY PROBLEM:
TECH SPECS DO NOT ADDRESS CONTROL ROOM PRESSURE BOUNDARY INOPERABILITY.
o INABILITYTO PRESSURIZE 3.0.3 ONE-HOUR SHUTDOWN.
o FILTRATION STILL AVAILABLEWITHOUT PRESSURIZATION.
o CURRENTLY UNABLE TO DO THOROUGH MAINTENANCE WITHOUT SHUTDOWN.
SOLUTION:
CHANGE TO ALLOW 72 HOURS FOR INOPERABLE PRESSURE BOUNDARY.
CONTROL ROOM VENTILATIONFILTERS PROBLEM:
TECHNICAL SPECIFICATIONS DO NOT ALLOW SUFFICIENT TIME FOR CONTROL ROOM VENTILATION FILTER MAZNTENANCE.
o 24 HOURS CURRENTLY ALLOWED.
o MAINTENANCE COULD INVOLVE TOTAL CHARCOAL REPLACEMENT AND TESTING.
SOLUTION:
CHANGE TO ALLOW 72 HOURS..
CONTROL ROOM MAKEUP AZR PROBLEM:
TECH SPECS DO NOT ADDRESS LIMITS ON OUTDOOR MAKEUP AIR TO ENSURE DOSES WITHIN CFR LIMITS.
SOLUTION:
o ADD A SURVEILLANCE REQUIREMENT TO VERIFY THAT THE AMOUNT OF OUTDOOR MAKEUP AZR IS WITHIN LIMITS WHICH NELL ENSURE CONTROL ROOM HABITABILITY.
o DETAILS WILL BE PLACED IN THE BASES SECTION.
o ANALYSES BASED ON NEW ICRP 30 DOSE CONVERSION FACTORS, AND WESTINGHOUSE SPRAY ADDITIVE TANK DELETION ANALYSIS.
USE OF ICRP 30 DOSE CONVERSION FACTORS o
REG.
GUIDE 1.4 AND THE STANDARD REVIEW PLAN REFERENCE ICRP 2.
o ICRP 30 SUPERSEDES ICRP 2.
o ICRP 30 1978 ZCRP 2 1959 o
CHANGES NEW INFORMATION ON RADIATION EFFECTS ON BODY.
BETTER MODELING OF UPTAKE AND RETENTION OF RADIOACTIVE MATERIALS BETTER DATA ON RADIOACTIVE DECAY.
USE OF ICRP 30 RECOMMENDED BY WESTINGHOUSE ELECTRIC AS PART OF SPRAY ADDITIVE TANK DELETION ANALYSIS.
CONTROL ROOM - ADDITIONALCHANGES 1.
ADDZTION OF MODES 5 AND 6 APPLICABILITYAND ACTIONS FOLLOWS GUIDANCE GIVEN ZN GENERIC LETTER 83"37 2.
MINOR CHANGES TO MORE ACCURATELY REFLECT THE OPERATION OF THE SYSTEM
BASES SECTION FOR CONTROL ROOM BASES SECTiON WILL INCLUDE:
o DEFINITION OF PRESSURE BOUNDARY.
o DEFINITXON OF RECIRCULATION/CLEANUP MODE OF OPERATION.
o REASONS FOR OUT OF SERVXCE TIMES.
o USE OF ANSI NS10-1980.
o METHOD OF CALCULATING CONTROL ROOM DOSES, INCLUDING USE OF XCRP 30 AND THE WESTINGHOUSE SPRAY ADDITIVE TANK DELETION ANALYSIS.
o LIMXTS ON FLOW, INCLUDING OPTXONS.
ANSI N510 1975 vs.
1980 PROBLEM:
VENTILATION SYSTEMS NOT DESIGNED TO ANSI N509 STANDARDS.
o TECH SPECS REQUIRE FILTER TESTING TO ANSI N510-1975.
o AIR-AEROSOL TEST IS A PREREQUISITE FOR IN-PLACE HEPA AND CHARCOAL TESTS.
CANNOT MEET CRITERIA OF 1975 OR 1980 STANDARDS.
SOLUTION:
CHANGE TO 1980 STANDARD.
SPECIFIC EXEMPTIONS IN BASES.
o ANSI N510-1980 ONLY FOR TECHNICAL GUIDANCE IF NON-N509 SYSTEM.
AIRFLOW DISTRIBUTION PROBLEM:
ESF> SPENT FUEL POOL TECH SPECS REQUIRE AIRFLOW DISTRIBUTION TEST EVERY 18 MONTHS.
P o
NUREG-0452, REV.
4 (STS)
DOES NOT REQUIRE THlS.
o ANSI N510 (1975 AND 1980)
LISTS TEST AS ACCEPTANCE TEST.
SOLUTION:
DELETE REQUIREMENT FROM TECH SPECS.
FILTER TESTING PROBLEM:
TECH SPECS REQUIRE FILTER TESTING FOLLOWING ANY FIREr PAINTING, OR CHEMICAL RELEASE IN AN AREA COMMUNICATING WITH THE FILTERS.
0 DO NOT CURRENTLY CONSIDER AMOUNT OF PAINTINGg SMOKE p ETC ~
o DO NOT ACCOUNT FOR NON-VOLATILE CHEMICALS OR PAINTS, OR THE DEGREE OF CHARCOAL AFFINITY FOR PARTICULAR SUBSTANCES.
SOLUTION:
CHANGE TECH SPEC TO ALLOW FOR EVALUATION.
DRAFT CONTROL ROOM TECHNICAL SPECIFICATIONS
PLANT SYSTEMS 3/4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITINGCONDITION FOR OPERATION 3.7.5.1 The control room emergency ventilation system shall be OPERABLE with:
ao b.
co d.
Two independent heating and cooling systems, Two independent pressurization
- fans, One charcoal adsorber and HEPA filter train, and The control room pressure boundary.
APPLICABILITY: All MODES.
ACTION:
MODES 2, 2, 3, 4:
a ~
With one heating and cooling system inoperable, 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 />.
b.
With one pressurization fan inoperable, restore the inoperable" fan 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 />.
c ~
With the filter train inoperable, restore the filter train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 />.
d.
With the control room pressure boundary inoperable, restore the control room pressure boundary to OPERABLE status within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s: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 6s 4
e.
With one pressurization fan inoperable, do on'e of the following:
(1) restore the inoperable fan to OPERABLE status within 7 days, or (2) initiate and maintain operation of the remaining OPERABLE pressurization fan and the filter train in the recirculation mode, or (3) suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
DE C
COOK - UNIT 2 3/4 7-14
f.
With any of the following (1) both heating and cooling systems; (2) both pressurization fans; (3) the filter train (4) the control room pressure boundary; inoperable, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE RE UZREMENTS 4.7.5.1 The control room emergency ventilation system shall be demonstrated OPERABLE:
a.
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 temperature is < 120 F.
b.
At least, once per 31 days on a STAGGERED TEST BASIS by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the system operates for at least 15 minutes.
c.
At least once per 18 months or (1) after any structural maintenance on the HEPA f'lter or charcoal adsorber
- housings, or (2) following painting, fire or chemical release deemed by evaluation to be significantly detrimental to the filters by:
1.
Verifying that the charcoal adsorbers remove~99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 6000 cfm i 10%.,
2.
Verifying that the HEPA filter banks remove 99% of the DOP when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 6000 cfm + 10%.
3.
Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal efficiency of
'7 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1980 (130 C, 95% R.H.).
The carbon samples not obtained from test canisters shall be prepared by either:
a)
Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or D.
CD COOK UNIT 2 3/4 7-15
b)
Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.
4.
Verifying a system flow rate of 6000 cfm +
10% during system operation in the recirculation/cleanup
- mode, when tested in accordance with ANSI N510-1980.
d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by either:
Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of ) 90% for radioactive methyl iodide when the" sample is tested in accordance with ANSI N510-1980 (130 C, 95% R.H.); or 2.
Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrates a
removal efficiency of
> 90% for radioactive methyl iodide when the samples are tested in accordance with ANS1 N510-1980 (130 C, 95% R.H.)
and the samples are prepared by either:
a)
Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b)
Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.
Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the system shall be demonstrated OPERABLE by also:
a)
Verifying that the charcoal adsorbers remove 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 6000 cfm + 10%, and b)
Verifying that the HEPA filter banks remove 99% of the DOP when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow of 6000 cfm 2 10%.
D. C.
COOK - UNIT 2 3/4 7-16
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) e.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is 46 inches Water Gauge (W.G.) while operating the ventilation system at a flow rate of 6000 cfm + 10%.
2.
Verifying that on a Safety Injection Signal or a containment phase.A isolation signal, from either Unit 1 or Unit 2, the system automatically initiates operation in the recirculation/cleanup mode.
3.
Verifying that the system maintains the control room at-1/16 inch W.G. relative to the outside atmosphere at a system flow rate of 6000 cfm +
10% while operating in the recirculation/cleanup mode.
4.
Verifying that the system maintains the machine room and the P250 computer room at a positive pressure with respect to the outside atmosphere.
5.,
Verifying that the combination of filtered makeup and unfiltered inleakage is within limits which will maintain thd control room habitable under accident conditions.,
f.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove~ 99% of the DOP when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 6000 cfm
+ 10%.
g.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove
~ 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 6000 cfm + 10%..
D.
C COOK UNIT 2 3/4 7-16a
DRAFT SPENT FUEL POOL TECHNICAL SPECIFICATIONS
REFUELING OPERATIONS STORAGE POOL VENTILATION SYSTEM*
LIMITINGCONDITION FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.
APPLICABILITY: Whenever irradiated fuel is in the storage pool.
ACTION:
r With no fuel storage pool exhaust ventilation system
- OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.9.12 The above required fuel storage pool air cleanup systems shall be demonstrated OPERABLE:
a r At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that, the train operates for at least 15 minutes.
b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber
- housings, or (2) following painting, fire or chemical release deemed by evaluation to be significantly detrimental to the filters by:
1.
Verifying that with the exhaust ventilation system operating at a flow rate of 30,000 cfm t 10% and exhausting through the HEPA filter and charcoal adsorbers, the total bypass flow of the exhaust ventilation system to the facility vent, including leakage through the exhaust ventilation system diverting valves, is < 1% when the exhaust ventilation system is tested by admitting cold DOP at the storage pool exhaust ventilation system intake.
- Shared system with D. C. Cook - Unit 1 D. C.
COOK UNIT 2 3/4 9-12
REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 2.
Verifying that the charcoal adsorbers remove 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI NS10-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm + 10%.
3.
Verifying that the HEPA filter banks remove 2 99% of the DOP when they are tested in place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm ~ 10%.
4.
Verifying within 31 days after removal'hat a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal efficiency of
> 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1980 (130 C, 95% R.H.).
The carbon samples not obtained from test canisters shall be prepared by either:
(a)
Emptying one entire bed from a removed adsorber tray, mixing the adsorbent, thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or (b)
Emptying a lcngitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to thickness of the bed.
5.
Verifying a system flow rate of 30,000 cfm i 10% with each exhaust fan while testing in accordance with ANS1'510-1980.
Testing shall be performed with the supply fans operating.
c.
. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by either:
1.
Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of 290% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1980 (130 C, 95% R.H.); or D. C.
COOK - UNIT 2 3/4 9-13
REFUELING OPERATIONS SURVEILLANCE RE UIREMENTS (Continued 2.
Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrates a
removal efficiency of2 90% for radioactive methyl iodide when the samples are tested in accordance with ANSI N510-1980 (130 C, 95% R.H.)
and the samples are prepared by either:
a)
Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b)
Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent"thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.
Subsequent to reinstalling the adsorber tray used for obtaining the carbon
- sample, the system shall be demonstrated OPERABLE by also:
a)
Verifying that the charcoal adsorbers remove
~ 99% of a halogenated hydrocarbon refrigerant test gasiwhen they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 30,000 cfm + 10'h, and b)
Verifying that the HEPA filter banks remove >99% of the DOP when they are tested in place in accor'dance with ANSI N510-1980 while operating the ventilation system at a flow rate of 30,000 cfm + 10%.
d.
At least once per 18 months by:
1.
Verifying that pressure drop across the combined HEPA f'lters and charcoal adsorber banks is L6 inches Hater Gauge while operating the exhaust ventilation system at a flow rate of 30,000 cfm + 10%.
I D. C.
COOK - UNIT 2 3/4 9-14
REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 2.
Verifying that on a high-radiation signal, the system automatically directs its exhaust flow through the charcoal adsorber
- banks, and automatically shuts down the storage pool ventilation system supply fan units.
3.
Verifying that with one exhaust fan operating and flow directed through the charcoal filters, the exhaust ventilation system maintains the spent fuel pool storage area at a negative pressure of 1/8 inches Water Gauge or greater relative to the outside atmosphere.
The test may be performed with either the supply fans operating or the supply fans not operating.
e.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at.a flow rate of 30,000 cfm i 10%.
f.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested'n place in accordanc'e with ANSI N510-1980 while operating the ventilation system at a flow rate of 30,000 cfm i 10%.
D. C.
COOK UNIT 2 3/4 9>>15
DRAFT ESF VENTILATION SYSTEM TECHNICAL SPECIFICATIONS
PLANT SYSTEMS 3/4.7.6 ESF VENTILATION SYSTEM LIMITINGCONDITION FOR OPERATION 3.7.6.1 Two independent ESF ventilation system exhaust air filter trains shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the ESF ventilation system exhaust air filter train inoperable, restore the inoperable train 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 />.
SURVEILLANCE RE UIREMENTS 4.7.6.1 Each ESF ventilation system exhaust air filter train shall be demonstrated OPERABLE:
a 0 At Least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filter and charcoal adsorber train.and verifying that the train operates for at least 15 minutes.
b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber
- housings, or (2) following painting, fire or chemical release in any ventilation zone deemed by evaluation to be significantly detrimental to the filters by:
1.
Verifying that with the system operating at a flow rate of 25,000 cfm i 10% and exhausting through the HEPA filters and charcoal adsorbers, the total bypass flow of the system to the facility vent, including leakage through the system
-diverting valves, is L1% when the system is tested by admitting cold DOP at the syst: em intake.
D. C.
COOK UNIT 2 3/4 7-17
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) 2.
Verifying that the charcoal adsorbers remove ~ 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm + 10%.
3.
Verifying that the HEPA filter banks remove 5 99% of the DOP when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm + 10%.
4 ~
Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal efficiency of 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1980 (130 C, 95% R.H.).
The carbon samples not obtained from test canisters shall be prepared by either:
a)
Emptying one entire bed from a removed'dsorber
- tray,
'ixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a 'length equal to the 'thickness of the bed, or b)
Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.
5.
Verifying a system flow rate of 25,000 cfm +
10% during system opeiation when tested in accordance with ANSI N510-1980.
c ~
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by either:
1.
Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency ~ 90% for radioactive methyl iodide when the sample is tested. in accordance with ANSI N510-1980 (130 C, 95% R.H.)
g or D. C.
COOK - UNIT 2 3/4 7-18
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrates a
removal efficiency of >90% for radioactive methyl iodide when the samples are tested in accordance with ANSI N510-1980 (130 C, 95% R.H.) and the samples are prepared by either:
a)
Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b)
Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.
Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the system shall be demonstrated OPERABLE hy also:
a)
Verifying that the charcoal adsorbers remove 2 99% of "a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm +
10% and b)
Verifying that the HEPA filter banks remove~99% of the DOP when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm + 10%.
d.
At least once per 18 months by>
1.
Verifying that the pressure drop across the combined HEPA filters an~harcoal adsorber banks is L.6 inches Water Gauge while operating the ventilation system at a flow rate of 25,000 cfm + 10%.
D. C.
COOK UNIT 2 3/4 7-19
PLANT SYSTEM SURVEILLANCE RE UIREMENTS (Continued) 3.
Verifying that the standby fan starts automatically on a Containment Pressure--High-High Signal and diverts its exhaust flow through the HEPA filters and charcoal adsorber banks on a Containment Pressure High-High Signal.
e.
After each complete or partial replacement of HEPA filter bank by verifying that the HEPA filter banks remove 99% of the DOP when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm +
10%.
f.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove+99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1980 while operating the ventilation system at a flow rate of 25,000 cfm + 10%.
D. C.
COOK - UNIT 2 3/4 7-19a
ISOLATION VALVES PROBLEM:
WE HAVE BEEN INTERPRETING INOPERABLE ISOLATION VALVE AS INSUFFICIENT FOR CONTAINMENT INTEGRITY UNDER ANY CIRCUMSTANCES.
o INOPERABILITY COULD BE DUE TO MANY FACTORS, e.g.
STROKE TIME, AIR OPERATOR, SOLENOID ETC.
o CLOSING VALVE SUFFICIENT ZF INOPERABILITY DUE TO REASONS OTHER THAN INABILITYTO ISOLATE.
SOLUTION:
CHANGE TECH SPEC 3.6.3.1 TO ALLOW AUTOMATIC VALVES TO BE CLOSED AND DEACTIVATED.
CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 Thy containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.
The ACTION statement of T/S 3/4.6.3 is not applicable to the containment purge sup-ply and exhaust isolation valves, VCR-101 through 106 and VCR-201 through 206, listed in Table 3.6-1.
The Limiting Condition for Operation and its associated ACTION statement for these valves is given in Technical Specification 3/4.6.1.7.
APPLICABILITY:
MODES 1,2,3 and 4.
ACTION:
With one or more of the isolation valve(s) specified in Table 3.6-1 inoperable, either:
a.
Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
,b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or
~+
c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or d.
Be in at least HOT STANDBY wi.'thin 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 />.
SURVEILLANCE RE UIREMENTS 4.6.3.1.1 The isolation valves specified in Table 3.6-1 shall be demonstrated OPERABLE:
a.
At least once per 92 days by cycling each OPERABLE power operated or automatic valve testable during plant operation through at least one complete cycle of full travel.
b.
Immediately prior to returning the valve to service after maintenance, repair or replacement work is performed on the D.C.
COOK-.UNIT 1 3/4 6-14
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) valve or its associated
- actuator, control or power circuit by performance of the cycling test,
- above, and verification of isolation time.
4.6.3.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
a 0 Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation. position.
ci Verifying that on a Containment Purge and Exhaust isolation
- signal, each Purge and Exhaust 'valve actuates to its isolation position.
d.
Cycling each power operated or automatic valve through at least one complete cycle of full travel and measuring the isolation
'time.
e.
Cycling each manual valve not locked, sealed or otherwise secured in the closed position through at least one complete cycle'of full travel.
I
- If inoperability of an automatic isolation valve is due to factors other
= than the ability to provide containment isolation capability, the valve may be considered OPERABLE for purposes of this specification provided it is closed and deactivated.
The valve must be verified to be closed and deactivated at least once per 31 days.
D. C.
COOK UNIT 1 3/4 6-15
STEAM LINE ISOLATION PROBLEM:
TECH SPECS REQUIRE A CHANNEL FUNCTIONAL TEST OF THE MANUAL ACTUATION ASSOCXATED CIRCUITRY ON A MONTHLY BASIS.
REF:
T/S TABLE 4.3-2, ITEM 4A.
o SYSTEM DESXGN DOES NOT ACCOMMODATE MANUAL TESTING OF THIS CIRCUITRY IN MODES 1 OR 2 WITHOUT RISKING UNIT TRIP.
o THE SYSTEM IS ALREADY TESTED UNDER T/S 4.7.1.5 ON A QUARTERLY BASIS.
(UNIT 1)
SOLUTION: CHANGE T/S TABLE 4.3-2, ITEM 4A TO AN 18-MONTH (REFUELING) SURVEILLANCE.
~
~
XQCLd.~
~A~IN~IP Q~QQB ~~~I~
7 P
~RT II~I 7
P Ta 7
N Q,T~~~II'I~ IIT 5QQTQNIfR ILK 0
<I~TRA~T I.tanar~
~~~TN L5RS)~L g~w HSS A
VI W P
I
~ ~
Zzl I
~
P s
gI(
II
~
II I I V
lUEKLLhIL T
a 7
N OONALO C.COOK NUCLEAR PLANT PERSONNEL LOCKS TYPICAL ARRANGEMENT 8 DETAILS Pig 5 2 5 JULY 1982
BUBBLE TIGNT DAMPER IlV-ACRDA I AIR CONDITIONING SYSTEM p250 Roon MACHINE RO.OM EMERGENCY CLEANUP SYSTEM AIRFMH MEASURING STATION IlV ACRDA 2 HV-ACRDA-3 EL. 650'-0"
~ ~.o. s
~
CONTROL ROON EL. 633 e -0 AUX~
CABLE g ~
VAULT VAULT 0
VENT FAN COWTR0L ROOM CA BLE vAtlLT CABLE VAULT FAN AUX
~ CABLE VAULT
CONTROL ROOM VENTILATION SYSTEM FUNCTIONS NORMAL HEATING AND COOLING NORMAL FRESH AIR MAKEUP EMERGENCY COOLING MAINTAIN HABITABILITY FOLLOWING TOXIC GAS RELEASE MAINTAIN HABITABILITYFOLLOWING RADIOLOGICAL RELEASES KEEP CO<
AND SMOKE OUT OF CONTROL ROOM FOLLOWIAG CABLE VAULT FIRE
NOMINAL OP(RATIOht BUBBLE TIGMT DAMPER NV-ACRDA-I AIR CONDITIONING SYSTEM 0 PEA/
pzs-oooo'ACHINE RO.On EMERGENCY CLEANUP SYSTEM AIRFLOW MEASURING STATION MV-ACRDA 2 NV-ACRDA-3 EL. 650'"
eo~rRo~ Roo~
EL. 633'-0" AUX~
CABLE g ~
VAULT VAULT FAN coN tR0L ROOtt CABLE'AEALT 4
4 AUX.
VAULT VENT U
VAULT
RAOM TlON PJODE AIR CONDITIONING SYS~
BUBBLE TIGllT DAMPER llV-ACRDA"I CLo.sag M
M
~C CC 1
P250 ROOff MACHlME RO.On 4
~
41). '
4
~
4 EMEljQENCY CLEANUP SYSTEM C
w AIRPIDW MEASURING STATION 0 PEA IIV-ACRDA-3 I
al P~arl ALL >
DPEH HV-ACRDA"2 EL. 650'-0" M
O COblTROL Roon AUX CABLE 0 ~
VAULT VAULT U
VENT FAN 0
h' coNTRQL RODIN CA 8LF VAULT EL. 633'0" AUX.
VAULT~ g VENT U
VAULT
FIRE PA'OTEC 1/ON m oDE BUBBLE TIGNT DAMPER IlV-ACRDA-I AIR CONDITIONING SYSTEM C Los'c 0 P250 R00/7 HACHlME RO.OPl EMERGENCY CLEANUP SYSTEM AIRFLOW MEASURING STATION NV-ACRDA-2 4
~ 0
~
4 C
u OPEH n
NV-ACRDA-3 4
~
a
~'~
o EM EL; 6500-P" eOWTRO~ ROOrr
~ ~
~
r EL. 633'-0" AUX~
CABLE 0 ~
VAUIT VAULT 0
VENT FAN CONTROL ROOrl CABLE vAtlL7 CABLE VAULT AUX~
~ CABLE
'VAULT
SPENT FUEL POOL VENTILATXON CONFIGURATION PROBLEM:
TECH SPECS DO NOT SPECIFY WHXCH SPENT FUEL POOL FANS SHOULD RUN DURXNG VENTILATION SYSTEM TESTXNG COOK HAS 4
SUPPLY UNITS AND 2 1004 CAPACITY EXHAUST FANS
'ALL SUPPLY UNITS SHUT DOWN'WITH HIGH RADIATION SIGNAL TECH SPECS SPECIFY 30,000 CFM THIS IS REQUIRED ONLY WITH SUPPLY AND EXHAUST UNITS RUNNING
~
UNDER ACCIDENT CONDITIONS, TECH SPEC TEST FLOW MINIMUM FLOW OF 30,000 CFM -104 IS NOT REQUIRED
~
LESS FLOW XS CONSERVATIVE FOR ACCIDENT ANALYSIS PROVXDED NEGATIVE PRESSURE IS MAINTAINED BECAUSE OF RESIDENCE TXME CONSIDERATIONS SOLUTION:
PLACE FAN CONFIGURATXON IN TECH SPECS t'
SUPPLY AIR HAHDLIHG UHITS 1 C
2 SPEtiT FUEL PIT FUEL HANDLING AREA EXHAUST SYSTEM SUPPLY AIR HAHDLIHG UNITS 3 C 4
ANSI N510 1975 vs.
1980 PROBLEM:
VENTILATION SYSTEMS NOT DESIGNED TO ANSI N5'09 STANDARDS.
o TECH SPECS REQUIRE FILTER TESTING TO ANSI N510-1975.
o AIR-AEROSOL TEST IS A PREREQUISITE FOR IN-PLACE HEPA AND CHARCOAL TESTS.
CANNOT MEET CRITERIA OF 1975 OR 1980 STANDARDS'OLUTION:
CHANGE TO 1980 STANDARD.
SPECIFIC EXEMPTIONS IN BASES.
o ANSI N510-1980 ONLY FOR TECHNICAL GUIDANCE IF NON-N509 SYSTEM.
AIR-AEROSOI MIXING UNI FORMITY TEST PROBLEM ANSI N510-75 8 80 - AIR AEROSOL MIXING UNIFORMITY.TEST A. PREREQUISITE FOR HEPA R CHARCOAL TESTING EMERGENCY SAFETY FEATURES (ESF)
VENT SYSTEM
~
NOT N509 -76 DES IGN
~
OPERATIONAL BEFORE N510-75 WAS IN FORCE BECAUSE OF PREREQUISITE STATEMENT A TEST HAS PERFORMED IN 1985 ON THE UNIT WITH MORST CASE DISTRIBUTION
SUNNATION OF EXENPTION PREVIOUSLY DISCUSSED MITH THE NRC ANSI N510-8 STATE UPSTREAN SAMPLE CONCENTRATION ACROSS SAMPLE PLANE SHALL BE MITHIN + 20X OF NEAN CONCENTRATION OUR TEST HAS A VARIANCE OF + 42Xr -30X OF f'lEAN CONCENTRATION BASED ON A FEM POINTS
. AFFECTING MHOLE DISTRIBUTION REASON IS DESIGN OF INTAKE DUCT TO MHICH ME MERE LICENSED
READINGS IN THE CENTER OF THE SANPLE PLANE>
MHERE THE NORNAL UPSTREAN SANPLE IS TAKEN. ARE WITHIN + 20X OF THE NEAN THE ESF FILTER SYSTEi'I DRAWS AIR FRON A PLENUN NITHOUT ANY INTAKE DUCT THERE ARE NO ELBOMS OR DUCT RUNS TO GENERATE TURBULENCE THE FUEL HANDLING EXHAUST FILTRATION UNIT HAS NANY ELBOWS BET'j<EEN THE INJECTION POINT AND THE SANPLE POINTr PROVIDING 600D DISPERSION THE CONTROL ROON CLEANUP UNIT HAS AN ELBOW IN THE INTAKE PLUS A BAFFLE PLATE IN THE UNIT TO PROVIDE 600D DISPERSION
REPORT OF INDENPENDANT CONSULTANT JOHN R,
- HUNT, NUCLEAR CONSULTING SERVICES MEMBER OF ANSI N510 MAINTENANCE COMMITTEE WITNESSED OUR TEST IN A CONSULTING ROLE STATED THAT EACH AREA OF THE SAMPLE PLANE HAS ADEQUATELY CHALI ENGED STATED "MHILE CERTAIN INDIVIDUALREADINGS DIFFER FROM THE MEAN CONCENTRATION BY MORE THAN + 20X.
THE INTENTS THOUGH NOT THE LETTER OF N510-80 IS CERTAINLY BEING MET,"
STATED IT MOULD BE FRUITLESS TO ADD BAFFLING'R MAKE OTHER ATTEMPTS TO ENHANCE AIR-AEROSOL MIXING
STEAM LINE ISOLATION CS RE UIRE A CHANNEL FUNCTXONAL TEST OF THE CXRCUXTRY ON A MONTHLY BASIS.
MANUAL ACTUATION ASSCCXATED CIRC REF:
T/S TABLE 4 3 2i ITEM 4A.
DOES NOT ACCOMMODATE MANUAL TESTING OF o
SYSTEM DESIGN T RXSKING UNiT THIS CXRCUXTRY IN MODES 1 OR 2 NITHOU TRIP.
o THE SYSTEM IS ALREADY TESTED UNDER T/S 4.7.1.5 ON A QUARTERLY BASXS.
(UNIT 1)
ITEM 4A TO AN 18-MONTH SOLUTION:
CHANGE-T/S TABLE 4.3-2, ITEM
,(&FUELING) SURVEILLANCE..
C/0 FUNCTIONAL UNIT 4.
STEAM LINE ISOLATION TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIQHAL OPERATIONAL ACTUATION RELAY RELAY
. SURVEILLANCE CHECK CALIBRATIOH TEST TEST ii I ii T Tiii iiii i
Rlliiiii 5.
a.
Manual H.A.
H.A.
b.
Automatic Actuation Logic and Actuation Relays c.
Containment Pressure S
High-High d.
Steam. Flow in Two Steam S
LinesHigh Coincident With Either 1
Tav
- Low-Low or S
2.
Steam Line S
Pressure Low TURBINE TRIP AND FEEDWATER ISOLATION H.A.
H.A.
H.A.
H. A.
R N. A.
H.A.
N.A.
H.A.
H.A.
M(1)
N.A.
H.A.
H.A.
H.A.
N.A.
H.A.
M(1)
Q 1,2,3 1,2,3 N.A.
H.A.
1 2
3 H.A.
H. A.
N.A.
H.A.
1 2
3 1
2 3
N.A.
1,2,3 6.
a.
Steam Generator Water S
Level--High-High b.'utomatic Actuation N.A.
Logic and Actuation Relay AUXILIARYFEEDWATER a.
Manual N.A.
b.
Automatic Actuation H.A.
Logic and Actuation Relays c.
Steam Generator Water S
LevelLow-Low H.A.
N.A.
M H.A.
N.A.
H.A.
N.A.
H.A.
R N.A.
H. A.
H.A.
M(l)
M(l)
H.A.
1, 2
j.,
2 N.A.
M(l)
H.A.
H.A.
M(1)
Q 1, 2, 3
1, 2, 3
H.A.
1,2,3
INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMEHTATIOH LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumenta-tion channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY:
As shown in Table 3.3-3.
ACTION:
a.
With an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE RE UIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the HODES and at the frequencies-shown in Table 4.3-2.
4.3.2;1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.
The tota].iqterlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.2.1.3 The ENGINEEREO SAFETY FEATURES RESPOHSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times
~ 18 months where N is the total number of redundant channels in a specific ESFAS function as.shown in the "Total No. of Channels" Column of Table 3.3-3.
0.
C.
COOK-UNIT 1
3/4 3"15 Amendment No.
PVlÃT SYSTB5 STEW GKNP3ATOR STOP VRLYES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each steam generator s.op valve shall be OPEQBLE.
APPLICABILITY:
HOOES 1, 2 and 3.
ACTION:
tCOES 1 - Mfth one steam generator stop valve fnoperable, P%ER OP%ATION may continue provided the inoperable valve fs either restored to OP%ABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwfse, be fn HOT SHUTOOQl within the next 1Z hours.
NOES 2 - fifth one steam generator stop valve fnoperable, subsequent and 3
operatfon fn NODES 1, 2 or
'3 may procied after:
a.
The inoperable stop valve fs restored to OPERABLE
- status, or b.
The s
op va1ve is maintained. c1osed; otherwise, be fn HOT SHUTGOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURYEILLANCE REOU IRBlBiTS 4.7.1.5 Each steam generator stop valve >at fs open shall be demonstrated OPEMBLK by:
~a.
Part-strake exercising the valve at least once pe!
9Z days, and b.
Verffyfng fu11 closure withfn 5 seconds on any closure acmatfon signal while in HOT STANDBY wfth T i i41'0 durfng each reactor shutdown exceot that verB7catfon of full c1osure within 5 seconds need not be determined more often than once per 92 days.
O.C. CQOMJNIT l 3/4 7 10
HYORAOLlr.
p l5TOW ATE,A,M PISTON N EF P HOLE.
Q" PLugGED DRAIN MMO-2po(.wo p)
MMO-2lO(MO l.).
MAO-2~0(.¹ 5)
MMo-v<0(Ho~)
11 3
Ptl HPl
~r l-22l(ill 2)
'1P I-2 I I (N~ < l NPI-25l {4"-5)
NP I-24l (¹4)
NRV-22I (N'-2) I NRV-2l l (Mo I)
NRV-. 25I (No~}
I"RV-24l(N 4) 70 ATMOS NRV-ZZZ(N"-Z)
NRV-ZIZ(N-I)
NRV-232 (N<g)
H Rv-P.4Z (M<4-)
tAS156-i
'SI36-Q MS l36-4 MS IBQ-'p I'ONTI'NUOuS GRAIN 70 DRAiN POT
'SEE THIS QIIIlf; P(g~
~f
--.MPI-PZZ(Nag)
STEAM l ENF ROTOR pi,- I-zi p (N~ I)
'STOP VALV6 (S.CI)
VIP I- ~3Z. (hi=3)
MRv-2P.O
(. M~ P )
<Pi-2-.'Z(¹4)
MRV-~lO lV. l Mgy-230 ( No 5 )
., MPY-240 (.bio~)
)44 4T Leav
. <l(QMLY)
SKAG.TC.H "H-2'YplC.Al AggANl EMF.NT OF PlPINl.
AT 5TEAQ ~ENERATDR bebop ypLyp
-~O" ~. D.. I" ~.W.
XEL
t
>a }
I J
~ o AKCaJebm~
<earn vQA@4 S
<CH OCUL. TO L OCaLC. MV444Q
'X'b n.~
Q %
- 'LLO
%Ca ST~
u-"4W C4a
~ STCAM CMOBS.
mv-QO
~6.
C,i WCAAQ lC
~
vegulLl GXESLC,>56.
iNf05EhVL.lC, vAA.~
%XEAC.lbC UA H8N LtL
~F 'It%
~Sf-Xkl DVHtVA
-le
\\
'ass'I 4l sOl 104
<01 I
Qa He@-t2.L g ~L>Z.
Qs~ ~
- e.-
TABLE 4. 3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION-SYSTEM INSTRUMEHTATIOH HVEKU FUNCTIONAL UNIT 4.
STEAM LINE ISOLATION CHANNEL CHECK CHANNEL
. CALIBRATION CHANNEL MODES'H MHICH FUHCTIONAL SURYEILLAHCE TEST RE UIRED a.
Manual b.
Automatic Actuation Logic c.
Containment Pressure--
High-High d.
Steam Flow in Two Steam LinesHigh Coincident with T
Low-Low Pressure Low 5;
TURBINE TRIP AHD FEEDMATER ISOLATION a.
Steam Generator Mater LevelHigh-Hi gh N.A.
H.A.
H.A.
H.A.
.R R
M(1)
M(2}
. M(3) 1,2,3 1,2,3 1, 2, 3
1, 2, 3
1,2,3 6.
MOTOR DRIVEN AUXILIARYFEEDMATER PUMPS.
a.
Steam Generator Mater S
Level--Low-Low b.
4 kv Bus Loss of Yoltage 1, 2, 3
1, 2, 3
c.
Safety Injection d.
Loss of Main Feed Pumps H.A.
N.A.
H.A.
M(2}
1,2,3 1
2 3
INTRODUCTION NUREG-0737 TECHNICAL SPECIFICATIONS - GENERIC LETTER NO. 83-37 CONTAINMENT SUMP LEVEL (EQUIVALENT OF 83 37 nNARROW RANGE'i)
CONTAINMENT WATER LEVEL (EQUIVALENT OF 83-37 "WIDE RANGE")
5 35 X
3II H
s 2
iv 5I' pJ Z
C N
D xaptea<d~
S PPRIO'GEmbnl ~
A ryA'kies'8a v'p I
P'WR. SVPP I
I I
Hc.r; pa o
(.441-S~l )
J I
P~ R. su%
H>/LO RMRN I
<ra-aso oway Cll5 50AS P4A'EC.
t NCh )/0 (ucs-err )
I r rr
~br
/ r Q/
q /
CL Xr',r "r/
/
Q r X r SC. (if-a"
/'l/ir/'rurzZ< //
gi'/ err OVe4~AP gFr~Fde SOD/ gAD coco'rur&mZAy cdlrER cE'vSr 'aarcdrro>
r/'/ l~/
, ~r
/'//
r89-5" Ec s'8'9 - o "
~AD E,'Vd CPA'4 I C PL P~D EG MTPr C r4'L s&ZAgrju&s
+nPF /dgclldb3 SoR Ran~ s~~r g4xrWom
PROBLEMS INTERPRETATION OP CHANNEL CHECK 83-37 REQUIREMENT TO SHUTDOWN THE PLANT WITH CONTAINMENT SUMP LEVEL AND CONTAINMENT WATER LEVEL INOPERABLE.
C
~
'r V
CHANNEL CHECK 1.10 A CHANNEL CHECK SHALL BE THE QUALITATIVEASSESSMENT OF CHANNEL BEHAVIOR DURING OPERATION BY OBSERVATION.
THIS DETERMINATION SHALL INCLUDEg WHERE POSSIBLES COMPARISON OF THE CHANNEL INDICATION AND/OR STATUS WITH OTHER INDICATIONS AND/OR STATUS DERIVED FROM INDEPENDENT INSTRUMENT CHANNELS MEASURING THE SAME PARAMETER.
PROPOSED INTERPRETATION THE CONTAINMENT WATER LEVEL CHANNEL CHECK IS A VISUAL INSPECTION OF PARALLEL CHANNELS.
THE CONTAXNMENT WATER LEVEL CHANNELS SHOULD READ 0% 2 ACCEPTABLE INSTRUMENT DRIFT.
THE CONTAXNMENT SUMP LEVEL CHANNELS ARE ACCEPTABLE PROVIDED BOTH CHANNELS READ WITHIN AN ACCEPTABLE PRE-DETERMINED TOLERANCE BAND.
CONTAINMENT WATER LEVEL OR CONTAINMENT SUMP LEVEL INOPERABLE THE PROPOSED ACTION IS WITH ONE OF TWO INOPERABLE FOR LONGER THAN 30 DAYS NOTIFY THE NRC WITH TWO INOPERABLE NOTIFY THE NRC WITHIN ONE HOUR VERBAL NOTIFICATION jS SUFFICIENT UNLESS THE NRC REQUESTS FURTHER INFORMATION IN WRITING
JUSTIFICATION OF THE PROPOSED TECHNICAL SPECIFICATION FOR CONTAINMENT SUMP AND WATER LEVEL CONTAINMENT WATER LEVEL IS A BACKUP SYSTEM A WIDE VARIETY OF ZNTRUMENTATION IS AVAILABLETO DETERMINE LEAKAGE IN CONTAINMENT.
CHANCES OF LOSING TWO REDUNDANT INSTRUMENTS TOTALLY IS RELATIVELY SMALL.
THE MOST LZKELY SCENARZO ZS "TECHNICALLY INOPERABLE" BUT STILL FUNCTIONAL.
MINIMIZE PAPERWORK BURDEN AVOID UNNECESSARY SHUTDOWNS OF PLANT OR EMERGENCY TECHNICAL SPECIFICATION CHANGES REQUESTS.
PRIME INDICATION FOR OPERATOR ACTION IN LOCA ZS REFUELING WATER STORAGE TANK LEVEL.
REDUNDANT INSTRUMENTATION TO SUMP LEVEL INSTRUMENTATION HUMIDITY MONITORS SUMPPUMP RUN TIME CHARGING PUMP FLOW ECCS ACTUATION CONTAINMENT ATMOSPHERE PARTICULATE RADIOACTIVITY MONITORING CHANNELS CONTAINMENT ATMOSPHERE GASEOUS RADIOACTIVITY MONITORING CHANNELS
TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION 3 4 5.
6.
7.
Containment Pressure Reactor Coolant Outlet Temperature T
(Wide Range)
HOT Reactor Coolant Inlet Temperature T
(Wide Range)
Reactor Coolant Pressure - Wide Range Pressurizer Water Level Steam Line Pressure Steam Generator Water Level Narrow Range R
8.
RWST Water Level 9.
Boric Acid Tank Solution Level 10.
Auxiliary Feedwater Flow Rate 11.
Reactor Coolant System Subcooling Margin Monitor 12.
13.
PORV Position Indicator - Limit Switches PORV Block Valve Position Indicator Limit Switches M
'14.
Safety Valve Position Indicator Acoustic Monitor 15.
Containment Sump Level 16.
Containment Water Level
TABLE 3.3-11 POST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE 1.
Containment Pressure 2;
3.
4 ~
Reactor Coolant Outlet Temperature TH (Wide Range)
Reactor Coolant Inlet Temperature T
(Wide Range)
Reactor Coolant Pressure - Wide Range 5.
Pressurizer Water Level 6.
Steam Line Pressure 7.
Steam Generator Water Level - Narrow Range 8.
Refueling Water Storage Tank Water Level 9.,
Boric Acid Tank Solution Level 10.
Auxiliary Feedwater Flow Rate ll.
Reactor Coolant System Subcooling Margin Monitor 12.
PORV Position Indicator - Limit Switches***
13.
PORV Block Valve Position Indicator. Limit Syitches 14.
Safety Valve Position Indicator Acoustic Monitor 15.
Containment Sump Level 16.
Containment Water Lev'el 2/Steam Generator 1/Steam Generator 1/Steam Generator*
1/Valve 1/Valve 1/Valve Steam Generator Water Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument.
PRODAC 250 subcooling margin readout can be used as a substitute for the subcooling monitor instrument.
5 TO BE DEVELOPED FOLLOWING JANUARY 13, 1986 MEETING WITH THE NRC.
s
aZaCTm COOmST SY 314.4.6 RZAl~ COOLANT SYSTEM LEAFAGE LZMZTmC CeeXTZaS ZOa OPnuZZm 3.4.6.1 The follmrLag Reactor Coolant Syotea Ieakugo detactioa oysteng ahall bo OPKRhBLE:
a.
Oae of the coat~aent atmoophere particulate radioactivity sold.tormen@
channelo gRS-1301 or ERS-1401),
'b.
The cea~seat oemy lavol H.ow aaMtatiag
- syacma, aad c.
X1ther the coataismeat humidisy monitor or oao of the coaa~aat atmosphere Naleeee radioactivity monitoring channels
. gRS-1305 or ERS-1405)
~
~
~Z~ZLITY: EauES 1, 2, 3 and 4.
kCZZOM>
Qith only tvo of the above requirad Iealaago detectioa syatamo
- OHDUSLE, operation may continue for up to 30 daya provided grab aenplas of the containment atmosphere are obtained and analyxad at, least once per 24'oure
<<hea the recpCh ed gaseoes aad/or particulate radioactivity bonito~ 'channeli are inoperable; othemCse,.
be ia 't leaet EOT'TAÃ)BX within the ac@:t 6
hosea and in COAX SEJT!XSR eishia tho foll~Lag 30 houro.
4.4.6.1 The Ieakege detactioa ayateaa shall be demoaotratad OPE4LBLE by:
a.
Containment atmosphere particulase and gaoaoua (if be~
used) moaitoriz~
aye tea-perf ormaace of CHARKL
- CEECX, CHhMHXL CALI3l4LXZOH and QUANEL HECT XOHhL TEST at the fraquenciae specified in Table 4.3-3, b.
Consainmeat sump level flax monitoring syitaa-performaace of CKhHHEL ChLZZLCZQM at laaas once per 1S moathN, c.
Coata&uaens hoity monitor (if babas used) - per ozmance of QhLRHEL 'CALZ3RJLTTOH at least oace per 18 moasha.-
D ~
C ~
COOK UHZX'/44 14 Asendment No.
60
MEETING
SUMMARY
DISTRIBUTION I
Docket Fil.e~
NRC PDR L PDR NSIC PRC System PWR¹4 Reading File Project Manager D.
Wi in ton M. Duncan
- Attorney, OELD J. Partlow E. Jordan B. Grimes ACRS (10)
NRC Partici ants D. Wigginton J.
Shapaker K. S.
West J.
Hayes C. Tinkler S.
Brown OTHERS bcc:
Licensee 8 Service List
$ ~ t I" IT, l~~
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