ML18227C714
| ML18227C714 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/03/1976 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| L-76-192 | |
| Download: ML18227C714 (27) | |
Text
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I'r. IJI I NRC DISTRIBUTION rorl, PABT 50 DOCI(I=T MATI:-f)IAL 5 -250 251 FILE NUMOEA TO: (~
V. 'SSel l o FIIOMI ol la power 1 g o.
Miami, FloTdia R.E. Uhrig DATE Of'OCUMENT DATE AECEIVEO 5-QLETTEA
'onicINnL U COPY PNOTOAIZEO QUNC LASSIFIE O, PROP INPUT FOAM NUMBER OF COPIES AECEIVEO 43 oEscnfpTIoN Ltr. trans the following.......
ENCLOSURE I
Proposed.Amdt. to Facility OL/Change to Tech.
Spec.
to Amid Appedix A, Coneer'ning the limit-"
ing conditions for operation applicabikh to the Emergency Containment Filtering System during powei operation.....Notarized',5-3-76.
- (3 Sigead 8 40 CC
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Received)
PLANT NAME:
Turkey PT.
IfI 3 8
4 SAFETY ASSIGNED AD:
FOR ACTION/INF0 R ibIATION ASSXGiPi;D AD EHVXRO RANCH CHXHF:
PROJECT hlANAGER; CD ASST'ar BRANCH O'.IXEF PROJECT 1IANAGER LIC~ ASST L
RC PDR
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.2 LD GOSSXCK & STAFF QggE QNAUE F~
PROJECT MANAGEMENT BOYD P.
COLT.XHS HOUSTON PHTERSOI'I MI.'LTZ IIELTI;IIES SKOVHOLT TPDI
'XC HSING ASI,B I
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INTERNALD EN NF.ER I'I CA KNIGIIT SXII"IEXL PANLXCKX REACTOR SAFETY ROSS NOVAK ROS7TOC7Y CHECK AT&I SAL'f/lIAN R UT131',l<G EX'I Lfl(NALDISTR IDUTION NATl. LAB 1<I'.G. V"XI
I A PDR C()NS 0 fiTAN'fS ISTRI BUTION BENAROYiX QDI+
XPPOLXTO OPERATItifG REACTORS STELLO OPERATING TECH
.ISENIIUT HAO SCHUI'.NCl'.R ItXIII;S STTI: SAFETY & ENVIR h tIAI.YSIS TON & MUIiT.EIt 131(OOI:IIAVI'.N NATI. 1&13 UI.RIKSON(Oi,NI.)
HIKR(LZZ ERtiST BALT.ARD SPANGLER SXTE TECH GA>u~IXLL STEPP HULlIAN SITE ANAIXSIS VOI.LhIER BUi'ICII COLLXNS KREGER CONTROL NUMIIEI3 5104
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FLORIDA POWER El LIGHT COMPANY May 3, 1976 L-76-192 Director of Nuclear Reactor Regulation Attention: Mr.'ictor Stello, Jr., Dire Division of Operating React U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Stello:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 Proposed Amendment. to Facility 0 crating Licenses DPR-31 and DPR-41 "1'eC Ql@p@
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In accordance with 10 CFR 50.30, Florida Power and Light Company submits herewith three (3) signed originals and forty (40) conformed copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41.
As requested by your staff, we have revised the Turkey Point Technical Specifications to conform as near as is practical to the Standard Technical Specifications without making any hardware changes.
The current proposal supersedes our proposal of January 30, 1975.
The proposed changes are as described below and as shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner.
Pages'ii and iii Table of Contents headings are revised to reflect the following changes.
Pa es 3.4-4 through 3.4-6 Specification 3.4.3.b is revised.
This specification concerns the limiting conditions for operation applicable to the Emergency Containment Filtering. System during power operation.
CO'ELPING BUILD FLORIDA
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Director of Nuclear Reactor Regulation Page Two May 3, 1976 Pa e 3.12-1 New specification 3.12 is added.
This specification concerns the limiting conditions for operation applicable to the Control Room Ventilation System and the Post Accident Contain-ment Vent System.
Pa es 4.7-1 throu h 4.7-3 The surveillance requirements of specifications 4.7.1 (Emergency Containment Filtering System) and 4.7.2 (Post Accident Containment Vent, System) are revised.
A new specification
- 4. 7. 3 (Control Room Ventilation System) is added.
A new section B3.12-1 is added to provide bases for new specification 3.12.
Pa e B4.7-1 The bases for specification 4.7 are revised to include mention of the Control Room Ventilation System.
The proposed amendment has been reviewed and the conclusion reached that it does not involve a significant hazards consideration, therefore, prenoticing pursuant to 10 CFR 2.105 should not be required.
Very truly, yours, Robert E. Uhrig Vice President REU/
Attachnemt cc: 'r. Norman C. Moseley Jack R.
Newman, Esquire
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'ZABLE OF CONTENTS (Continued)
Section Title 3..7 3.8 3.9
- 3. 10 3.11 3.12 Electrical Systems Steam and Power Conversion Systems Radioactive Materials Release Liquid Wastes Gaseous 4'astes Containerized Vastes Refueling Miscellaneous Radioactive Materials Air Treatment Systems Sources 3.7-1 3.8-1 3.9-1 3.9-1 3.9-2 3.9-3 3.10-1 3.11-1 3e12-1 4
4.1
- -'" 4~2' 4.3 4.4 4.5 4.6 4.7 4.8 4.9 4.10 4.11 4.12 4.13 SURVEILLANCE REQUIREtKNTS Operational Safety Review Reactor'ool'ant'System In'ervice Inspectii5n
"'eactor Coolant System Integrity Containment Tests Integrated Leakage Rate Test Post Operational Lo al Penetration Tests Report of Test Results Isolation Valves Residual Heat Removal System Tendon Surveillance End Anchorage Concrete Surveillance Liner Survci'lance Safety In)ection Emergency Containment Cooling Systems Emergency Containment Filter System, Post Accident Containment Vent System, and Control Room Ventilation System Emergency Power System Periodic Tests Main Steam Isolation Valves Auxiliary Feedwater System Reactivity Anomalies Environmental Radiation Survey Radioactive Materials Sources Surveillance
- 4. 1-1
- 4. 1-1
""" '"4;2-1 4.3-1 4.4-1 4.4-1 4.4-1 4.4-2 4.4-3 4.4-3 4'-4 4.4-6 4.4-7 4.5-1 4.6-1 4.7-1 4.8-1 4.9-1 4.10-1 4.11-1 4.12-1 4.13-1 5
5.1 5.2 5.3 5.4 DESIGN FEATURES Site Reactor Containment Fuel Storage 5.1-1 5.1-1 5.2-1 5.3-1 5.4-1 6
6.1 6.2 6.3 6.4 6.5 6.6 6.7 6.8 6,9 ADMINISTRATIVE CONTROLS Responsibility Organization Facility Staff Qualifications Training Review and Audit Reportable Occurrence Acti.on Safety Limit Violation Procedures Reporting Requirements
- 6. 1-1 6-1 6-1 6-5 6-5 6-5 6-14 6-14 6-14 6-16 5/3/76
Section r
6-10 6-11 6-12 6-13 B2.1 B2.2 B2. 3 B3.1 B3.2 B3.3 B3.4 B3.5 B3. 6 B3. 7 B3,8 B3.9 B3.10
\\i B3,11 B3. 12
'4.1 B4.2 B4.3 B4.4 B4.5 B4.6 B4.7
. TABLE OF,CONTENTS (Continued)
Title Record Retention Radiation Protection Program Respiratory Protection Program High Radiation Area
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Bases for Safety Limit, Reactor Core Bases for Safety Limit, Reactor Coolant System Pressure Bases for Limiting Safety System Settings, Protective Instrumerrtation Bases for Limiting Conditions for Operation, Reactor Coolant: System Bases for Limiting Conditions for. Operation, Con-trol Rod and Porkier Distribution Limits Bases for Limztirig Conditions 'fo'r Operat'ion,
. Containment
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Bases for Limiting Conditions for Operation, Engineered Safer:y Features Bases for Limiting Conditions for Operation, Instrumentation Bases for Limiting Conditions for Operation, Chemical and Volume Control Syste.
Bases for Limiting Condition for Operation, Electrical Systems Bases for Limiting Condit
.'".s for Operation, Steam and Power Conversior..'ystems Bases for Limiting Condit
.-::rs for Operation, Radioactive Haterials Rcl::r.:e Bases for Limiting Conditions for Operation, Refueling Raaes for Limiting Conditions for Operation, Yiiscellancous Radioactive Haterials Sources Bases for Limiting Conditions for Operation, Air Treatment Systems Bases for Oper:ational Safety Reviev Bases for Reactor Coolant System In Service Inspection Bases for Reactor Coolant System Integtity Bases for Containment Tests Bases for Safety Injection Tests Bases for Emergency Containment Cooling System Tests Bases for Emergency Containmcnt Filtering System, Post Accident: Containment Vcrrting System, and Control Room Ventilation System Tests
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6-29 6-29 6-33 B2. 1-1 B2.2-1 B2.3-1 B3.1-1 B3. 2-1 B3. 3-1 B3.4-1 B3.5-1 B3.6-1 B3.7-1 B3.8-1
,'B3.9-1 B3.10-1 B3. 11-1 B3.12-1 B4.1-1 B4.2-1 B4.3-1 B4.4-1 B4.5-1 B4.6-1 B4.7-1
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B4.8 B4.9
~B4. 10
'B4.:ll B4. 12 Bases Bases Bases Bases Bases for Emergency Por"er System Periodic Tests'or Hain Stcam Isolation Valve Tests for-Auxiliary Feedwater System Tests for Reactivity Anomalies for Environmental Radiation Survey'4.8-1 B4r.9-1 B4.10-1 B4,ll-l B4.12-1 5/3/76
l.
ONE emergency containment cooling unit may be out r
'f service for a per d of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Prior to initi-ating maintenance the other TWO units'shall be tested to=demonstrate operability.
2.
ONE containment spray pump may be out of service provided it is restored to operable status with-in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The remaining containment spray pump shall be tested to demonstrate operability before initiating maintenance on the inoperable pump.
-"--.:3; --Any.valve, in-.the system"may.be: inoperable pro-" '".-"-:."-.
C vided"repairs are completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
.Prior to initiating, repairs, all valves that provide the duplicate function shall be tested to demonstrate operability.
3.
EHERGENCY CONTAIRfENT FILTERING SYSTEN a.
The reactor shall not be made critical, except for low power physics tests unless:
1.
THREE emergency, containment filtering'nits h
'are operable.
2.
All-valves, interlocks and piping associated
'with'he above components and required for
'most-accident operation, are operable.
b.
During the power op'eration:
0 The three Emergency Containment :iltering Units shall be operable at all times or the reactor shall C
be shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with the following exception:
If one of the three emergency containment filtering circuits is made or found to be inoperable for any reason, reactor operation is permissable only 3.4-4 5/3 76
during the'succeed seven days provided that all active components of the other two circuits
~ shall be demonstrated to be operable within two hours and daily thereafter.
2.
Any valve in the system may be inoperable provided repairs are completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except as stated in 3.b.l above.
Prior to initiating maintenance, all valves that provide the duplicate function shall be tested to demonstrate operability.
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COMPONENT COOLING SYSTEM a.
The reactor shall not be made critical, except for 1ow power physics tests, unless the following conditions are met:
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THREE component cooling pumps are operable.
'2.
THREE component cooling heat exchangers are operable.
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.b.
3.
All valves, interlocks and piping associated with.the above components are operable.
During power operation, the requirements of 3.4.4a may be modified as stated below.
Xf the system is not restored to meet the
'.conditions of 3.4.4a within the time period specified, the reactor shall be placed in the hot shutdown condition. If the requirements of 3.4.4a are not satisfied within an ad-ditional 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.
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1.
ONE pump may be out'f service for 7 days.
2i ONE additional pump and ONE heat exchanger may be out of service for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
'I 3.4-5
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5.
INTAKE Cppr.ING WTER SYSTEM a.
The reactor shall not be de critical unl ss the following conditions are met:
THREE intake cooling water pumps and TVO headers are operable.
2.
All valves, interlocks and piping associated with the operation of these
- pumps, and required for post accident operation, are operable.
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. b.
During power operation, the requirements of
~v 3.4.5,a.,
- above, may be modified to allow any one of the following components to be inoperable provided the remaining systems are in continuous operation.
If the system is not restored to meet the requirements of 3,4.5.a.
within the time period specified, the reactor shall be placed in the hot shutdown condition, If the requirements of 3.4.5.a.
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.
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One of the two headers may be out of ser-vice for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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'2.
One intake cooling water pump may be out of service for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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3.4-6 5/3/76
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3.12
. AIR TREATMENT SYSTEMS Ventilation System and the Post Accident Containment Vent System.
that are necessary:
1.
To prevent airborne activity from entering the control room in the event of a maximum hypothetical accident and to remove airborne activity from y'
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2.
To reduce containment hydrogen concentration and to reduce containment pressure during post-accident conditions, and e"
a.
The Control Room Ventilation (Emergency Internal Cleanup)
System may be inoperable for a period nf up to seven days. If the, system cannot be made
'operable within seven days, both reactors shall be shutdown.
2.
POST ACCIDENT CONTAINMENT VEN1 SYSTEM a.
The Post Accident Containment Vent System
'may be inoperable for a period up to thirty days. If the system cannot be made operable 0
within 30 days, both reactors shall be shutdown.
1 3.12-1 5/3/76
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4.7 EMERGENCY CONTAINM FILTER SYSTEM, POST ACClDENT AI¹zfENT VENT SYSTEM AND CONTROL ROOM VENTILATION SYSTEM.
Post Accident Containment Vent System, the Control Room Ventilation System.
To verify that these systems and their components will be able to perform their design functions during normal operations.
In the event that painting, fire', or chemical release occurs such that the filters are exposed to the effluents of these
,.events,. the,system will..be tested to verify, its performance of design features~
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0 eratin Tests System tests shall be performed once per operating cycle.
The tests shall consist of pressure drop and flow measurements across all filters in the plenum.
Less than 6" of water pressure drop at design flow (+ 10%)
across the combined HEPA filters and charcoal adsorbers shall constitute acceptable performance.
Once per operating cycle, the Emergency Containment Filtering System shall be tested to demonstrate automatic initiation upon receipt of a safety injection signal.
The Emergency Containment Filtering System shall be operated monthly for at least 15 minutes to demonstrate operability.
- 4. 7-1 5/3/76
Performance Tests
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Once per operating cycle, in-place DOP and halogenated
'ydrocarbon tests on each Emergency Containment filter
.plenum shall be performed.
Removal of >99% DOP and
>99X-halogenated hydrocarbon shall constitute acceptable performance.
Once per operating cycle, a charcoal sur-veillance specimen from one of the emergency containment filters shall be analyzed for methyl iodide removal cap-ability.
The re'suits of the laboratory carbon sample analysis shall show >85% removal efficiency.
Failing this, the
'C charcoal shall be replaced with charcoal which meets 4S "or exceeds. original specifications.
4.7.2 POST ACCIDENT CONTAINMENT VENT SYSTEM l.
0 eratin Tests Operating tests shall be performed annually.
The tests shall consist 'of visual inspection of the system, operation of'all valves, and pressure drop and'air flow measurements.
Visual inspection shall include search for any foreign materials and gasket deterioration in the HEPA 'filters and charcoal adsorbers.
Less than 6" of water pressure'drop at 55 cfm flow shall constitute acceptable performance.
2.
Performance Tests 0
Performance tests shall be conducted annually.
Cold DOP and halogenated hydrocarbon tests shall be conducted on the HEPA filter and on the charcoal adsorber.
Removal of
. >99X DOP and
>99% halogenated hydrocarbon removal shall k
constitute acceptable performance.
The hydrogen concentration measurement instrument shall be calibrated with proper consideration for humidity.
4.7-2 5/3/76
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4'.3 CONTROL RO VENTILATION (EMERGENCY INTERN CLEANUP)
SYSTEM 1.
0 eratin Tests The Control Room Ventilation System shall be operated monthly for at least 15 minutes to demonstrate operability.
Auto initiation of the systems operations shall be checked annually.
Pressure drop measurements across the filter bank shall be made annually.
Less than 6" of water pressure drop at designed flow
'(+10%) across the combined HEPA filter and charcoal adsorbers shall constitute acceptable performance.
2.
Performance Tests lP, I
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Performance Tests shall be conducted annually.
Cold DOP and halogenated hydrocarbon tests shall be'onducted on the HEPA filter and charcoal adsorbers respectively.
Removal of >99%
DOP and
>99% halogenated hydrocarbon removal shall constitute
'cceptable performance.
A charcoal surveillance specimen fiom one of the charcoal adsorbers shall be removed and analyzed annually for methyl iodide removal capability.
The results of the laboratory carbon sample analysis shall show
>85% removal efficiency.. Failing thi<, the charcoal shall be replaced with charcoal'which meets or'exceeds original specifications.
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4,7-3 5/3/76
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B 3.12 BASES FOR LIMITING CONDITIONS FOR OPERATION, AIR TREATMENT SYSTEMS The Control Room Ventilation'(Emergency Internal Cleanup)
System is designed to partially filter the Control Room atmosphere for recirculation during Control Room isolation conditions. If the system is inoperable.,
there is no imm'ediate threat.to the Control Room and reactor operation may continue for a limited time while repairs are being made.
If the system cannot be repaired within seven days, both reactors are shutdown in accordance with 10 CFR 50.36(c).
The Post Accident Containment Vent System is designed to facilitate controlled venting of either containment 'through HEPA and charcoal 4S filters to waste gas tanks and to the.atmosphere following a loss of coolant accident.
If the system is inoperable, there is no significant threat caused by continued reactor operation because the system would only be used seven to ten days after an accident.
.Reactor operation may, therefore, continue for up to thirty days while repairs are being made. If the system cannot be repaired in that time, both reactors are shutdow'n in accordance with 10 CFR 50.36(c).
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B3. 12-1 S/3/76
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0 B 4.7 BASES FOR EMERGENCY CONTAINMENT FILTERING SYSTEM, POST ACCIDENT CONTAINMENT VENT SYSTEM, CONTROL ROOM VENTILATION SYSTEM.
System components are not subject to rapid deterioration, having lifet'.nes of many years',
even under continous flow conditions.
Visual inspection and operating tests provide assurance of system reliability and will insure early detection of conditions which could cause the system to fail or operate properly.
The performance tests prove conclusively
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that filters have been properly installed, that. no deterioration or damage has occurred, and that all components and subsystems operate
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The tests provide assurance that filter performance has not deteriorated below original specification values due to aging, contami-nation, or other effects.
B4.7-1 5/3/76
STATE OF FLORIDA
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COUNTY OF DADE
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Robert E. Uhrig, being first duly sworn,. deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that, the statements made in this said document are true and correct to the best. of his knowledge, information, and belief, and that he is authorized to execute the document on behalf, of said Licensee.
Robert E. Uhrig Subscribed and sworn to before me this day of l976 Ny commission expires:
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Notary Pubis.c, i and for the County of Dade, State of Florida HOTARY PUSLIC STA% OF FLORIDA AT LARCk NYtOMMISSION EXPIRES NOV. 30 1979 SONDED THRU CFNER4L INS. UNDERWRITER.
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