L-76-192, 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes

05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes

ML18227D858
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: ML18227D858 (22)

Text

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Ltr. trans the following...'.... Proposed Amdt. to Facility OL/Change to Tech.

Spe'c. to Amehd Appedix A, Concerning the limit-ing'onditions for operation applicable to the Emergency Containment Filtering System during power operation.....Notarized 5-3'-76.

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~ A. 201S18y Alc>>f Socttcn Ilay 3, 1976 Doc4g C4ci L-76-192 Director of Nuclear Reactor Regulation Attention: Nr. Victor Stello, Jr., Director r I)(

Division of Operating Reactors Zg.

U. S. Nuclear Regulatory Commission ~~cc"~zg Washington, D. C. 20555 i+6

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Dear Mx. Stello:

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PcU ~i 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 Xn 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 rev'sed to reflect the following changes.

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Pa es 3.4-4 throu h 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.

HELPING 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. Uhrz.g Vice President REV/

Attachnemt cc: Mr. Norman C. Moseley Jack R. Newman, Esquire I

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TABLE OF, CONTENTS (Continued)

Settioe Title ~Pa e 3.7 Electrical 3.7-1 3.8 Systems'team and Power Conv"rsion Systems 3.8-1 3.9 Radioactive Haterials Release 3.9-1 Liquid Wastes 3.9-1

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Gaseous Wastes 3.9-2 Containerized Wastes 3 9-3

3. 10 Refueling 3.10-1 3.11 Hiscellaneous Radioactive Haterials Sources 3.11-1, 3.12 Air Treatment Systems 3.12-1 4 SURVEILLANCE REQUXREHENTS 4. 1-1 4.1 Operational Safety Review 4. 1-1 4.2 Reactor Coolant System In Service Inspection 4. 2-1 4.3 Reactor Coolant System Integrity 4. 3-1.

4.4 Containment Tests 4.4-1 Integrated Leakage Rate Test Post Operationa1. 4.4-1 Lo al Penetrat"on Tests 4.4-1 Report of Test Results 4.4-2 Isolation Valves 4.4.-3 Residual Heat Removal System 4.4-3 Tendon Surveillance 4,4-4 End Anchorage Concrete Surveillance 4.4-6 Linc" Su:ci'ance 4 4-7 4.5 Safety Injection 4.5-1 4.6 Emergency Containment Cooling Systems 4. 6-1 4.7 Emergency Containment Filter System, Post Accident 4. 7-1 Containment Vent System, and Control Room System 'entilation 4.8 Emergency Power System Periodic Tests 4.8-1 4.9 Hain Steam Isolation Va1ves 4.9-1 4.10 Auxiliary Feedwater System 4.10-1 4.11 Reactivity Anomalies 4.11-1 4.12 Environmental Radiation Survey 4.12-1 4.13 Radioactive Haterials Sources Surveillance 4.13-1 5 DESIGN FEATURES 5.1-1 5.1 Site 5.1-1 5.2 Reactor 5.2-1 5.3 Containment 5.3-1 5.4 Fuel Storage 5.4-1

6. ADHINISTRATXVE CONTROLS 6. 1-1 6.1 Responsibility 6-1 6.2 Organization 6-1 6.3 Facility Staff Qualifications 6-5 6.4 Training 6-5 6.5 Review and Audit 6-5 6.6 ~ Reportable Occurrence Action 6-14 6.7 Safety Limit Violation, 6-14 6.8 Procedures . 6-14 6.9 Reporting Requirements 6-16 5/3/76

TABLE 0F,COllTEHTS (Continued)

Section Title 6-10 Record Retention 6-27 6-11 Radiaeion )'rotcceion Program 6-29 6-12 Rcspiiatoxy Protection Program 6-29 6-13 )ligh Radiation Area 6-33 B2.1 Bases for Safety Limit, Reactor. Core B2. 1-1 B2.2 Base" for Safety Limit, Reactor Coolant System Pxesluxe B2. 2-1 B2. 3 Bases for Li aiting Safety System Scetings, Protective Instrumentation B2. 3-1 B3. 1 Bases for Limiting Conditions for Oper. tion, Reactor Coolant System B3. 1-1 B3.2 Bases for Limiting Conditions for Operation, Con-txol Rod and Power Distribution Limits B3.2-1 B3.3 Bases for Limiting Conditions for Operation,

'Containment B3.3-1 B3.4 Bases for Limiting Conditions for Operation, Engineered Safety Features B3.4-1 B3.5 Bases for Limiting Conditions for Operation, Instrumentation B3.5-1 B3.6 Bases for Limiting Conditions for Operation, Clieuiical and Volu=c Control Syste. B3.6-1 B3. 7 Bases for T.imit'ing Condition for Operation, Electrical Systems B3. 7-1 B3.8 Bases for Limiting Condit I.' f'r Operation, Steam and Power Conversiou'..'7seems B3. 8-1 B3.9 Bases for Limiting Condie '::Is for Operation, Radioactive Hatexials Reins.:e ..'3. 9-1 B3.10 Bases for Limiting Cond'itions for Operation, ....

Refueling B3. 10-1 Eases for Limiting Condieions for Operation,

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B3. 11 B3. 11-1 Viiscellancous Radioactive Haterials Sources ~ ~

B3. 12 Bases for Limiting Conditions for Operation, Air B3.12-1.

Treatment Systems B4.1 Bases for Operational Safety Review B4.1-1 B4.2 Bases for Reactor Coolant System In Service Inspection B4.2-1 B4.3 Bases for Reactor Coolant System Integtity B4.3-1 B4,4 Bases for Containment Tests B4,4-1 B4.5 Bases for Safety Injection Tests B4,5-1 B4.6 Bases for Emergency Containment Cooling System Tests B4.6-1 B4. 7 Bases for Emergency Containmcne Filtering/System, Post Accident Containment Venting System! and B4 ~ 7-1 Contxol Room Ventilation System Tests B4.8 Bases for Fmergcncy Power System Periodic Tests B4.8-1 B4.9 Bases for Hain Stean Isolation Valve Tests B4.9-1

~ B4. l0 Bases for Auxiliary Feedwater System Tests B4.10-1

'B4;.11 BaSCS for Reactivity Anomalies B4.11-1 B4I ~ 12 Bases for Environmental Radiation Survey 94.12-1 5/3/76

l. ONE emergency conta ent cooling unit may be out t 4 of service for a period of 24 hours. 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 hours. The remaining containment spray pump shall be tested to demonstrate operability before initiating maingenance on the inoperable pump e

3. -Any valve in the system may'be inoperable pro-

.vided repairs are completed within 24 hours.

.Prior to initiating repairs, all valves that provide the duplicate function shall be tested to demonstrate operability.

3. EMERGENCY CONTAINMENT FZLTERlNG SYSTEM

a. The reactor shall not be made critical,'xcept for low power physics tests unless:

1. THREE emergency containment filtering units are operable..

2. All valves, interlocks 'and piping associated with the above components and required for

'most-accident operat on, are operable.

b. During the power operation:

0 The three Emergency Containment -"iltering Units shall C

be operable at all times or the reactor shall 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:

Ef one of the three emergency containment filtering c'ircuits is made or found to be inoperable for any reason, reactor operation is permissable only 3.4-4

during l

the'succeed g 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 hours 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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4. 'COMPONENT COOLING SYSTEM I

8P The reactor shall not be made critical, except for, low power physics tests, unless the following conditions

.are met:

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K component cooling pumps are operable.

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2. THREE component'ooling heat exchangers are I

operable.

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3. All valves, interlocks and piping associated with .the above components are operable.

b. During. power operation,'he requirements .of 3.4.4a may be modified as stated below.

If the'system is not restored to meet the

.conditions of 3.4.4a within the time period

~ r 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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l. ONE pump may be out'f. service for 7 days.

2. 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 />.

3.4-5

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5. INTAKE'COOLING WATER SYSTEM a.. The reactor shall not be made critical unl.ss the following conditions are met:

. l. THREE intake cooling water pumps and TWO headers are operable.

2. All valves, interlocks and piping associated with the operation of these pumps, and required for post accident operation, are operable.

b. During power operation, the requirements of 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.

l. 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'ay 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

3. 12 AIR TREATMENT SYSTEMS Ventilation System and the Post Accident Containment" Vent System.

To define those limiting conditions for operation that're 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 the control room if detected,

2. To reduce containment hydrogen concentration and to reduce containment pressure during post-accident conditions, and 1~ CONTROL ROOM VENTILATION SYSTEM

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

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'operable within seven days, both reactors shall be shutdown.

2. POST ACCIDENT CONTAINMENT VEN'i 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 within 30 days, both reactors shall be shutdown.

3.12-1 5/3/76

4..7 EMERGENCY CONTAI FILTER SYSTEM, POST ACCIDENT NTAINMENT 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 ~stem will be tested to verify its performance of design features.

1. 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 Emexgency Containment Filtering System shall be operated monthly for at least 15 minutes to demonstrate operability.

4,7-1 5/3/76

Performance Tests Once J

per operating cycle, in-place t DOP and halogenated hydrocarbon tests on each Emergency Coritainment filter plenum shall be performed. Removal of >99% DOP and >99 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 results of the laboratory carbon sample analysis shall show >85% removal efficiency. Failing this, the charcoal shall be replaced with charcoal which meets or exceeds .original specifications.

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 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

>99% DOP and >99% halogenated hydrocarbon removal shall constitute acceptable performance.

The hydrogen concentration measurement instrument shall be calibrated with proper consideration'or humidity.

4.7-2 5/3/76

4.7.3 CONTROL RO VENTILATION (EHERGENCY INTERN CLEANUP) SYSTEM

l. 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'b'ank 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.

'. Performance Tests 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

acceptable performance.

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. C 0

4,7-3 5/3/76

B 3.12 BASES FOR LIMITING CONDITIONS FOR OPERATION, AIR TREATHENT SYSTEHS 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 immediate threat to the Control Room and reactor operation may

'U 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 filters to waste gas tanks and to the .atmosphere

~ r 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 e

made. If the system cannot be repaired in that time, both re'actors are shutdown in accordance with 10 CFR 50.36(c).

B3.12-1 5/3/76

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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 lifetimes of many years, even under continous flow conditions'isual 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 that filters have been properly installed, that no deterioration or damage has occurred, and that'a3;1 components and subsystems operate properly. 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 )

) ss.

COUNTY OF DADE )

Robert E. Uhrig,. being first duly sworn, deposes and says:

That he is a Vice President of Florida Power & Light Company, the Licensee her'ein; 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 M~ day of 1976 Notary Public, x and for the County o Dade, State of Florida hOTARY PUSUC STATF. OF FLORIDA AT tARCR Nf COhNISSIONEXPIKS HOV. 30 1979

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comIM.sszon expires. ~ lONDEO THRU CXNERAL INS. UNDERWRITERS

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