ML20107M446

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Application for Amend to License DPR-59,relocating TS 3.11.B/4.11.B Crescent Area Ventilation & Associated Bases from TS to Controlled Procedure
ML20107M446
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/24/1996
From: William Cahill
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20107M438 List:
References
NUDOCS 9604300400
Download: ML20107M446 (13)
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Text

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BEFORE THE UNITED STATES )

l . NUCLEAR REGULATORY COMMISSION l

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In the matter of ) l l NEW YORK POWER AUTHORITY ) Docket No. 50-333 f James A. FitzPatrick Nuclear Power Plant )

A.PPLICATION FOR AMENDMENT TO OPERATING LICENSE 1

The New York Power Authority requests an amendment to the Technical Specifications l

(TS) contained in Appendix A to Facility Operating License DPR-59 for the James A. i FitzPatrick Nuclear Power Plant. This application is filed in accordance with Section 10  !

CFR 50.90 of the Nuclear Regulatory Commission's regulation. l l

l This application for an amendment to the James A. FitzPatrick TS relocates Specification

3.11.B/4.11.B " Crescent Area Ventilation" and associated Bases from the TS to an Authority controlled procedure. These requirements are implicit in the definition of OPERABLE in the FitzPatrick TS, and their relocation will not adversely affect Emergency j Core Cooling System (ECCS) or Reactor Core Isolation Cooling (RCIC) system operability. I This change, as with the existing TS, will not permit the ECCS and RCIC system to be considered operable without adequate area ventilation.  !

This proposed change is consistent with Standard Technical Specifications (STS) l (Reference 1), and NEDO-31466 (Reference 2). The FitzPatrick TS definition of OPERABLE provides the necessary controls, and appropriate actions should the area coolers become inoperable for any reason. The NRC approved similar changes for the Peach Bottom Atomic Power (Reference 3) and the Cooper Nuclear Stations (Reference 4).

The Authority requests approval of these proposed changes to the TS by June 30,1996 in anticipation of higher lake water temperatures which may occur during the Summer of 1996.

Attachments I and 11 to this application contain the proposed changes to the TS and the associated safety evaluation, respectively. A mark-up of the affected TS pages is included in Attachment lli. Commitments made by the Authority in this submittal are included in Attachment IV.

A copy of this application and the associated attachments are being provided to the designated New York State officialin accordance with 10 CFR 50.91.

New York Power Authority STATE OF NEW YORK COUNTY OF WESTCHESTER Subscrib thisMgd andday of Ato dbefore sworn f

me 1996.

William J. Cahill, Jr. [ Notary Public Chief Nuclear Officer GERALDINE STRAND Notary Public. State of New Wrk No. 4991272 i

Quellflodin Westchester com Commineion Empires Jan. 27,ISJJ 9604300400 960424 PDR ADOCK 05000333 i P PDR

Attachment I tn JPN-96-017 PROPOSED TECHNICAL SPECIFICATION CHANGES (JPTS-96-007)

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New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59

l l-l JAFNPP IAB.LE OF CONTENTS (Cont'd)

Eagst F. ECCS-Cold Condition F. 122 i G. Maintenance of Filled Discharge Pipe G. 122a I H. Avera e Planar Unear Heat Generation Rate H. 123 l APL R) 1.

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(Linear Heat Generation Rate (LHGR)-J.

Thermal Hydraulic Stability

1. 124 124a
SURVEILLANCE l l LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.6 Reactor Coolant System 4.6 136 A. Pressurization and Thermal Limits A. 136 B. DEL ETED C. Coolant Chemistry C. 139 D. Coolant Leakage D. 141 E. Safety and Safety / Relief Valves E. 142a

! F. Structural integrity F. 144

, G. Jet Pumps G. 144 L H. DELETED

l. Shock Suppressors (Snubbers) 1. 145b j l

l 3.7 Containment Systems 4.7 165 A. Prima Containment A. 165 B. Sta Gas Treatment System B. 181 l C. Secon a Containment C. 184 D. Primary ntainment isolation Valves D. 185

! 3.8 Miscellaneous Radioactive Material Sources 4.8 214 l 3.9 Auxiliary Electrical Systems 4.9 215 )

A. Normal and Reserve AC Power Systems A. 215 l l B. Emergency AC Power System B. 216- l l C. Diesel Fuel O. 218 I D. Diesel-Generator Operability F. 220 E. Station Batteries Ei. 221 F. LPCI MOV Independent Power Supplies F. 222a

, G. Reactor Protection System Electrical Protection G. 222c Assemblies l

I 3.10 Core Alterations 4.10 227 l A. Refueling Interlocks A. 227 l B. Core Monitoring B. 230

C. Spent Fuel Storage Pool Water Level C. 231 l D. Control Rod and Control Rod Drive Maintenance D. 231 l 3.11 Additional Safety Related Plant Capabilities 4.11 237 A. Main Control Room Ventilation A. 237 I B. DELETED l C. Battery Room Ventilation C. 239 Amendment No. 20, 43, 08,-44Br468, i ii

JAFNPP .

3.11 LIMITING CONDITIONS FOR OPERATION 4.11 SURVEILLANCE REQUIREMENTS _

3.11 ADDITIONAL SAFETY RELATED PLANT CAPABILITIES 4.11 ADDITIONAL SAFETY RELATED PLANT CAPABILITIES Acolicability: Apolicr.b;!ity:

Applies to the operating status of the main control and Appl:es to the surveillance requirements for the main l relay rooms, and battery room ventilation and cooling. control and relay room, battery room ventilation systems, l Applies to emergency service water system and intake emergency service water and intake deicing heaters.

deicing heaters.

Obiective:

Objective:

To verify the operability or availability under conditions To assure the availability of the main control and relay for which these capabilities are an essential response to l room, and battery room ventilation systems, to assure plant abnormalities.

the availability of the emergency service water system and intake deicing heaters, under the conditions for which the capability is an essential response to plant abnormalities.

A. Main Control Room Ventilation A. Main Control Room Ventilation

1. Each of the control room emergency ventilation
1. The reactor shall not have a coolant air supply fans and dampers shall be tested for temperature greater than 212 *F and fuel may operability every 3 months.

not be handled unless both of the control room emergency ventilation air supply fans and fresh The fresh air filter trains shall be tested once air filter trains are available for normal every 6 months as follows:

operation except that one emergency

a. Pressure drop test across each filter and the filter system.

Amendment No.

237

._.m . _ _ _ . . _ . _ . . . . _ . . _ _ _ _ _ . _ . - _ . _ _ _ _ . . . . _ _ _ . _ -

JAFNPP .

3.11 (cont'd) 4.11 (cont'd) .

I B. DELETED B. DELETED- 1 C. Battery Room Ventilation C. Batterv Room Ventilation Battery room ventilation shall be operable on a continuous Battery room ventilation equipment shall be demonstrated basis whenever specification 3.9.E is required to be satisfied. operable once/ week.

1. From and after the date that one of the battery room 1. When it is determined that one battery room ventilation-ventilation systems is made or found to be inoperable, its system is inoperable, the remaining ventilation system shall associated battery shall be considered to be inoperable be verified operable and daily thereafter.

for purposes of specification 3.9.E.

2. Temperature transmitters and differential pressure switches s.nall be calibrated once/ operating cycle.

Amendment No. 48,82,12S,134,'48,15S, 239

- - _ . __ - _ - _ _ ~ - - _ _ - - - - - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - - - _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ - - _ . . - _ _ -- -_ - -. _.. -,. , _____ - _ - _- ______. __________ - . -

JAFNPP .

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3.11 & 4.11 BASES A. Main Control Room Ventilation System B. DELETED l One main control room emergency ventilation air supply fan C. Batterv Room Vendlation provides adequate ventilation flow under accident conditions.

Should one emergency ventilation air supply fan and/or fresh Engineering analyse,s indicate that the temperature rise and air filter train be out of service during reactor operation, a hydrogen buildup in the battery, and battery charger repair time of 14 days is allowed because during that time, a ccmpartments without adequate ventilation is such that redundant 100% capacity train is required to be operable. continuous operation of equipment in these compartments cannot be assured.

The 3 month test interval for the main control room emergency ventilation air supply fan and dampers is sufficient D. Emeraencv Service Water System since two redundant trains are provided and neither is

.-.srmally in operation. The ESWS has two 100 percent cooling capacity pumps, each powered from a separate standby power supply. The ESW A pressure drop test across each filter and across the filter system supplies lake water to cool equipment required to system is a measure of filter system condition. DOP injection function following an accident. This equipment consists of:

measures particulate removal efficiency of the high efficiency emergency diesel generators, electric bay unit coolers, cable particulate filters. A Freon-112 test of charcoal filters is tunnet/ emergency switchgear room coolers, crescent area essentially a leakage test. Since the filters have charcoal of coolers, control room air handling units and relay room air known efficiency and holding capacity for elemental iodine handling units. Emergency service water is initially supplied to and/or methyl iodine, the test also gives an indication of the the control room chillers and chiller room air handling units relative efficiency of the installed system. Laboratory analysis unless ESW is manually realigned to supply the control room of a sample of the charcoal filters positively demonstrates and relay room air handling units. ESW will also supply water halogen removal efficiency. These tests are conducted in to the control rod drive pump coor which are not accordance with manufacturers' recommendations. automatically isolated following an t.ccident. The surveillance requirement compares pump performance with the pump curve The purpose of the emergency ventilation air supply system to determine pump operability. It also specifies testing at a capacity test is to assure that sufficient air is supplied to the main control room so that a slight positive pressure can be maintained, thereby minimizing in-leakage.

Amendment No. ' ' ', ' 20, 223, 243

Attachment !! to JPN-96-017 SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES (JPTS-96-007) l l

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l New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 l

DPR-59

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l Attachment 11 to JPN-96-017 SAFETY EVALUATION l Page 1 of 6 l

1. DESCRIPTION OF THE PROPOSED CHANGES i l - l I This section provides a description of the proposed changes to the Technical Specifications l (TS). Minor changes in format, such as type font, margins or hyphenation, are not l described in this submittal. This type of change is typographical in nature and does not , {

i affect the content of the TS. This proposed change relocates Specification 3.11.B/4.11.B l " Crescent Area Ventilation" and associated Bases from the TS to an Authority controlled )

i procedure. The specific changes are detailed below, ,

I Paae ii, Table of contents l l

l Replace the following:

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" B. Crescent Area Ventilation B. 239" i with

" B. DELETED" l

l Paae 237, 3.11 Acolicability i

Replace the following:

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" Applies to the operating status of the main control and relay rooms, battery room , and l crescent area ventilation and coolis g. Applies to emergency service water system and l intake deicing heaters."

with l- " Applies to the operating status of the main control and relay rooms, and battery room ventilation and cooling. Applies to emergency service water system and intake deicing heaters."

Paae 237, 3.11 Obiective Replace the following:

"To assure the availability of the main c'oi trol and relay room, battery room , and crescent -

area ventilation systems, to assure the availability of the emergency service water system and intake deicing heaters, under the conditions for which the capability is an essential response to plant abnormalities." i l

with

! "To assure the availability of the main control and relay room, and battery room ventilation j systems, to assure the availability of the emergency service water system and intake i deicing heaters, under the conditions for which the capability is an essential response to plant abnormalities."

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Attachment ll to JPN-96-017 i SAFETY EVALUATION Page 2 of 6 Paae 237,4. i1 ADolicability Replace the following:

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" Applies to the surveillance requirements for the main control and relay room, battery room, crescent area ventilation systems, emergency service water and intake deicing heaters."

with

" Applies to the surveillance requirements for the main control and relay room, battery room ventilation systems, emergency service water and intake deicing heaters."

Paae 239, 3.11.B.

l Replace the following:

" B. Crescent Area Ventilation i

Crescent area ventilation and coolin0 equipment shall be operable on a continuous ,

l basis whenever specification 3.5.A,3.5.B, and 3.5.C are required to be satisfied.

1. From and after the date that more than one unit cooler serving ECCS compartments in the same half of the crescent area are made or found to be inoperable, all ECCS components in that half of the crescent area shall be considered to be inoperable for purposes of specification 3.5.A,3.5.B, and 3.5.C.
2. If 3.11.B.1 cannot be met, the reactor shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />."

with i

" B. DELETED" l

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Attachment 11 to JPN-96-017 SAFETY EVALUATION l Page 3 of 6 1

l Paae 239, 4.11.B.

Replace the following:

" B. Crescent Area Ventilation i

1. Unit coolers serving ECCS components shall be demonstrated operable I once/3 months.  !
2. Each unit cooler's temperature control instrument shall be calibrated once/ operating cycle."

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" B. DELETED" Paae 243. 3.11.B. and 4.11.B. Bases Replace the following:

" B. Crescent Area Ventilation Engineering analyses indicate that the temperature rise in safeguards compartments without adequate ventilation flow or cooling is such that continued operation of the rafeguards equipment or associated aux;liary equipment cannot be assured."

with

" B. DELETED"

11. PURPOSE OF THE PROPOSED CHANGES The purpose of this proposed change is to relocate Specification 3.11.8/4.11.B " Crescent Area Ventilation" and associated Bases fron: the TS to an Authority controlled procedure.

Requirements for adequate Crescent Area Ventilation will remain effective because they are implicit in the definition of OPERABLE in the FitzPatrick TS.

The Authority requests approval of these proposed changes to the TS by June 30,1996 in anticipation of higher lake water temperatures which may occur during the Summer of 1996.

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Attachment il to JPN-96-017 SAFETY EVALUATION Page 4 of 6 Ill. SAFETY IMPLICATIONS OF THE PROPOSED CHANGES There are no safety implications associated with these changes because:

  • The Crescent Area Ventilation Specifications were included in the original version of the TS when FitzPatrick was licensed. Since that time, the definition of OPERABLE in FitzPatrick TS Section 1.0.J was revised with Amendment Number 83 (Reference
5) to include the following requirements:

l "Ocerable - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electricalpower sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the l l system, subsystem, train, component or device to perform its function (s) are also l l capable of performing their related support function (s). " 1 I '

i The Crescent Area Ventilation system supports ECCS and RCIC system operability.

As a result, the requirement for Crescent Area Ventilation to be operable for the ECCS and RCIC system to be considered operable is implicit in the definition of OPERABLE contained in TS Section 1.0.J, TS Sections 3.5.A " Core Spray System and Low Pressure Coolant injection (LPCI) Mode of the RHR System",3.5.B

" Containment Cooling Mode (of the RHR System)",3.5.C "High Pressure Coolant injection (HPCI System)", and 3.5.E " Reactor Core Isolation Cooling (RCIC)

System" .

  • Compliance with Crescent Area Ventilation system operability and surveillance l

requirements will be assured by maintaining them in an Authority controlled l procedure. The provisions of 10 CFR 50.59 will apply to changes made to the l Crescent Area Ventilation system to assure that any changes do not involve an l l unreviewed safety question. Crescent Area Ventilation operability and testing I requirements will continue to be an integral part of FitzPatrick plant operation.

Audits and surveillances will continue to be performed in accordance with Authority Quality Assurance Program requirements.

  • This proposed change is consistent with Standard Technical Specifications (STS)

(Reference 1), and NEDO-31466 (Reference 2). The FitzPatrick TS definition of OPERABLE provides the necessary controls, and appropriate actions should the area coolers become inoperable for any reason. The NRC approved similar changes for the Peach Bottom Atomic Power (Reference 3) and the Cooper Nuclear Stations (Reference 4).

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Attachment Il to JPN-96-017 l SAFETY EVALUATION  !

Page 5 of 6 l 1

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l IV. EVALUATION OF NO SIGNIFICANT HAZARDS CONSIDERATION l

Operation of the FitzPatrick plant in accordance with the proposed Amendment will not 1 involve a significant hazards consideration as defined in 10 CFR 50.92, based on the l following: l (1) These changes do not involve a significant increase in the probability or consequences of an accident previously evaluated because:

No modifications, no changes to operating procedura requirements, and no reduction in equipment reliability are being made as a result of these changes.

Operating limitations will continue to be imposed, and required surveillance will continue to be performed in accordance with regulations, and written procedures and instructions that are auditable by the NRC. Crescent Arch Ventilation operability and testing requirements will continue to be an integral part of FitzPatrick plant operation.

Although future changes to the Crescent Area Ventilation system will no longer be controlled by 10 CFR 50.90, proposed changes will be evaluated under 10 CFR 50.59 and plant procedures. Programmatic controls will continue to assure that Crescent Area Ventilation system changes will not adversely affect ECCS or RCIC  ;

system operability. As such, there is no significant increase in the probability or l consequences of an accident previously evaluated.

(2) These changes do not create the possibility of a new or different type of accident i previously evaluated because: 1 No modifications, no changes to operating procedure requirements, and no reduction in equipment reliability are being made as a result of these changes.

Compliance with Crescent Area Ventilation system operability and surveillance requirements will be assured by maintaining them in an Authority controlled procedure. Changes to the Crescent Area Ventilation system will be subject to the requirements of 10 CFR 50.59. Therefore, the proposed changes do not introduce any failure mechanism of a different type than those previously evaluated since there are no changes being made to the facility and do not create the possibility of a new or different type of accident previously evaluated.

(3) The proposed amendment does not involve a reduction in a margin of safety because:

The Crescent Area Ventilation system supports Core Spray, LPCI mode of RHR, l containment cooling mode of RHR, HPCI, and RCIC operability, and Crescent Area l Ventilation system inoperability does affect these systems. As a result, the j requirement for Crescent Area Ventilation to be operable for these systems to be considered operable is implicit in TS Sections 3.5.A,3.5 B,3.5,C,3.5 E, and the l definition of OPERABLE contained in TS Section 1.0.J. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

l Attachment 11 to JPN-96-017 SAFETY EVALUATION Page 6 of 6 l

V. IMPLEMENTATION OF THE PROPOSED CHANGEJ Implementation is administrative in nature and involves changes to plant procedures.

Authority controlled procedures will be updated to reflect relocation of Crescent Area Ventilation system Specifications and Bases.  ;

implementation of the proposed changes will not adversely affect the ALARA or Fire l

Protection Programs at the FitzPatrick plant, nor will the changes affect the environment. l l l VI. CONCLUSION

! Based on the discussion above, the Specifications and Bases for the Crescent Area Ventilation system can be removed from the FitzPatrick TS. The Plant Operating Review 1 Committee (PORC) and Safety Review rammittee (SRC) have reviewed these proposed changes to the TS and have concluden that they do not involve an Unreviewed Safety Question, or a Significant Hazards Crnsideration, and will not endanger the health and safety of the public.

l l Vll. REFERENCES l

1. NUREG-1433, " Standard Technical Specifications," General Electric Plants, BWR/4, I Revision 1, dated April 1995 l l l l 2. NEDO-31466, " Technical Specification Screening Criteria Application and Risk 1 Assessment," dated November 1987
3. NRC Letter to Mr. George A. Hunger, Jr., " Issuance of improved Technical l Specifications, Peach Bottom Atomic Power Station, Unit Nos. 2 and 3, (TAC NOS.

! M90746 and M90747)," dated August 30,1995 1

4. NRC Letter to Mr. Guy R. Horn, " Cooper Nuclear Station - Amendment NO.163 to I Facility Operating License NO. DPR-46 (TAC NO. M86319)," dated May 19,1993 i
5. NRC Letter to Mr. J. P. Bayne Transmitting TS Amendment Number 83, Regarding j use of the Term Operable as it Applies to Safety Systems in Power Reactors, dated  ;

August 28,1984 l l

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