ML20134C962
| ML20134C962 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/04/1996 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134C964 | List: |
| References | |
| NUDOCS 9610110189 | |
| Download: ML20134C962 (13) | |
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UNITED STATES i
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NUCLEAR REGULATORY COMMISSION t
WA85tlNGTON, D.C. 20066-0001
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1 POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 234 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated March 27, 1996 as supplemented April 24, 1996 and August 15, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;
B.
TLa facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common j
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements i
have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
9610110189 961004 7
PDR ADOCK 05000333 P
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.234, are hereby incorporated in the a
license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION j
l S. Singh Bajwa, Acting Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes tc the Technical Specifications Date of Issuance:
October 4, 1996 i
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ATTACHMENT TO LICENSE AMENDMENT N0.234 I
FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:
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Remove Paaes Insert Paaes iv iv i
vi vi 30e 30e 4
30f 30f 166 166 167 167 194 194 198 258e 258e 4
i 285 285 i
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i JAFNPP TABLE OF CONTENTS (Cont'd) 6.16 Process Control Program (PCP) 258b 4
6.17 Offsite Dose Calculation Manual (ODCM) 258b 6.18 Major Modifications to Radioactive Liquid, Gaseous, and 258c Solid Waste Treatment Systems i
6.19 Postaccident Sampling Program 258e i
6.20 Primary Containment Leakage Rate Testing Program 258e I
i 7.0 References 285 1
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d Amendment No. 7, 22, 92,130, 234 iv a
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JAFNPP LIST OETABLES Table Iilla Eagg 1
4.2-8 Minimum Test and Calibration Frequency for Accident Monitoring 86 Instrumentation 4.6 1 Snubber Visual Inspection Interval 161 4.6 2 Minimum Test and Calibration Frequency for Drywell Continuous 162a Atmosphere Radioactivity Monitoring System
!l 4.7 1 (DELETED) 210
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4.7-2 (DELETED) 211 1
3.12-1 (DELETED) 244a 2
3.12 2 (DELETED) 244a 3.12-3 (DELETED) 244a i
j 4.12-1 (DELETED) 244a 1
4.12-2 (DELETED) 244a i
4.12-3 (DELETED) 244a i
6.2 1 Minimum FMft Manning Requirements 260a 6.10-1 Component Cyclic or Transient L' 261
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Amendment No. G4h-22, 92, ' ' 1,130,131,150,173,1 SO,181, 210, 210, 2%
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JAFNPP 4.0 BASES A.
This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are requirement will be identified as an exception. An example met and will be performed during the OPERATIONAL of an exception when the test interval is not specified in the CONDITIONS (modes) for which the Limiting Conditions for regulations is the Note in Specification 6.20. " Primary Operation are applicable. Provisions for additional Containment Leakage Rate Testing Program," which states
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surveillance ectivities to be performed without regard to the "The provisions of Specification 4.0.B do not apply to the applicable OPERATIONAL CONDITIONS (modes) are provided test frequencies specified in the Primary Containment in the individual SurveiNance Requirements.
Leakage Rate Testing Program." This exception is provided because the program already includes provisions for extension of intervals.
B.
Specification 4.0.B establishes the limit for which the specified time interval for Surveillance Requirements may be C.
extended. It permits an allowable extension of the normal This specification establishes the failure to perform a surveillance interval to facilitate surveillance scheduling and Surveillance Requirement within the aNowed survedlance i
consideration of plant operating conditions that may not be interval, defined by the provisions of Specification 4.0.B. as I
suitable for conducting the surveillance (e.g., transient a condition that constitutes a failure to meet the i
conditions or other ongoing surveillance or maintenance OPERABILITY requwements for a Limiting Condition for i
activities). It also provides flexibility to accommodate the Operation. Under the provissons of this specification, length of a fuel cycle for survediences that are performed at systems and components are assumed to be OPERABLE each refueling outage and are specified with a 24 month when Survedlance Requwements have been satisfactorily i
surveillance interval. It is not intended that this provision be performed within the specified time interval. However, used repeatedly as a convemence to extend surveillance nothing in this provision is to be construed as implying that intervals beyond that specified for surveillances that are not systems or components are OPERABLE when they are found performed during refueling outages. The limitation of this or known to be inoperable although stiN meeting the specification is based on engmeeting judgement and the Sur;f: G R==A..
.;s. This specification also clarifies recognition that the most probable result of any porticular that the ACTION requwements are apphcable when surveillanc being performed is the verification of Survedlence Requirements have not been completed within I
conformance with the Survedlance Requirements. The limit the ellowed surves#ence interval and that the time limits o[
on extension of the normal survedlance interval ensures that the ACTION requwsments apply from the point in time it is i
the relialslity confirmed by surveillance activities is not identified that a survedience has not been performed and not significantly reduced below that obtained from the,specified at the time that the allowed sur:2;7.c. was exceeded.
surveillance interval. The exceptions to Specification 4.0.B Completion of the Sur;T _.= R*"h.
.i within the i
are those surveillances for which the 25% extension of the alloweble outage time limits of the ACTION requwoments interval specified does not apply. These exceptions are restores compliance with the requwements of Specification
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stated in the indnnduel Technical Specifications. The 4.0.C. However, this does not negate the fact that the i
requirements of regulations take precedence over the fadure to have performed the survoeNence within the allowed Technical Specifications. Therefore, when a test interval is surveiMance mterva8, defined by the provisions of specified in the regulations, the test interval cannot be Specification 4.0.B, was a violation of the OPERABILITY extended under the provisions of 4.0.B. and the surveillance requwements of a Limiting Condition for Operation that is sublect to enforcement action. Further, the failure to
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Amendment No. 83 ? SS.198. 227, 30e t
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4.0 BASES - Continued j
C.
Coi.tinued C.
Continued perform a surveillance within the provisions of Specification Surveillance Requirements do not have to be performed on i
4.0.B is a violation of a Technical Specification requirement inoperable equipment because the ACTION requirements and is, therefore, a reportable event under the requirements define the remedial mesaures that apply. However, the of 10 CPR 50.731a)(21111(3) because it is a condition Surveillance Requirements have to be met to demonstrate i
l prohibited by the plant Technical Specifications.
that inoperable equipment has been restored to OPERABLE l
status.
If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is I
required to comply with ACTION requirements, a 24-hour D.
This specification establishes the requirement that all allowance is provided to permit a delay in implementing the applicable surveillances must be met before entry into an ACTION requirements. This provides an adequate time limit t
OPERATIONAL CONDITION or other condition of operation i
to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the specified in the Applicability statement. The purpose of this specification is to ensure that system and component
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completion of a surveillance before a shutdown is required to OPERABILITY requeroments or parameter limits are met L
comply with ACTION requirements or before other remedial before entry into an OPERATIONAL CONDITION or other I
measures would be required that may preclude completion of specified condition associated with plant shutdown as well i
a surveillance. The basis for this allowance includes as startup.
l consideradon for plant conditions, adequate planning, availability of personnel, the time required to perform the Under the provisions of this specification, the applicable surveillance and the safety significance of the delay in Surveillance Requirements must be performed within the completing the required surveillance. This provision also provides a time limit for the completion of Surveillance specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup i
Requirements that become applicable as a consequence of or following a plant outage.
OPERATIONAL CONDITION (mode) changes imposed by ACTION requirements and for completing Surveillance When a shutdown is required to comply with ACTION Requirements that are applicable when an exception to the requirements, the provisions of this specification do not requirements of Specification 4.0.C is allowed. If a surveillance is not completed within the 24-hour allowance, apply because this would delay placing the facility in a lower i
CONDITION of operation.
the time limits of the ACTION requirements are applicable at i
that time. When a surveillance is performed within the l
24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time the surveillance is terminated.
I Amendment No. 49. Si, SS,100,162,132, 227, 234 3nf
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JAFNPP 3.7 (cont'd) 4.7 (cont'dl (2)
During testing which adds heat to the suppression pool, the water temperature shall not exceed 10*F above the normal power operation limit specified in (1) above. In connection with such testing, the pool temperature must be reduced to below the normal power operation limit specified in (1) above within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(3)
The reactor shall be scrammed from any operating i
condition if the pool temperature reaches 1107.
t Power operation shall not be resumed until the pool temperature is reduced below the normal power operation limit specified in (1) above.
(4)
During reactor isolation conditions, the reactor pressure vessel shall be depressurized to less than 200 psig at normal cooldown rates if the pool t
temperature reaches 120T.
2' Primary containment integrity shall be maintained at all times 2.
a.
Perform required visuel examenetson and leakage rate when the reactor is critical or when the reactor water testing of the Pnmary Contamment in accordance temperature is above 212*F, and fuel is in the reactor with the Pnmery Contamment Leekage Rate Testing vessel, except whole performing low power physics tests at Program.
atmospheric pressure at power levels not to exceed 5 MWt.
b.
Demonstrate leakage rate through each MSIV is s 11.5 scfh when tested at a: 25 poig. The testing frequency is in accordance with the Primary l
Containment Lookage Rate Testmg Program.
l Once per 24 months, demonstrate the leakage rate of c.
10AOV-68A,8 for the Low Pressure Coolant injection system and 14AOV-13A,8 for the Core Spray system to be less then 11 scfm por valve when pneumatically tested at 2: 45 psig at eminent temperature, or less than 10 gpm per valve if hydrostatically tested at 2:
1000 psig at ambient temperature.
i Amendment No. 44, 234 166 J
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JAFNPP 4.7 BASES (cont'd) assumption of no holdup in the secondary containment.
3.
The MSIVs are tested at a pressure less than P, and resulting in a direct release of fission products from the 2 25 psig, with a leakage rate acceptance criteria of primary containment through the filters and stack to the s 11.5 scth per valve. This exemption was approved environs. Therefore, the spe6fied primary containment leak by the NRC in the ongmal Technical Specifications rate and filter efficiency are conservative and provide (Table 4.7-2).
additional margin between expected offsite doses and 10CFR100 guidelmes.
The Program as implemented meets the requirements of l
Option B of 10 CFR 50 Appendix J (16) and Regulatory The leakage rate testing program was originalty based on Guide 1.163 (13), with the exception stated in Specification NRC guidelines for development of leak rate testing and 6.20. This exception applies to valves currently installed in surveillance schedules for reactor containment vessels.
this configuration, and does not apply to new installations.
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Containment structural integrity is currently verified with This exception is consistent with TS Table 4.7-2, previously visual inspections and containment leak tightness is verified contained in the TS, which allows reverse direction testing of i
by the leakage rate surveillance testing described in the valves as an exception to the requirements of the draft JAFNPP Primary Containment Leakage Rate Testing Appendix J on the basis that pressurization direction was
- Program, not a requirement at the time of plant design.
i The following are the exemptions to 10 CFR 50 Appendix J.
l Option A, that have been approved by the NRC, and remain appiicable to Option B of 10 CFR 50, Appendix J:
l 1.
The Type C exceptions listed on Table 4.7-2, "Ex eption to Type C Test", as of the date of B.
Standbv Gas Treatment System and issuance of Amendment 194 (July 29,1993).
C.
Secondarv Contamment ~
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Vatves wtuch are sealed with fluid from a seal Initiating reactor bulkNng isolation and operation of the
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system, such as the liquid in the suppression Standby Gas Treatment System to maintain at least a 1/4 in.
t chamber are not required to be Type C tested. This of water vacuum withm the secondary containment provides
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exemption was approved by the NRC in the original an adequate test of the operation of the reactor Technical Specifications (SR 4.7.A.2.c(3)).
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JAFNPP 6.19 POSTACCfDENT SAMPLING PROGRAM A program shall be established, implemented, and maintained which will ensure the c
capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shallinclude the following:
A) Training of personnel, B) Procedures for sampling and analysis, C) Provisions for maintenance of sampling and analysis 6.20 PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the Primary 1
Containment as required by 10 CFR 50.54 (o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-F ed Containment Leak-Test Program", dated September 1995, as modifit,J by the exception that Type C testing of valves not isolable from the containment free air space may be accomplished by pressurization in the reverse direction provided that testing in this manner provides equivalent or more conservative results than testing in the a :cident direction, if potential atmospheric leakage paths (e.g., valve stem packing) are not subjected to test pressure, the portions of the valve not exposed to test pressure shall be subjected to leakage rate measurement during regularly scheduled Type A testing. A list of these valves, the leakage rate measurement method, and the acceptance criteria, shall be contained in the Program.
A.
The peak Primary Containment internal pressure for the design basis loss of coolant accident (P ), is 45 psig.
B.
The maximum allowable Primary Containment leakage rate (L,), at P., shall be
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1.5% of primary containment air weight per day.
C.
The leakage rate acceptance criteria are:
1.
Primary containment leakage rate acceptance criteria is i 1.0 L,.
During unit startup following testing in accordance with this program, t
the leakage rate acceptance criteria are i O.60 L, for the Type B and Type C tests and 10.75 L, for the Type A tests:
2.
Airlock testing acceptance criteria are:
a.
Overall airlock leakage rate is 10.05 L, when tested at A P,,
b.
For each door seal, leakage rate is i 120 scfd when tested at A P,.
3.
MSIV leakage rate acceptance criteria is i 11.5 scfh for each MSIV when tested at 125 psig.
D.
The provisions of Specification 4.0.B do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
E.
The provisions of Specification 4.0.C are applicable to the Primary Containment Leakage Rate Testing Program.
Amendment No. 440,234 258e
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7.0 REFERENCES
(1)
E. Janssen, " Multi-Rod Burnout at Low Pressure," ASME Paper (9)
C.H. Robbins, " Tests of a Full Scale 1/48 Segment of the 62-HT-26, August 1962.
Humbolt Bay Pressure Suppression Containment "
i GEAP-3596, November 17,1960.
(2)
K.M. Backer, " Burnout Conditions for Flow of Boiling Water in Vertical Rod Clusters," AE-74 (Stockholm, Sweden) May (10) "NuGear Safety Program Annual Progress Report for Period 1962.
Ending December 31,1966, Progress Report for Period Ending December 31,1966, ORNL 4071."
(3) FSArT Section 11.2.2.
l (11) Section 5.2 of the FSAR.
(4) FSAR Section 4.4.3.
v (12) TID 20583, " Leakage Characteristics of Steel Containment i
(5) 1.M. Jacobs, " Reliability of Engineered Safety Features as a Vessel and the Analysis of Leakage Rate Determinations."
Function of Testing Frequency," Nuclear Safety, Vol. 9, No. 4, July-August 1968, pp 310-312.
(13) Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program", dated September 1995.
(6) Deleted (14) Section 14.6 of the FSAR.
(7) 1.M. Jacobs and P.W. Mariott, APED Guidelines for i
Determining Safe Test intervals and Repair Times for (15) ASME Boiler and Pressure Vessel Code, Nuclear Vessels, Engineered Safeguards - April 1969.
Section Ill. Maxwnum allowable internal pressure is 62 psig.
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(8) Bodega Bay Preliminary Hazards Report, Appendix 1. Docket i
(16) 10 CFR Part 50, Appendix J, " Primary Reactor Containment 50-205, December 28,1962.
Leakage Testing for Water-Cooled Power Reactors, Option B -
l Performance Based Requirements", Effective Date October 26, 1995 l
(17) Deleted I
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Amendment No. 1"^.227 234 285
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