ML20137R768
| ML20137R768 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/21/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20137R774 | List: |
| References | |
| DPR-59-A-097 NUDOCS 8512060079 | |
| Download: ML20137R768 (7) | |
Text
_. _
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k UNITED STATES p
k NUCLEAR REGULATORY LOMMISSION g
j WASHINGTON, D. C. 20555 s,,,e*
l POWER AUT40RITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. OPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated May 2, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules end regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license l
amendment and paragraph 2.C(2) of Facility Operating Licen:e No.
DPR-59 is hereby amended to read as follows:
kDjao Oj K9 851121 P
050003 3 PD
l l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 97, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
4 3.
This license amendment is effective as of the date of its issuance.
F0k THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Re3ctors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 21, 1985 t
l
ATTACHMENT TO LICENSE AMENDMENT N0. 97 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 173 173a - added 174 194 O
9'
JAFNPP 4,7 (cont'd)
The third test of each set shall be conducted when the plant is shutdown for the 10-year plant inservice inspections.
Permissible periods for testing.
The performance of Type A tests shall be limited to periods when the plant facility is nonoperational and secured in the shutdown condition under the administrative control and in accordance with the plant safety procedures.
(2) Type B tests, (except tests for air-locks), shall be performed during each reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than 2 years.
(3) Type B tests of airlocks shall be conducted at an internal pressure of not less than 45 psig (Pa).
The overall leakage rate for the airlock shall be less than or equal to 268 SCFD (0.05 La).
Airlock tests shall be conducted:
a) Every six months.
b) Prior to restoration of contain-ment integrity, when maintenance has been performed on the airlock
.which could affect its sealing capability.
E Amendment No.
97 173 i
k
JAFNPP 4.7 (cont'd) c) Within three days of opening the airlock, when containment integrity is required and maintenance has been performed on the airlock which could affect its sealing capability.
(4) Airlock seals shall be tested at a pressure not less taan 45 psig.
The seal leakage rate shall be less than or equal to 120 SCFD.
Airlock seal tests shall be con-ducted:
a) Prior to restoration of contain-ment integrity *. If maintenance which could affect sealing capa-bility was performed the entire airlock shall be tested as required by 4.7. A.2.e (3).
b) Within three days after opening the airlock, when containment integrity is required.
c) Once every three days, during periods of frequent openings when containment integrity is re-quired.
t Amendrent No.
97 173a
- Exemption to 10 CFR 50, Appendix J l
JAFNPP 3
4.7 (cont'd) i i'
(5) Type C test.
Type C tests shall be performed during each reactor shutdown for refueling but in no case at intervals greater than two years.
(6) Other leak rate tests specified in l
Section 4.7d shall be performed during each reactor shutdown for refueling but in no case at intervals
' greater than two years.
f.
Containment modification Any major modification, replacement of a component which is part of the primary reactor containment boundary, or resealing a seal-welded door, performed 4
after the preoperational leakage rate test shall be followed by either a Type A, Type B, or Type C test, as applicable, for the area affected by the modification.
The measured leakage i
from this test shall be included in the i
test report.
The acceptance criteria as appropriate,'shall be met.
Plinor mo'difications, replacements, or re-t l
sealing on seal-sal.ded doors, performed directly prior to the conduct of a j
scheduled Type A test do not require a separate test.
l s
i i
i Amendment No.
97 174.
JAFNPP 4.7 BASES (cont'd) assumption of no holdup in the As most leakage and deterioration of j
secondary containment, resulting in integrity is expected to occur a direct release of fission products through penetrations, especially
{
from the primary containment through those with resilient seals, a the filters and stack to the periodic leak rate test prooram of j
environs.
Therciore, the specified such penetrations is conducted at j
primary containment leak rate and the peak pressure of 45 psig to filter efficiency are conservative insure no-only that the leakage and provide additional margin remains acceptably low but also that i
between expected offsite doses and the sealing materials can withstand 10CPRIGO guidelines.
the accident pressure.
For airlock icak test, a seal test at the peak The maximum allowable test leak rate pressure could be substituted for the I
at the peak pressure of 45 psig (Pa) complete airlock test, if no mainte-is 0.5 weight percent por day (Lam).
nance work is done which could af fect The maximum allowable test leak rate the sealing' capability of the airlock.
3 at the reduced pressure of 23 psig a
(P ) will be verified to be The leak rate testing program was t
l conservative by actual primary originally based on AEC guidelines -
I containment leak rate measurements for development of leak rate testing i
at both 45 psig and 23 psig upon and surveillance schedules for completion of the containment reactor containment vessels, (16) structure.
and discussed in Question 5.4 of the FSAR.
With the exceptions listed in To allow a margin for possible Table 4.7-2, the system conforms leakage deterioration between to the latest AEC guidelines (17).
intervals, the maximum allowable The exceptions stated in l
leak rate (Ltm), which will be met Table 4.7-2 are necessary since j
to. remain on the normal test additional requirements were added schedule, is 0.75 Lt.
In addition, after the system was designed.
it is intended to operate the I
primary containment structure at a B.
Standby Gas Treatment System and slight positive pressure to C.
Secondary containment continuously monitor primary containment Icakage.
Initiating reactor building isolation and operation of the l
Standby Gas Treatment System to maintain at least a 1/4 in. of water vacuum within the secondary 1
containment provides an adequate-l test of the operation of the reactor Amendnent t ro.
97 194
,