ML20113E174
| ML20113E174 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/28/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20113E170 | List: |
| References | |
| NUDOCS 9607050100 | |
| Download: ML20113E174 (5) | |
Text
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UNITED STATES j,
j NUCLEAR REGULATORY COMMISSION o
a WASHINGTON. D.C. 20565-0001 4 *****,o 9
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 231 TO FACILITY OPERATING LICENSF NO. OPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 1
1.0 INTRODUCTION
By letter dated April 24, 1996, the Power Authority of the State of New York (the licensee) submitted a request for changes to the James A. FitzPatrick Nuclear Power Plant Technical Specifications (TSs).
The requested changes would relocate Specification 3.11.8/4.11.8 " Crescent Area Ventilation" and associated Bases from the TS to the final safety analysis report (FSAR).
i The specific changes made to the TS by this amendment are as follows:
Paae ii. Table of contents Replace the following:
"B.
Crescent Area Ventilation B.
239" with "B.
DELETED" Paae 237. 3.11 Acolicability Replace the following:
" Applies to the operating status of the main control and relay rooms, battery room, and crescent area ventilation and cooling.
Applies to emergency service water system and intake deicing heaters."
with
" 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."
d 9607050100 960628 PDR ADOCK 05000333 p
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. Paae 237. 3.11 Ob.iective 4
Replace the following:
"To assure the availability of the main control 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 I
the conditions for which the capability is an essential response to plant abnormalities."
t with j
"To assure the availability of the main control and relay room, and battery room 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."
e Paae 237. 4.11 Aoolicability Replace the following:
" 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."
l with i
" Applies to the surveillance requirements for the main control and relay i
room, battery room ventilation systems, emergency service water and intake deicing heaters."
Paae 239. 3.11.B.
Replace the following:
)
i "B. Crescent Area Ventilation i
Crescent area ventilation and cooling equipment shall be operable on a continuous basis whenever specification 3.5.A, 3.5.B, and 3.5.C are required to be satisfied.
i 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, 3.5.8, 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 />."
)
4-4
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with "B.
DELETED"-
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Paae 239. 4.11.B.
~
Replace the following:
"B. Crescent Area Ventilation'
[
l.
Unit coolers serving ECCS components shall be demonstrated operable once/3 months.
2.
Each unit cooler's temperature ' control instrument shall be calibrated once/ operating cycle."
with 4
"B.
DELETED" l
Pace 243. 3.11.B. and 4.11.B.-Bases Replace the following:
"B. Crescent Area Ventilation I
1-Engineering analyses indicate that the temperature rise in safeguards compartments without adequate ventilation flow or cooling is such that continued operation of the safeguards equipment or associated auxiliary equipment cannot be assured."
4 with "B.
DELETED"
2.0 BACKGROUND
AND EVALUATION l
The purpose of this proposed change is to relocate Specification 3.11.8/4.11.B
" Crescent Area Ventilation" and associated Bases from the TS to the FSAR.
The definition of OPERABLE in FitzPatrick TS Section 1.0.J was revised with Amendment Number 83 to include the following requirements:
I "Onerable - A systen, subsysten, train, component or device shall be OPERABLE or'have OPERABILITY when it is capable of performing its specified function (s).
Impilcit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the systen,-subsysten, train, component or device to perform its function (s).
are also capable of performing their related support function (s)."
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_4 Section 182a of the Atomic Energy Act (the "Act") requires applicants for nuclear power plant operating licenses to state technical specifications (TS) to be included as part of the license. The Commission's regulatory requirements related to the content of technical specifications are set forth in 10 CFR 50.36. That regulation requires that the TS include items in five specific categories, including (1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls. However, the regulation does not specify the particular requirements to be included in a plant's TS.
The rule with respect to limiting conditions for operation identifies four criteria to be used in determining whether a particular matter is required to be included in the TS, as follows:
(1) Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; (2) a process variable, design feature, or operating restriction that is an initial condition of a Design Basis Accident or Transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; (3) a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a Design Basis Accident or Transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; (4) a structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety. As a result, existing limiting conditions for operation requirements which fall within or satisfy any of the criteria in 10 CFR 50.36 must be retained in the TS, while those TS requirements which do not fall within or satisfy these criteria may be relocated to othe,r, licensee-controlled documents.
The requirements of the existing TS for the Crescent Area Ventilation system provide a means to assure that safety-related equipment will operate properly during normal plant operation. This support system function is reflected in operability requirements associated with the TS limiting conditions for operation for the specific low-pressure coolant injection (LPCI), residual heat removal (RHR), high-pressure coolant injection (HPCI), and reactor core isolation cooling (RCIC) equipment that the ventilation system serves.
However, the Crescent Area Ventilation system is not associated with a process variable that constitutes an initial condition of a design basis accident or transient to support operation of the LPCI, RHR, HPCI, or RCIC equipment.
Therefore, the Crescent Area Ventilation system does not meet criterion 2 of 10 CFR 50.36.
The staff has also determined that the remainder of the four criteria do not apply to this system. The operation and surveillance of the Crescent Area Ventilation System will be sufficiently described in the FSAR that 10 CFR 50.59 will apply to future changes in these requirements.
Therefore, the requirements specified in these existing TS do not satisfy the criteria for TS, and future changes to the requirements for the Crescent Area Ventilation system can be adequately controlled under 10 CFR 50.59.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR i
Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a
. proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (61 FR 25710). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common i
defense and security or to the health and safety of the public.
l Principal Contributor:
Karen R. Cotton Date: June 28, 1996 l
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