ML20046C109
| ML20046C109 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/29/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20046C107 | List: |
| References | |
| NUDOCS 9308090209 | |
| Download: ML20046C109 (3) | |
Text
.
ps* ** cuq It A
i
)*
E UNITED STATES il NUCLEAR REGULATORY COMMISSION
\\j-
,/
W ASHINCTON, D.C. 2055MXX)1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.104 TO FACILITY OPERATING LICENSE N0. OPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET 60. 50-333
1.0 INTRODUCTION
By letter dated April 15, 1993, 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 pertain to Technical Specification Table 4.7-2, " Exception to Type C Tests,"
for select containment isolation valves.
Specifically, the changes would (1) add system numbers to the valve identification numbers for seven control rod drive (CRD) containment isolation valves and clarify the penetration arrangement, (2) remove valves 10MOV-57 and 10MOV-67 from the table, (3) add valves 10RHR-729A and 10RHR-729B to the table, and (4) correct errors introduced in Amendment No. 143.
2.0 EVALUATION Technical Specification Table 4.7-2 provides the containment isolation valves that are exempt from Type C local leak rate testing.
The licensee has proposed several changes to the table.
First, the licensee has proposed a change to the table to add system numbers to the valve identification numbers for seven control rod drive containment isolation valves to be consistent with valve identifiers elsewhere in the TSs.
In addition, the licensee has proposed a clarification to the penetration arrangements.
Specifically, the change clarified the fact that each penetration is actually a cluster of 31 to 38 lines for a total of 137 lines, one inlet and outlet pair for each CRD.
Further, each inlet line below a CRD piston has the four specified containment isolation valves while each corresponding outlet line above the CRD piston has the three specified containment isolation valves.
The NRC has reviewed the proposed changes and finds that they are all administrative in nature to enhance the information provided in the table. Therefore, the staff finds these changes acceptable.
Second, the licensee has proposed removing valves 10MOV-57 and 10MOV-67 from the table. The valves are located on the drain line leading to the radwaste system from the "A" side of the residual heat removal (RHR) system.
Removal of the valves from the table is based on a safety evaluation performed by the 9308090209 930729 PDR ADOCK 05000333 P
licensee that concluded the valves are not containment isolation valves, as defined by the current FitzPatrick licensing basis.
Specifically, the licensee determined that several normally closed manual valves located upstream of 10MOV-57 and 10M0V-67 provide boundary isolation. The staff has reviewed the Final Safety Analysis Report (FSAR), the TSs, and James A.
FitzPatrick Nuclear Power Plant Safety Evaluation JAF-SE-92-033, Revision 0, dated February 4, 1992. The FSAR indicated that valves on lines that penetrate the primary containment but do not communicate with the reactor vessel, with the primary containment free space, or with the environs require at least one containment isolation valve which shall be either automatic, or locked closed, or capable of remote manual operation.
Since manual isolation valve 10RHR-729A, located upstream of 10M0V-57 and 10MOV-67, is normally locked closed, it provides the isolation necessary to assure containment isolation. Therefore, 10MOV-57 and 10MOV-67 are not required for containment isolation, and the staff finds removal of the valves from the table to be acceptable.
Third, the licensee has proposed adding valves 10RHR-729A and 10RHR-729B to the table. The licensee determined that the normally closed manual valves form a part of the containment isolation boundary by isolating the branch lines out of penetrations X-225A and X-2258, respectively, leading to the RHR/Radwaste drain down lines. Since:
(1) the valves provide a containment isolation function as defined by the current FitzPatrick licensing basis, and (2) the valves are excepted from Type C testing as specified in Surveillance Requirement 4.7.A.2.c.(3), the staff finds adding the valves to the table to be acceptable.
Fourth, the licensee has proposed correcting errors introduced in Amendment No. 143.
Specifically, the licensee has proposed:
(1) removing the Type C surveillance requirements for valves 10M0V-34A and 10MOV-348, which were erroneously added to the table, and (2) adding a functional identifier for containment penetration X-221.
Since the discharge lines for valves 10MOV-34A and 10M0V-34B terminate below the low torus water level, the requirements for exception from Surveillance Requirement 4.7.A.2.c.(3) are satisfied, and removal of the Type C surveillance requirements is acceptable.
In addition, adding the functional identifier for containment penetration X-221 is an administrative change, which is also acceptable. The staff has reviewed the above changes and finds them acceptable.
In summary, the staff has reviewed the proposed changes to TS Table 4.7-2, and finds all changes to be acceptable.
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
-3_
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 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 (58 FR 32391). 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 CONCLUSIQH 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 defense and security or to the health and safety of the public.
Principal Contributor:
Kristine Shembarger Date: July 29, 1993
)
9 l
July 29, 1993 Dociet No. 50-333 Mr. Ralph E. Beedle Executive Vice President - Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Beedle:
SUBJECT:
ISSUANCE OF AMENDMENT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC N0. M86325)
The Commission has issued the enclosed Amendment No. 194 to Facility Operating License No. DPR-59 for the James' A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TS) in response to your application transmitted by letter dated April 15, 1993.
The amendment makes several changes to Table 4.7-2, " Exception to Type C Tests." Specifically, the changes (1) added system numbers to the valve identification numbers for seven control rod drive containment isolation valves and clarified the penetration arrangement, (2) removed valves 10M0V-57 and 10M0V-67 from the table, (3) added valves 10RHR-729A and 10RHR-729B to the table, and (4) corrected errors introduced in Amendment No. 143.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, Original signed by Maudette Griggs for:
John E. Menning, Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No.144 to DPR-59 2.
Safety Evaluation cc w/ enclosures:
See next page
- See previous concurrence PDI-1:PM NRR/SCSB OGC PDI-1:D PDI-1:LA PDI-1:PM.
CVogan cJ KShembarge N JMenning)4
- RBarrett
( b E C C' RACapra W f
" / /93 7 /L7/93 1/iG/93 l
7/ S /93
')/R /93 07/15/93 0FFICIAL RECORD COPY FILENAME: G:\\FITZ\\ FIT 86325.AMD