ML20205G506
| ML20205G506 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/26/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205B143 | List: |
| References | |
| TAC-56313, TAC-56314, NUDOCS 8810280274 | |
| Download: ML20205G506 (5) | |
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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REL ATED TO AMENDMENT N05,95 AND 99 TO FACILITY OPERATING LICENSE N05. OPR-24 AND GPR-27 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-266 AND 50-301
1.0 INTRODUCTION
By letter dated October 26, 1984 Wisconsin Electric Power Company submitted proposed amendments to the Point Beach Nuclear Plant Technical Specifications.
The proposed amendments revise Technical Specification 15.4.2.A and Table 15.4.2-1 to clarify that selection of one steam generator for inservice in-spection is acceptable, to allow utilization of state-of-the-art inspection techniques, and to reflect current reporting requirements for inspection results. The corresponding Technical Specification Bases are also revised.
The proposed amendments also revised Technical Specification 15.3.4.A.2.c.
by deleting a limiting condition for operation with respect to the auxiliary feedwater system.
This safety evaluation is a review of the requested changes and their inpact on the operation and administration of plant activities.
2.0 EJALVATION Proposed Change +o Technical Specification 15.4.2. A.2.(a)
Description of Change The criteria for the number of steam generators to be inspected have been revised to indicate that selection of onti steam generator is permissible rather than required.
Evaluation l
Existing Technical Specifications require one steam generator per unit to be inspected during each unit's prescribed inspection period. The proposed revision permits the inspection of either one or both steam generators of a given unit during a prescribed inspection period, thereby allowing an assessment of the conditions of both steam generators prior to the dis-covery of degradation in either steam generator.
If the option of inspec-ting both steam generators is selected, Table 15.4.2-1 of Techilical Specification 15.4.2 would allew for a reduction in the number of tubes inspected per steam generator by a factor of two; however, the total 8010200274 050726 DR ADOCK 050 6
2-number of tubes inspected would remain the same, thereby providing the same level of assurance that degraded conditions could be detected. This revision is consistent with existing requirements in Westinghouse Standard Technical Specifications (NUREG-0452) Revision 4.
This change is acceptable.
Proposed Chance to Technical Specification 15.4.2. A 3 The existing Technical Specification requires that the examination method be that prescribed in ASME Section XI Appendix IV. This is consistent with the requirements contained in the Westinghouse Standard Technical Specifications (NUREG-0452). The proposed revision would allow the use of alternate methods within the following prescribed bounds:
1.
Equipment, personnel, and procedure requirements must be consistent with the ASME.Section XI Appendix IV requirements.
2.
Certification and calibration requirements must be consistent with ASME Section XI Appendix IV requirements.
3.
Records must be consistent with ASME Section XI Appendix IV require-ments.
4 Reporting requirements remain unchanged.
5.
Flaw detection capability must be equivalent or superior to the methods prescribed in ASME Section XI Appendix IV.
10 CFR 50.55a(b)(2)(iii) states, "If the technical specifications of a nuclear power plant include surveillance requirements for steam generators different than those in Article IWB-2000 (of ASME Section XI), the inservice inspection program for steam generator tubing shall be governed by the requirements in the technical specifications."
I Based on the fact that any alternative techniques selected must be at least as sensitive to the presence of flaws as existing prescribed techniques, adeouate assurance is provided that equivalent degradation detection capability will exist. The requirements for equivalency in administrative, qualification, certification, calibration, and reporting requirements assures that the inspec-tion program controls will be equivalent to existing requirements. Thus, the proposed revision will not result in program degradation and will likely result in program enhancement.
As deviations from prescribed requirements are pennitted by 10 CFR 50.55a(b)(2)(iii),
this change is acceptable.
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Proposed Change to Technical Specification 15.4.2.A 7 Description of Change Reporting regof rements for steam generator inservice inspections have been evised to establish consistency with Westinghouse Standard Technical Spacifications(NUREG-0452).
Evaluation The proposed changes establish a greater degree of consistency between the Point Beach Technical Specificatf or.s and Westinghouse Standard Technical Specifications (NUREG-0452).
The result of this change will be more complete and timely reporting of the results of inspection results.
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This change is acceptable.
Proposed Change to Technical Specification 15.6.10 and Table 15.4.2-1 Description of Change The reporting requirements for ins >ection results falling into the category of "more than 10% of the total num>er of tubes examined are degraded, but none are defective" or "more than 1% of the sample is defective" have been updated to reflect tTe requirements of 10 CFR 50.73 Technical Specification 15.6.10 changes reportable occurrence (a)(2)(11).
records to reportable 6
events.
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Evaluation l
l These changes reflect the updated reporting requirements of 10 CFR 50.73(a)(2)(11) and are acceptable.
t Proposed Change to Bases i
The Basis of Technical Specification 15.4.2 is revised to reflect state-of-the-art l
steam generator tube inspection requirements consistent with program control requirements of ASME Section XI Appendix IV requirements, and to reflect the epplicability of ASME Section XI inspection requirements for safety class com-ponents other than steam generators, t
i Evaluation The change to the Basis of Technical Specification 15.4.2 is consistent with the proposed revisions to the specification.
J This change is acceptable.
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4 Proposed Change To TS 15.3.4.A.2.c.
Description of Chenoes I
J Specification 15.3.4.A.2.c which provides for the temporary closing of the
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motor driven auxiliary feedwater pump discharge valves during operations, has i
i been deleted.
Evaluation
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By letter dated July 6,1984, the licensee a tified the Comission of the com-pletion of a system modification to the auxiliary feedwater system which serves i
j to provide added assurance of automatic initiation of auxiliary fetdwater flow
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from the motor-driven auxiliary feedwater pumps without operator action. The iteensee's proposed modification submitted by letter dated June 20, 1983, was reviewed and approved by the Cnmission by letter dated September 15, 1983.
The modification concerned the auxiliary feidwater system motor-operated dis-
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charge valve operating logic and p ovides assurance that automatic initiation i
of auxiliary feedwater flow to an affected unit's steam generators will occur even if the motor-operated pump discharge valves are initially closed.
The Ifeensee, per their comitment in the July 6,1984, letter, he' Peluded g
the required surveillance and testing of the modified motor-operatef velve t
control logte in the appropriate Technical Specification on a monthly Fre-l 1
quency.
In addition, the Itcensee stated that valve function 61 testing is i
j performed per the requirements of Section XI of the ASME Code and that l
Engineered Safety features response testing of the valves is perfomed at l
each refueling to provide added assurance that the valve will perform its l
safety function in the event of an accideret.
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I Since the system modifications ensure that automatic initiation of auxiliary
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feedwater will occur even if the motor-operated valves are initially closed j
and the valve control logic is tested monthly, the provisions of Technical l
Specification 15.3.4.A.2.c are no longer necessary to pernit teeporary closing of the discharge valves, j
I The staff has concluded that this change is acceptable.
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l 5-ENVIRONMENTAL CONSIDERATION These amendments involve a change in the installation or use of a facility I
component located within the restricted area as defined in 10 CFR Part 20.
The staff has detemined that the arendments involve no significant increase in the amounts, and no significant change in the types, of any effluents i
that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation axposure. The Comission l
has previously published a proposed finding that te., ~e amendments involve no significant hazards consiceration and thera has been no public coment on such l
finding. Accordingly, those amendnents meet the eligibility criteria for cate-gorical exclusion set forth in 10 CFR 551.22(c)(9). The amendments also involve changes in recordkeeping, reporting or administrative procedures or requirements.
Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 151.t2(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
CO,NCLU510N We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be and(2)suchactivitieswill endangered by operation in the proposed manner g be conducted in compliance with the Comission s regulations, and the issuance of the amendments will not be inimical to the comen defenre and security or to the health and safety of the public.
Date: July 26, 1985 Principal Contributor:
P. L. Eng, Region !!!
B. L. Burgess, Region !!!
W. G. Guldemand, Reg. !!!
T. Colburn, DL l
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July 26, 1985 MEMORANDUM FOR:
Donna Noti.ingham Division of Licensing FROM:
Edward J. Butcher, Acting Chief Operating Reactors Branch v3, DL
SUBJECT:
REQUEST FOR PUBLICATION IN BI-WEEKLY FR NOTICE - NOTICE 0F ISSUANCE TO AMENDMENTS TO FACILITY OPERATINS LICENSES Wisconsin Electric Power Company, Docket Nos. 50-266 and 50-301, Point. Beach Nuclear Plant, Unit Nos. I and 2, Town of Two Creeks Manitowoc County, Wisconsin Date of application for amen 6nents:
October 26, 1984 Brief description of amendments: The amendments modified steam generator in service inspection requirements under Technical Specification 15.4.2.A, deleted a limiting condition for operation for the Auxiliary Feedwe'.or System and
,nodified reporting requirements to be consistent with 10 CFR 50.73.
Date of issuance:
July 26, 1985 20 days from the date of issuance Effective date:
Amendment Nos.:
90 and 99 Facility Operating License Nos. DPR-24 and DPR-27 Amendments revised the Technical Specifications.
l Date of initial notice in Federal Register:
February 27, 1985 (50 FR 7979 at 8011)
The Comission's related evaluation of the amendments is contained in a Safety Evaluation dated July 26, 1985.
1 No significant hazards consideration coments received: No.
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l i Local Public Document Room location: Joseph P. Mann Library, 1516 Sixteenth Street, Two Rivers, Wisconsin.
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i Edward J. Butcher, Acting Chief Operating Reactors Branch #3, DL t
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