ML20078D117
| ML20078D117 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/20/1995 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078D121 | List: |
| References | |
| NUDOCS 9501270278 | |
| Download: ML20078D117 (8) | |
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4 UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 3084 5 4001
'+9.....,o THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.68 License No. NPF-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by The Cleveland Electric Illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated September 19, 1994, 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.
The 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 (1) that the activities authorized by this amendment can be conducted without endangering the health and i
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 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 have been satisfied.
2.
Accord 5 gly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
9501270278 950120 4
PDR ADOCK 05000440 P
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- (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 68 are hereby incorporated into this license.
The Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license a:aendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COP 91ISSION 77
/
Jon B. Hopkins, Senior Project Nanager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
January 20, 1995 c
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ATTACHMENT TO LICENSE AMENDMENT NO. 68 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications'with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
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l Remove Insert 3/4 7-8 3/4 7-8 3/4 7-9 3/4 7-9 l
3/4 7-12a l
3/4 7-12b l
B 3/4 7-2 B 3/4_7-2 l
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PLANT SYSTEMS 3/4.7.4 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.4 All snubbers shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
OPERATIONAL CONDITIONS 4 and 5 for snubbers located on systems required OPERABLE in those OPERATIONAL CONDITIONS.
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (si to OPEWLE status and perform an engineering evaluation l
per Specification 4.P.4.g on the attached component or declare the attached I
system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.4 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of
-Specification 4.0.5.
a.
Insoection Tvoes As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer,. irrespective of capacity.
b.
Visual Inspections A visual inspection of all snubbers shall be performed according to the schedule determined by Table 4.7.4.1.
Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently. The visual inspection for each type of snubber shall be determined based on the criteria provided in Table 4.7.4-1 and the initial inspection interval utilizing this criteria shall be 18-months, beginning from the conclusion of the last visual inspection conducted during RF04.
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i PERRY - UNIT 1 3/4 7-8 Amendment No. 68 g
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PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) c.
Visual Inspection Acceptance Criteria Visual inspections shall verify that (1) there are no visible l
indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable; however, they may be reclassified acceptable for the purpose of establishing the next visual inspection interval, providing that:
1 the cause of the rejection is clearly established and remedied fo(r)that particular snubber and for other snubbers irrespective of type on that system that may be generically susceptible; and/or (2)dition the affected snubber is functionally tested in the as found con and determined OPERABLE per Specifications 4.7.4.f.
For those snubbers common to more than one system, the OPERABILITY of such snubbers shall be considered in assessing the surveillance schedule for each of the related systems.
d.
Transient Event Inspection An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially i
l damaging transients as determined from a review of operational data l
or a visual inspection of the systems, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for j
accessible systems and 6 months for inaccessible systems following 1
this determination.
In addition to satisfying the visual inspection 1
acceptance criteria, freedom-of-motion of mechanical snubbers shall l
be verified using at least one of the following: evaluation of in-p(la)ce snubber 1 manually induced snubber movement; or 2 piston setting; or (3) strokin(g)the mechanical snubber through its full range of travel.
PERRY - UNIT 1 3/4 7-9 Amendment No.68
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TABLE 4.7.4-1
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SNUBBER VISUAL INSPECTION INTERVAL l
NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval (Notes I and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 5 and 7) 1 0
0 1
80 0
0 2
100 0
1 4
150 0
3 8
I 200 2
5 13 300 5
12 25
^
400 8
18 36 l
500 12 24 48 l
l 750 20 40 78 l
1000 or greater 29 56 109 Note 1:
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection ititerval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly. However, PNPP must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use the next lower integer for the value of the limit for Columns A,le, snubbers as determined l
B or C if that integer includes a fractional value of unacceptab by interpolation.
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l PERRY - UNIT 1 3/4 7-12a Amendment No. 68 l
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TABLE 4.7.4-1 (continued)
Note 3:
If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the l
previous interval but not greater than 48 months.
Note 4:
If the number of unacceptable snubbers is e ual to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
Note 5:
If the number of unacceptable snubbers is equal to or greater than the number in Column C, interval.the next inspection interval shall be two-i thirds of the previous However, if the number of unacceptable snubbers is less than the number in Column C but the next interval shall be greater than the number in Column B, ion; that is, the j
reduced proportionally b interpolat revious interval shall be reduce by a factor that is one-thir of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the snubbers in Columns B and C.
j Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
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PERRY - UNIT 1 3/4 7-12b Amendment No.68 l
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PLANT SYSTEMS BASES 3/4.7.4 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained l
during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
l Snubbers are classified and grouped by design and manufacturer but not by-size.
For example, mechanical snubbers utilizing the same design features of the 2-kip, 10-kip, and 100-kip capacity manufactured by Compan "A" are of the same type. The same design mechanical snubbers manufactured b Company "B" for the pur oses of this Technical Specification would be of a dif erent type, as would h draulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part.50. The accessibility of each snubber shall be determined and approved by the Plant Operations Review Committee. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e g., temperature, atmosphere, location, ion or), deletion of any snubber shall be etc.
'and the recommendations of Re ulatory Guide 8.8 and 8.10.
The addit ma e in accordance with Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to each safety-related system. Therefore, the required inspection interval is determined by the number of inoperable snubbers found during an inspection of each system, inspection interval.the total population or category siz each snubber type, and the previous In order to establish the inspection frequency for each type of snubber on a safety-related system, it was assumed that the frequency of snubber failures and initiating events is constant with time and that the failure of any snubber on that system could cause the system to be unprotected and to result in failure during an assumed initiating event.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. Any inspection I
whose results required a shorter inspection interval will override the previous I
schedule.
The acceptance criteria are to be used in the visual inspection to determine OPERABILITY of the snubbers.
To provide assu:ance of snubber functional reliability one of three functional testing methods is used with the stated acceptance criteria:
PERRY - UNIT 1 B 3/4 7-2 Amendment No.68