ML20236B119
| ML20236B119 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/10/1989 |
| From: | Reeves E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236B121 | List: |
| References | |
| NUDOCS 8903200355 | |
| Download: ML20236B119 (6) | |
Text
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UNITED STATES lj 4
8 NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 206S5 l
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i SYSTEM ENERGY RESOURCES, INC., et al.
DOCKET NO. 50-416 l
GRAND GULF NUCLEAR STATION, UNIT 1 i
AMEN 0 MENT TO FACILITY OPERATING LICENSE l
Amendment No. 56 License No. NPF-29
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The. Nuclear Regulatory Comissior. (the Commission) has' found that A.
The application for amendment by System Energy Resources, Inc.,
(the licensee), dated July 25, 1988, 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; 1
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 j
this amendment can be conducted without endangering the health and safety of tne public, and (ii) that such activities will be conducted
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in compilance with the Commission's regulations; D.-
The issuance of this amendment will not be inimical to the comun 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, i
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2.
Accordingly,. the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby
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amended to read as follows:
i (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised
' through Amendment No. 56, are hereby incorporated into this license.
System Energy Resources, Inc. shall operate.the facility in accordance with the Technical Specifications and the Environmental Protection' Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY. COMMISSION k
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Edward A. Reeves, Acting Director Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor. Regulation a
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 10,1989 0
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DATE :3/7 /89
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- 3/ 7 /89
- 3/Q/89 l
I 0FFICIAL RECORD COPY:
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ATTACHMENT TO LICENSE AMENDMENT NO. 56 FACILITY OPERA 11NG LICENSE N0. NPF-29 DOCKET NO. 50-416 i
Replace the following pages of the Appendix A" Technical Specifications with i
the attached pages.. The revised pages are identified by Amendment number and contain vertical lines indicating the ared of change.
Remove Insert 3/4 7-11 3/4 7-1) 3/4 7-14 3/4 7-14 B 3/4 7-3 B 3/4 7-3 i
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M Pl. ANT SYSTEMS
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SURVEILLANCE REQUIREMENTS (Continued) e.
Functional Tests During the first refueling shutdown and at 'least once per 18 months thereafter during shutdown, a representative Sample of snubbers shall be tested using one of the following sample plans for each type of snubber. The sample plan shall be selected prior to the test period and cannot be changed during the test period.
The NRC Regional Administrator shall be notified in writing of the sample plan selected prior to the test period or the sample plan used in the prior test period shall be implemented:
1)
At least 10% of the total of each type of snubber shall be functionally tested either in place or in a bench test.
For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.4.f, an additional 5%
of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have baan functionally tested; or 2)
A representative sample of each type of snubber shall be func-
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tionally tested in accordance with Figure 4.7.4-1.
"C" is the 3
total number of snubbers of a type found not meoting the accept-j ance requirements of Specification 4.7.4.f.
The cumulative num-
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ber of snubbers of a type tested is denoted by "N'.
At the end J
of each day's testing, the new values of "N" and "C" (previous j
' day's total plus current day's increments) shall be plotted on Figure 4.7.4-1.
If at any time the point plotted falls in tha l
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" Accept" region, testing of snubbers of that type may be termi-nated.
When the point plotted lies in the "Cantinue Testing" I
region, additional snubbers of that type shall be tested until i
the point falls in the " Accept" region or all the snubbers of that type have been tested.
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f GRAND GULF-UNIT 1 3/4 7-11 Amendment No. Ah, 56
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6 CONTINUE C
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O ACCEPT 1
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10 20 30 40 50 60 70 80.
90 100 N
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(SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST GRAND GULF-UNIT 1 3/4 7-14 AMENDMENT NO. 56
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. PLANT SYSTEMS BASES-3/4.7.4 SNUBBERS (Continued)
The acceptance criteria are to be used in the visual inspection to determine OPERABILITY of the snubbers.
For example, if a fluid port of 'a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.
To provide assurance of snubber functional reliability one of two-l functional testing methods is used with the stated acceptance criteria:
1.
Functionally test 10% of a type of snubber with an' additional 5%
tested ~for each functional testing failure, or 2.
Functionally test a sample size and determine sample acceptance using Figure 4.7.4-1.
Figure 4.7.4-1 was developed using SWald's Sequential Probability Ratio Plan" described in " Quality Control and Industrial Statistics" by Acheson J. Duncan and the Revision 2 draft (9/86) of the ANSI /ASME OM4 1
document (Examination and Performance Testing of Nuclear Power Plant Dynamic Restraints (Snubbers).
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and,.if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so. exempted l
shall be listed in the list of individual snubbers indicating the extent of the exemptions.
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and asso-ciated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view
- i of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
3/4.7.5 SEALED SOURCE CONTAMINATION The limitation on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from byproduct, source.
and special nuclear material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a j
source in that group.
Those sources which are frequently handled are required f
to be tested more often than those which are not.
Sealed sources which are i
continuously enclosed within a shielded mechanism, i.e., sealed sources within radiation monitoring or boron measuring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
GRAND GULF-UNIT 1 B 3/4 7-3 Amendment No. E, 56 h
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