ML20140E027
| ML20140E027 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/27/1986 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20140E004 | List: |
| References | |
| GL-84-13, NUDOCS 8602030165 | |
| Download: ML20140E027 (6) | |
Text
ARKANSAS NUCLEAR ONE - UNIT 2 PROPOSED TECHNICAL SPECIFICATION CHANGE REQUEST G602030165 060127 PDR ADOCK 05000360 PDR p
3 l
PLANT SYSTEMS 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)
LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers shall be OPERABLE.
The only snubbers excluded from this requirement 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.
APPLICABILITY:
MODES 1, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or more applicable 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 l
restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.8.f on the attached component, or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REOUIREMENTS 4.7.8 Each applicable snubber shall be demonstrated OPERABLE by performance l
of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
Snubbers are categorized as inaccessible or accessible during reactor operation, b.
Visual Inspections Visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period 0
18 months 25%
1 12 months i 25%
2 6 months i 25%
3, 4 124 days i 25%
5,6,7 62 days 25%
8 or more 31 days i 25%
The snubbers may be categorized into groups based on type and accessibility.
Each group may be inspected independently in accordance with the above schedule.
ARKANSAS - UNIT 2 3/4 7-22
i O
TABLE 3.7-4 SAFETY RELATED HYDRAULIC SNUBBERS (DELETED)
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ARKANSAS - UNIT 2 3/4 7-24 (NEXT PAGE 3/4 7-26)
1 em e
04 (DELETED)
ARKANSAS - UNIT 2 3/4 7-26 (NEXT PAGE 3/4 7-26a)
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TABLE 3.7-4a SAFETY RELATED MECHANICAL SHOCK SUPPRESSORS SNUBBERS (DELETED) 3 ARKANSAS - UNIT 2 3/4 7-26a (NEXT PAGE 3/4 7-27)
ADMINISTRATIVE CONTROLS f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications, i.
Records of Quality Assurance activities required by the QA Manual.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59.
k.
Records of meetings of the PSC and the SRC.
1.
Records of changes to the Core Protection Calculator System (CPCS)
SOFTWARE.
Changes to the CPCS SOFTWARE shall be made in accordance with methods approved by the NRC.
These records shall include the following:
1.
Purpose of change.
2.
Detailed description of change including algorithms, changes to the assembly listings, checksums and disk identification numbers.
3.
Summary of validation test results.
Records of Environmental Qualification which are covered under the m.
provisions of paragraph 6.12.
Records of the service lives of the seals of all hydraulic n.
snubbers required by Specification 3.7.8, including the date at l
which the service life commences and associated installation and maintenance records.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 ENVIRONMENTAL QUALIFICATION 6.12.1 By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of:
Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment",
December 1979.
Copies of these documents are attached to Order for Modification of License NPF-6 dated October 24, 1980.
ARKANSAS - UNIT 2 6-23
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