ML20198B512
| ML20198B512 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/06/1986 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20198B516 | List: |
| References | |
| GL-84-13, NUDOCS 8605220025 | |
| Download: ML20198B512 (11) | |
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UNITED STATES y'
p, NUCLEAR REGULATORY COMMISSION
-l WASHING TON, D. C. 20555
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY CPERATING LICENSE Amendment No. 72 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated January 24, 1986, ccmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
8605220025 360505 PDR ADOCK 05000368 P
. 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-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR TH. NUCLEAR REGUL TORY COMMISSION s
George. Knighton rector PWR Pr,oject Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: May 6, 1986 t
May 6, 1986 ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Remove Page Insert Page 3/4 7-22 3/4 7-22 3/4 7-24 3/4 7-24 3/4 7-26 3/4 7-26 3/4 7-26a 3/4 7-26a 6-23 6-23 e
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O ARKANSAS - UNIT 2 3/4 7-21 w
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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 demcostrated CPERABLE 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 l
of the same design and manufacturer, irrespective of capacity.
I Snubbers are categorized as inaccessible or accessible during reactor operation.
b.
Visual Inspections Visual inspections shall be performed in accordance with the following schedule:
1 No, Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period 0
18 months i 25%
1 12 months i 25%
2 6 months 25%
3, 4 124 days i 25%
5,6,7 62 days 25%
3 or more 31 days 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 AMENDMENT NO. 72 1
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PLANT SYSTEMS q
SURVEILLANCE REQUIREMENTS (Continued)
If any snubber selected for functional testing either fails to activate or fails-to move, i.e., frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be evaluated in a manner to ensure their OPERABILITY. This require-ment shall be independent of the requirements stated in Specifica-tion 4.7.8.d for snubbers not meeting the functional test acceptance criteria.
g.
Preservice Testing of Repatred, Replacement and New Snubbers Preservice operability testing shall be perfonned on repaired, replacement or new snubbers prior to installation. Testing may be at the manufacturer's facility. The testing shall verify the functional test acceptance criteria in 4.7.8.e.
In addition, a preservice inspection shall be perfonned on each repaired, replacement or new snubber and shall verify that:
('
1)
There are no visible signs of damage or impaired operability as a result of storage, handling or installation; 2)
The snubber load rating, location, orientation, position setting and configuration (attachments, extensions, etc.),
are in accordance with design; 3 )"
Adequate swing clearance is provided to allow snubber movement:
4)
If applicable, fluid is at the recommended level and fluid is not leaking from the snubber system; 5)
Structural connections such as pins, bearings, studs, fasteners and other connecting hardware such as lock nuts, tabs, wire, and cotter pins are installed correctly.
h.
Snubber Seal Replacement Program The seal service life of hydr:ulic snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The expected service life for the various seals, seal materials, and applications shall be determined and established based on engineering information and the seals shall be replaced so that the expected service life will not be exceeded during a period
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when the snubber is required to be OPERA 8LE. The seal replacements shall be documented and the documentation shall be retained in accordance with Specification 6.10.2.
ARKANSAS-UNIT 2 3/4 7-23b Amendment No.
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TABLE 3.7-4 SAFETY RELATED HYORAULIC SNU88ERS (DELETED) i f
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t AR W SAS - UNIT 2 3/4 7-24 (NEXT PAGE 3/4 7-26) i AMENDMENT NO. 72 l
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ARKANSAS - UNIT 2 3/4 7-26 (NEXT PAGE 3/4 7-26a)
AMENDMENT NO. 72 e
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TABLE 3.7-4a SAFETY RELATED MECHANICAL SHOCK SUPPRESSORS SNUBBERS (DELETED)
ARKANSAS - UNIT 2 3/4 7-26a (NEXT PAGE 3/4 7-27)
AMENDMENT NO. 72 '
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ADMINISTRATIVE CONTROLS f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current messers of the
' unit staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
1.
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.
m.
Records of Environmental Qualification which are covered under the provisions of paragraph 6.12.
n.
Records of the service lives of the seals of all hydraulic 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" (00R 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.
j ARKANSAS - UNIT 2 6-23 AMENDMENT NO. 72
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ADMINISTRATIVE CONTROLS 6.12.2 By no later than December 1,1980, complete and auditable records must be available and maintained at a central location which describe the environ-mental qualification method used for all safety-related electrical equipment' in sufficient detail to document the degree of compliance with the 00R Guide-lines or NUREG-0588.
Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
6.13 HIGH RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area (as defined in 20.202(t )(3) of 10 CFR 20) in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring the issuance of a radiation work permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a present in'tegrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledge-able of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation l
work permit.
6.13.2 The requirements of 6.13.1, above, shall also apply to each high r
radiation area in which the intensity of radiation is greater than 1000 l
mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized j
entry into such areas and access to these areas shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Health Physics Superintendent.
ARKANSAS - UNIT 2 624 Ofddf dd%dd Od%dWit 244 1980 l
Amendment No. y,gg *60
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