ML19326B987
| ML19326B987 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/15/1977 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19326B982 | List: |
| References | |
| NUDOCS 8004180684 | |
| Download: ML19326B987 (5) | |
Text
_ - - _ _ _ _
/
%g UNITED STATES O
NUCLEAR REGULATORY COMMISSION f
WASHINGTON. D. C. 30e86
%....j ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE - UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated January 13, 1977, complies 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) 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
.l 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.
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. OPR-51 is hereby amended to read as follows:
s 004180 b b
~1 2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 20, are hereby incorporated in this license. The licensee shall operate the facility in accordance with the Technical i
Specifications.
3.
This license amendment is effective as of the date of its issuance.
F0 THE NUCLEAR REGULATORY COMMISSION 2
Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 15,1977 e
6 6
e
ATTACHMENT TO LICENSE AMENDMENT NO. 20 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace existing pages '76 and 77 of the Appendix A portion of the Technical Specifications with the attached revised pages bearing the same numbers.
The changed areas on the revised pages are identified by a marginal line.
- l i
4
'l 1
1 j
.s 4.2. REACTOR COOLANT SYSTEM SilRVE1 Lt.ANCE Applicability Applies to the surveillance of the reactor coolant system pressure b L.ida ry.
Objective To assure the continued integrity of the reactor coolant system pressure boundary.
Specification 4.2.1 Prior to initial unit operation, an ultrasonic test survey shall be made of reactor coolant system pressure boundary welds as required to establish preoperational integrity and baseline data for future inspections.
4.2.2 Post operational inspections of components shall be made in accordance with the methods and intervals indicated in IS-242 and IS-261 of Section XI of the AS)E Boiler and Pressure Vessel Code,1971, including 1372 Summer Addenda, except as follows:
S-261 Item Component Exception 1.4 Primary No::le to 1 RC inlet no::le to be inspe cted at Vessel Welds approximately 31/3 years of the inspection interval. All four RC inlet nozzles to be inspected at or near the end of the inspection inter-val. At approximately 6 2/.~ years of the inspection interval, both RC outlet nozzles will be inspected.
At approximately 31/3 years of the inspection interval, one core flood no:zle will be inspected and one core flood nozzle will be inspect.ed at or near the e.nd of the inspection interval.
3.3 Safe Ends on Not Applicable Heat Exchanger 4.1 Vessel Safe Not Applicable End Welds 4.2 Valve Pressure Not Applicable Retaining Bolting Larger than 2" 4.9
-Integrally Nelded Not Applicable Supports 6.1 Valve Body Welds Not Applicable 6.3 Valve to Safe Not Applicabic End Welds
' knendment No. 7, 20 -
76
s-IS-261 Itan Co.yonent Exception 6.h Dolting 2%
Not Applicable 6.6 Integrally w lded not ApplicaEle e
Valve Supports h.2 3 The structural integrity of the reactor coolantisyste= toundary shall be rsintained at the level required by the original accep-tance clandards throughout the life of the station. Any evidence, as n' result of the tests outlined in Table IS-261 of Section XI of the cela, that def ects have developed or grown, shall be in. c: t i gstel.
4.2.h To ci tre the structurnl integrity of the reactor internals thro.ch-c'.'t the l!Tc of the unit, the two sets or main internals tol.s (ec: r.ceting the core turrel to the core support. shield and to the Tc cr gri! cylin!c.r} shall remain in place and under tentior.. This vill te verific 1 ty vir.aal inspection to determine that the velded ini t.l oc k i t..; cnr re:-ai: in place. All lockinr. caps vill tc inspect-ed af ter Foi f.. net :onal te:,tir.g and whenever the internsls are removed f rc, *.hc vescri du.-Inc a refueling or maintenance shatdova.
The ec: a barrel to core support shield caps vill be inspected each re f uel i n r, r. hut ?.own.
4.2 5 Cuf ficient re:ccrdr of each inr.pection chn]l t e kept to allow comr.r.ritor, ned evnlaation of future inspections.
4.2.6 Conplete ru face and volumet.ric examination of the renctor coolant pump flywheels vill be cond cted coincident with refueling or maintenaner shutdowns such that within n 10 year period af ter start-up all four reactor coolant pump' flyvheels vill be examined.
h.2 7 Reactor vessel specimenn shall be removed and examined, to deter-mine changes in material properties, at specimen exposure (E>lNey) equivalent to 3, 9.5,16 and 22.5 Ef f ective Full Power Years (EFFT) of operation.
This withdraval schedule may be modified to coincide with thonc ref ueling outages or plant shutdowns, when the reactor head is removed, most closely approaching the withdrawal' schedule.
Resulto of 'these examinations shall be used to update Technical Specific.1 tion 3.1.2.
Specimcas not subj ected en destructive tenting af ter the first 0.93 EFPY of Cycle l iay be removed and stored during the remainder of Cycle 1, but shall be re-installed prior to Cycle 2.
Bases The surveillance pre.rne bus been developed to comply with Section XI of the ACKE Boiler and Prer.rure Vess';l Code Inservice Inspection of Nuclear Reactor Coolant Systemc,19~2, including 1972 Summer Addenda cdition.
The number of renetor vennel arecimens and the frequencies for removing and tenting thene npecimenn are provided to nasure compliance with the
' requirements of Appendix 11 to 10 CFR Part 30.
Amendment No.12. 20
)
T1