ML20004A954
| ML20004A954 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/15/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W Arkansas Power & Light Co |
| Shared Package | |
| ML20004A955 | List: |
| References | |
| DPR-51-A-055 NUDOCS 8105270039 | |
| Download: ML20004A954 (7) | |
Text
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.....,{o, UNITED STATES eg j
NUCLEAR REGULATORY COMMISSION y f).:
WASMNGToN. D. C. 20655 May 15,1981 Docket No. 50-313 Mr. William Cavanaugh, III Vice President, Generation Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203
Dear Mr. Cavanaugh:
The Commission has issued the enclosed Acendment No.55 to Facility Operating License No. CPR-51 for Arkansas Nuclear One, Unit No.1.
This amendment consists of changes to the Technical Specifications (TSs) in response to your a:: plication dated April 2,1979, as supplemented October 31, 1980.
This amendment modifies the ANO-1 TSs to require the ANO-1 purge valves ce closed whenever the reactor ccolant system temperature is equal to or greater than 200*F. This amendment also updates pages i and 11 of the TS Table of Contents.
Copies of the Safety Evaluation and the Notice of Issuance are also enclosed.
In our letter of November 29, 1978, we identified the generic concerns of purging and venting of containments to all operating reactor licensees and requested your response to these concerns. Our review of your response was interrupted by the TMI accident and its demands on staff resources.
Consequently, as you know, an Interim Position on containment purging and l
venting was transmitted to you on October 26, 1979. You were requested to implement short-tern corrective actions to remain in effect pending completioq of our longer-term review of your response to our November 29, l
1973 letter.
Over the past several months our contractors and we have been reviewing the responses to our November 1978 letter to close out our long-term review of this rather complex issue. The components of this review are l
as follows:
1.
Confomance te Standard Review Plan Section 6.2.4 Revision 1 and l
Branch Tecnnical Position CSB 6-4 Revision 1.
These documents were provided as enclosures ta our November 1978 letter.
s 8105270 6 %
i Mr. William Cavanaugh 2.
Valve Operability Although the Interim Position allowed blocking of the valves at partial-open positions, this is indeed an interim position. Ear-lier we requested a program demonstrating operability of the valves in accordance with our " Guidelines for Demonstrative Operability of Purge and Vent Valves." These Guidelines were sent to you in our letter of September 27, 1979. There is an acceptable alternative which you may wish to consider in lieu of completing the valve qualification program for the large butterfly-type valves. This would be the installation of a fully-qualified mini-purge system with valves 8-inches or smaller to bypass the larger valves. Such a system change might prove more timely and more cost-effective. The system would meet BTP CSB 6-4 item B.1.c.
3.
Safety Actuation Stanal Override This involves the review of safety actuation signal circuits to ensure that overriding of one safety actuation signal does not also cause the bypass of any other safety actuation signal.
4 Containment Leakage Due to Seal Deterioration Position B.4 of the BTP CSB 6-4 requires that provisions be made to test the availability of the isolation function and the leakage rate of the isolation valves in the vent and purge lines, individually, during reactor operations. But CSB 6-4 does not explain when or how these tests are to be performed. After we complete the deveicoment of Standard Technical Specifications which will satisfy our position on this issue, we will forward them to you with a request for consideration of a submittal of proposed TS for A.iO-1.
The status of our long-term review of the above items for the ANO-1 facility is as follows:
1.
Conformance to Standard Review Plans Section 6.2.4 Revision 1 and Branen Technical Position CSB 6 4 Revision 1.
With the issuance of this amendment to your license, this issue is ccmplete for ANO-1. However, if you should decide to request a change in your TS which would allow some purging. Enclosure 4 is a rettatement of salient features of the position as interpreted by the staff. Evaluation of ANO-1 to this restatement and a comparison to BTP CSB 6-4 positions would be needed to reonen thi. review.
2.
Valve Ooerability With tne issuance of this amendment this issue is complete for ANO-1.
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It is our understanding that you do not intend to qualify the existing valves.
b
Mr. William Cavanaugh,
3.
Safety Actuation Signal Override This item is complete for ANO-1. Our letter dated August 14, 1980, provided our evaluation and acceptance of the electrical instru-mentation and control design aspects of the override of the containment purge valve isolation and other safety features actuation-signals.
Sincerely, (dohn F. Stolz, Chie-0py' rating Reactors Branch f4 Ofvision of Licensing
Enclosures:
1.
Amendment No. 55 DPR-51 2.
Safety Evaluation 3.
Notice 4.
Restatement of Staff Position cc w/ enclosures:
See next page l
A
Arkansas Power & Light Company cc w/ enclosure (s):
Mr. David C. Trimble cc w/ enclosure (s) & incoming dtd.:
Manager, Licensing 4/2/79,10/31/80 Arkansas Power & Light Company P. O. Box 551 Director, Bureau of Environmental Little Rock, Arkansas 72203 Health Services 4815 West Markham Street Mr. James P. O'Hanlon Little Rock, Arkansas 72201 General Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Mr. William Johnson U.S. Nuclear Regulatory Comission P. O. Box 2090 Russellville, Arkansas 72801 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Mr. Nicholas S. Reynolds Debevoise & Liberman 1200 17th Street, NU Washington, DC 20036 Arkansas Tech University Russellville, Arkansas 72801 Honorable Ermil Grant Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Director, Criteria and Standards Diviston Office of Radiation Programs (ANR-460)
U. 5. Environmental Protection Agency Washington, D. C.
20460 U. S. Environmental Protection Agency Region VI Office ATTN: E*S CCCRDINATCR 1201 Elm Street First International Building Dallas, Texas 75270 i
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%o, UNITED STATES y'
NUCt. EAR REGULATORY COMMisstCN
- lhi24rgg iY. E WASHINGTON, D. C. 20585 3~
s, v.....f ARKANSAS POWER & LIGHT COMPANY' COCKET NO. 50-313 ARKANSAS NUCLEAR ONE - UNIT NO.1 AMENCMENT TO L ACILITY OPERATING LICENSE Amendment No ~55 License No. OPR-51 1.
The Nuclear Regulatory Ccamissien (the Commission) has found that:
A.
The application for amendment by Arkansas Power and Light Company-(the licensee) dated April 2,1979, as supplemented October 31, 1980, ccmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulacions set forth in 10 CFR Chapter I; B.
The faciltty 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 (i) that the activities authori:ed by Siis amendment can be conducted without endangering the health and safety of the public, and (ii) that such a'ctivities will be conducted in compliance with the Commissien's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security er 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
2-2.
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. DPR-51 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.55, 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 ir3uance.
FOR THE NUCLEAR REGULATORY COMMISSION
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.9 J
LLIA. JT John F. Stolz, Chief'
- gerating Reactors Branch #4 Division of Licensing '"'
Attachment:
Changes to the Technical Specifications Date of Issuance: May 15,1981 s
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ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. OPR-51 DOCKET NO. 50-313 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 area of change.
Table of Contents (page1)
(page 11) 66t (new page) 110z (new page) t 4
TABLE OF CONTENTS SECTION TITLE PAGE 1.
DEFINITIONS 1
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1.1 RATED POWER 1
1.2 REACTOR OPERATING CONDITIONS 1
1.3 OPERABLE 2
1.4 PROTECTION INSTRUMENTATION LOGIC 2
1.5 INSTRUMENTATION SURVEILLANCE 3
1.6 POWER DISTRIBLTION 4
1.7 REACTOR BUILDING S
l 1.8 FIRE SUPPRESSION WATER SYSTEM S
2.
SAFETY LIMITS AND LIMITING SAFETY SYSTEM Sci INGS 7
2.1 SAPETY LIMITS, REACTOR CORE 7
2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE 10 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRU-MENTATION 11 3.
LIMITING CONDITIONS FcR OPERATION 16 3.1 REACTOR COOLANT SYSTEM 16 3.1.1 0 eratienal Cem:enents 16 3.1.2 Pressurization. Hea:ue and cooldewn Limitations 18 3.1.3 Minic.um Conc 1:1ons for Criticality 21 3.1.4 Reactor Coelan: Svst?m Activ.ity 23 3.1.5 Cnemistry 25 3.1.6 Leakace 27 3.1.7 Mccerater Temeerature Coefficient of Reactivity 30 3.1.8 Law Pcwer Pnvsics Testine Restrictions 31 3.1.9 Control Roc Oceratien
'32 3.2 MAKEJP AND CHEMICAL ADDITION SYSTEMS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, l
AND REACTOR EUILDING SPRAY SYSTEMS 36 3.4 STEAM AND POWER CONVERSION SYSTEM 40 1
l 3.5 INSTRUMENTATION SYSTEMS 42 3.5.1 Ocerational Safety Instrumentation 42 3.5.2 Control Roc Grcuo and Lower 01stributien Limits 46 3.5.3 Safe:v Features Actua:1:n System ie::cints 49 3.5.4 incero instrumen+ati n 51 3.5.5 Fire Detection Instrumentatics 534 3.6 REACTOR aulLDING 54 3.7 AUXILIARY ELECTRICAL SYSTEMS 56 3.8 FUEL LOADING AND REFUELING 52 3.9 CCNTROL ROOM EMERGENCY AIR CONDITIONING AND ISOLATION SYSTEM 60 3.10 SECONDARY SYSTEM ACTIVITY 66 3.11 EMERGENCY COOLING POND 66a 3.12 MISCELLANEGUS RADI0 ACTIVE MATERIALS SOURCES 66b 3.13 PENETRATION ROOM VENTILATION SYdi:M 66c 3,14 HYDROGEN PURGE SYSTEM 66e l
3.1d FUEL HANDLING AREA VENTILATION SYSTEM 66g 3.16 SHOCK SUPcRESSORS (SNUBSERS) 661 3.17 FIRE SUPPRESSION WATER SYSTEM 65m 3.15 FIRE SUP RESSION SPRINKLER SYSTE.=.5 66n 3.19 CONTROL ROOM AND AUXILIARY CONTROL ROOM MALON SYSTEMS 66c 3.20 FIRE HCSE STATIONS 660 3.21 PENE RATION FIRE BARRIERS 664
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i Amendment No. 55 l
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SECTION TITLE PAGE 4.
SURVEILLANCE STANDARDS 67 4.1 OPERATIONAL SAFEn ITEMS 67 4.2 REACTOR COOT. ANT SYSTEM SURVEILLANCE 76 4.3 TESTING FOLLOWING CPENING OF SYSTEM 78
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4.4 REACTCR BUILDING 79 4.4.1 Reactor Building Leakage Tests 79 4.4.2 Structural Integrity 85 4.5 EMERGENCY COPS COOLING SYSTDi AND REACTOR SUILDING COOLING SYSTEM PERIODIC TESTING 92 4.5.1 Emertenev Core Cooline Svstems 92 4.5.2 Reactor Building Cooling Systems 95 4.6 AUXILIARY ELECTRICAL SYSTDi TESTS 100 4.7 REACTOR CONTROL RCD SYSTEM TESTS 102 4.7.1 Control Rod Drive Svstem Functional Tests 101 4.7.2 Control Rod Progran Verification 104 4.8 EMERGENCY FEEDWATER PUMP IESnNG 105 4.9 REACTIVITY ANCMALIES 106 4.10 CCNTROL ROCM DiERGENCT AIR CONDITICNING AND ISOLATION SYSTEM SURVEILLANCE 107 4.11 PDiETRATICN ROCM VENTILATICN SYSTEM SURVEILLxiCE
'109 4.12 HYDROGEN PURCE SYSTDi SURVEII. LANCE 109b 4.13 EMERGENCY CCOLING POND 110s.
4.14 PJCICACnVE MATERIALS SCURCES SURVEILLANCE 110b i
4.15 AUGMENTED INSER7 ICE INSPEC* ION PROGRAM FCR HIGH ENERGY LINES CUISIDE OF CONTAlh E 110c 4.16 SHCCK SUPPRESSORS (SNU33ERS) 110e 4.16.1 Hvdraulie Shock Suoeressers 110e 4.17 FUEL HANDLDG AREA VENn1AUCN SYSTEM SURVEILLANCE 110h 4.18 S*IAh GENERATOR TUBING SURVIILLANCE 1101 4.19 FIRE DETICU CN D2TRUMENTATION 110p 4.20 FIRE SUPPRESSION VATER SYSTEM 110q 4.21 SPRINKLER SYSTDd.S 110e 4.72 CONTROL ROCM AND AUXILIARY CON ROL ROCM HAI.CN SYS dis 110u 4.23 FIRE HOSI STAUCNS 110v 4.24 PENE RAUCN FIRE BARRIEAS 110w 4.25 REACTCR BUILDDG PURGE FILDAn0N SYSTEM 110x l
4.26 REACTOR 3UILDDG PURGE VALVES 110z l
5.
DESIGN FEA*URES 111 l
5.1 SITE 111 5.2 EACTCR SUILDING 112 5.3 REACTCR 114 5.4 NEW AND SF U T FUEL STCRAGE FACILIn ES 116 6.
ADMINISTRATIVE CCN*ROLS 117 6.1 RESPONSIBILIn 117 6.2 ORGANI'*.A HON 117 6.3 FACILITY STAFF QUALIFICAnCNS 117 l
6.4 TRAINUG 117 l
6.5 EVIEW ANL AUDIT 117 6.6 REPORTA3LE OCCURRDCE ACn0N 126 6.7 SAFETY LDi1T VIOLAUCN 126 6.8 PROCEDURES 127 6.9 RECORD RETENH ON 128 6.10 RADIAH ON PROTEC~ ION PRCCRAM 129 6.11 HIGH RADIAUCN ARIA 129 6.
Pl?CRMNG REQU!RD'INTS la0 l
6.T3 ENVIRONMENTAL QUALIFICATION 147 g
l A=end:ent No.,13,13,, P. M, II ii
~e, 25 P00R ~0RIGINAl
3.23 REACTOR SUILDING PURGE VALVES APPLICA3ILITY This scecification acplies to the reactor building curse sucply and exhaust isolation valves.
CBJECTIVE To specify that reactor building isolation purge valves be closed whenever containment integrity is required by TS 3.6.1.
SPECIFICATICN 3.23.1 The reactor building purge supply and exhaust isolation valves shall be closed criar to the reactor coolant system being heated above 2CO'F.
BASES The react:t' building supoly and exhaust isolatien valves are required to be closed during normal plant cceration in order to ensure reactor build-ing integrity. Purging is allcwed only during :old shutccwn or in refueling shutdcwn.
P00R ORIGINAI.
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4.25 REACTCR SUILDING PURGE VALVES APCLICABILITY This s:ccification applies to the reactor building purge supply and exhaust isolation valves.
CBJECTIVE To assure reactor building integrity.
SPECIFICATICN 4.25.1 The reactor building purge suoply and exhaust isolation valves shall be deternined closed:
a.
At least once per 31 days when centairment integrity is required by TS 3.6.1; and, 3.
Prior to heating the reactercoolant system above 200*F.
BASES Detennination of reactor building purge valve closure will ensure that reactor building integrity is not unintentionally breeched.
1 Amendment No. 55 110z P00R ORIGINAL.
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