ML19326B782
| ML19326B782 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/06/1977 |
| From: | Desiree Davis Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19326B779 | List: |
| References | |
| NUDOCS 8004170609 | |
| Download: ML19326B782 (12) | |
Text
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b UNITED STATES y*
NUCt. EAR REGULATORY COMMISSION j
WASHlhiGTON, D. C. 20666 e
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE - UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 23 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 October 1,1975, as supplemented by letters dated February 11, 1976, August 30, 1976, September 13, 1976, and February 15, 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 conformity 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 authori:ed 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 common defense and security or to the health and safety of the public; 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.
g004170
. 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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 23, 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.
d FOR THE NUCLEAR REGULATORY COMMISSION
'in
'4 Don K. Davis, Acting Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: April 6,1977 8
ATTACHMENT TO LICENSE AMENDMENT NO. 23 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Change the Appendix A portion of the Technical Specifications as indicated below:
1.
Change the page numbers of existing pages as follows:
OLD PAGE NUMBER NEW PAGE NUMBER 110f 110h 1109 1101 2.
Add the following new or revised pages. The changed areas on the revised pages are identified by marginal lines, with the exception of page 110e, which has been entirely revised.
i revised) ii revised) 661 new) 66j new 66k new 661 new 110e revised) 110f (new) 1109 (new) l l~
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TABLE OF CONTESTS
-SECTION TITLE PAGE
- 1.
DEFINITICNS 1
1.1 RATED PC74ER 1
1.2 REACOR OPERATING C0::DITIO:;5 1
1.3 OPERA 3LE 2
1.4 PROTECTION INSTRUMENTATION LCG1C 2
1.5 INSTRUMESTATION SURVEILLN:CE 3-1.6 QUADRANT PO?iER TILT 4
1.7 REAGOR SUILDING 4
2.
SAFEW LDtITS ED LIMITING SAFETY SYSTDI SETTINGS 7
7 2.1 SAFETY LDlIT5, REAGOR CJRE 2.2 SAFETY LDtITS, REACTOR SYSTDI PRESSURE 10 2.3 LDtITING SAFETY SYSTDI SETTINGS, PROTECTIVE I'GUU-MENTATION 11 3.
LDIITING CONDITIONS FOR OPEMTION 16 3.1 REACTOR CCOLANT 5Y5TEt 16 3.1.1 Ocerational Conronents 16 3.1.2 Pressurttate.on, ricatuu s.d Cooldewn Limitations 18 3.1.3 Minimus Condi:: ens for Criticality 21 3.1.4 Reactor Coolant Svsten Ac :vity 22 3.1.S Chemistry 25 3.1.6 Leakage 27 3.1.7 Moderator Te rerature Coefficient of Reactivity 30 3.1.8 Low Powcr Atysics Testinz Restricticns 31 3.1.9 Control Roo 0:eratica 32 3.2 MAKEUP AND CNDlICAL ADDITION SYSTE!S 34
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33 DIERGENCY CORE COOLING, REACTOR BUILDING CDOLING, AND REACTOR BUILDING SPRAY SYSTDIS 36 40 3.4 STE.Ol AND PCNER CONVERSION SYSTDI 3.5 INSTRUMENTATION SYSTD!S 42 3.5.1 Operational Safety Ins trc.=entation 42 3.5.2 Control Roc Grous anc ower Distr:.bution Limits 46 3.5.3 Safety Features Actuation ivste= Setroints 49 3.5.4 In-Core Instru=entation 51 3.6 REACTOR BUILDING S4 3.7 AUXILIARY ELECTRICAL SYSTDI 56 3.8 FUEL IDADING AND REFUELING 58
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3.9 CO:RROL RCOM BtERGENCY AIR CONDITIONING SYSTDI 60 3.10 SECONDARY SYSTDI ACTIVITY 66 3.11 BtERGENCY CCOLING POND 66a 3.12 MISCELL\\NEOUS RADI0 ACTIVE MATERIALS SCURCES 66b
'3.13 PENETRATION ROCM VENTILATION SYSTDI 66c 3.14' HYDROGEN PURCE SYSTUI 66e 3.15 FUEL !!ANDLING AREA VENTILATICN SYSTDI 66g
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3.16 SHOCK SUPPRESSORS (SNUBBERS) 661 Amendment No. 23
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SECTION TITLE PAGE 4
' SURVEILLANCE P.ECUIREMENTS 67 4.1' OPERAT10:iAL SAi hiY iTSfS 67-4.2 REACOR COOLANT SYSTDI SURVEI'.L\\NCE 76 4.3.
REACTOR COOLNiT SYSTSt II.TEGRITY FOLLONING ENTRY 78 4.4 REACTOR BUILDING 79 4.4.1 Reactor Building Lenknee Tes:
79 4.4.2 S tructural In:eerity SS 4.5 DEkGENCY CORE CCOLING SYSTE:t AND REACOR BUILDING COOLING SYSTEM PERIODIC TESTING 92 4.S.1 Emergency Core Ceoling Syste:
92 4.S.2 Reactor Euildinz Cociinz S. stems 95 4.6 AUXILIARY ELECTRICAL SYSTE.'1 TESTS 100 4.7 REACOR CONTROL ROD SYSTE! TESTS 102 4.7.1 Control Rod Drive System Functional Tests 10 2 4.7.2 Control Rod Proers= Verifics: ion 104 4.8 EtERGENCY PEEDrATER PU:i? TESTING 105 4.9 REACTIVITY ANO:.tALIES 106 4.10 CONTROL ROOM EFERGENCY AIR CONDITIONING SYSTE4 SURVEILLANCE 107 4.11 PENE'GATION ROOM VENTILATION SYSTDi SURVEILLANCE 109 4.12 HYDROGEN PURGE SYSTE! SURVEILLANCE 109b i
4.13 DERGENCY COOLING POND 110s 4.14 RADICACIVE MATERIALS SOURCES SURVEILLANCE 110b 4.15 AUGIENTED INSERVICE INSPECTION PROGRN1 FOR HIGI ENERGY LINES CUTSIDE OF CONTAINMENT 110c 4.16 SHO'% SUPPRESSORS (SNUBBERS) 110e j
4.16.1 Hydraulie Shock Suporessors 110e 4.17,
. FUEL HANDLING AREA VENTILATION SYSTBI SURVEILLANCE 110h S.
DESIGN FEATURES 111 S.1 SITE 111 S.2 REA COR BUILDING 11' S.S REACTOR
,114 S.4 NEW AND SPENT FUEL STORAGE FACILITIES 116 ADMINISTR' TIVE CONTROLS 117 6.
A 6.1 RESPONSIBILITY 117 6.2 PLANT STAFF ORGANIEATION 117 6.3 QUALIFICATIONS 118
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6.4 REVTEN AND AUDIT 121 2
6.S ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE DESCRIBED IN TECHNICAL SPECIFICATION 6.12 3 1 127 6.6 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED 128 6.7 PLANT OPERATING PROCEDURES 129 6.8 RADIATION AND RESPIRATORY PROTECTION PROGRAM 130 6.9 EMERGENCY PLANNING 136 6.10 INDUSTRIAL SECURITY PROGRN!
137 6.11 RECORDS RETENTION 138-G.12~
PLANT REPORTING REQUIREtENIS 140 I
Amendment No.'23 11 1
3.16 Shock Suppressors (Snubbers)
Applicability Applies to all shock suppressors (snubbers) listed in Table 3.16-1.
Objective To assure adequate shock suppression protection for primary coolant system piping and any other safety related system or component under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. This is done by assuring the operability of those shock suppressors installed for that purpose.
1 Specification 3.16.1 The reactor shall not be heated above 200F if a shock suppressor listed in Table 3.16-1 is known to be inoperable.
3.16.2 If a shock suppressor listed in Table 3.16-1 is determined to be inoperable during power operation, that shock suppressor shall be made operable or replaced within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the reactor shall be placed in the cold shutdown condition within an additional 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
3.16.3 Shock suppressors may be added to safety related systems without prior License Amendment to Table 3.16-1 provided that a revision J,
to Table 3.16-1 is hcluded with the next License Amendment request.
Bases Shock suppressors are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable shock suppressor is an increase in the prob-
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ability of structural damage to piping as a result of a seismic or other event initiating dynamic loads. It is therefore required that all shock suppressors required to protect the primary coolant system or any other safety system or component be operable during reactor operation.
Because the shock suppressor procaction is required only during low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements. In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown condition will permit an orderly shutdown consis-ten't with standard operating procedures. Since plant startup should not commence with knowingly defective safety related. equipment, Specification 3.16.1 prohibits startup with inoperable shock suppressors.
Amindment No. 23 661
Table 3.16-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)
Snubber No.
Location Elevation Snubber in High Snubbers Snubbers Snubbers Radiation Area' Especially Inaccessible. Accessible During Shutdown
- Difficult During Normal During Normal to Remove Operation Operation HS-1 Decay Heat Line B 329' 1"
X X
HS-2 Decay Heat Line A 322' 11-3/8" X
X HS-49 Decay Heat Line A 329' 1"
X X
'HS-50 Decay Heat Line A 322' 11-3/8" X
X HS-8 Pressurizer Spray Line 408' 7-11/16" X
X HS-9 Pressurizer Spray Line 408' 7-11/16" X
X HS-51 Pressurizer Spray Line 373' 0"
X X
X HS-52 Pressurizer Spray Line 373' 0"
X X
X HS-53 Pressurizer Spray Line 382' 0"
X X
X HS-54 Pressurizer Spray Line 381' 6"
X X
X HS-55 Pressurizer Spray Line 398' 6"
X X
X HS-56 Pressurizer Spray Line 398' 0"
X X
X HS-57 Pressurizer Spray Line 406' 10" X
X HS-58 Pressurizer Spray Line 408' 7-11/16" X
X HS-59 Pressurizer Spray Line 408' 7-11/16" X
X HS-60 Pressurizer Spray Line 408' 7-11/16" X
X HS-61 Pressurizer Spray Line 408' 7-11/16" X
X HS-62 Pressurizer Spray Line 408' 7-11/16" X
X HS-63 Pressurizer Spray Line 408' 7-11/16" X
X l
f (Modifications to this Table due to changes in high radiation areas should be submitted to the NRC as part of t1e next license amendment.
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Amendment flo. 23
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Table 3.16-1 j
SAFETY RELATED Sil0CK SUPPRESSORS (SNUBBERS)
Snubbar No.
Location Elevation Snubber in liigh Snubbers Snubbers Snubbers Radiation Arca Especially Inaccessible
- Accessible During Shutdown
- Difficult to' During Norr.al During Normsl Rcmove Operation Operation HS-10 Pressurizer Relief Line 409' 2-3/4" X
X HS-11 Pressurizer Relief Line 410' 2-3/4" X
115 -1 2 -
Pressurizer Relief Line 410' 2-3/4" X
115 -1 3 Pressurizer Relief Line 400' 0"
X X
HS-14 Pressurizer Relief Line 400' 0"
X X
HS-66 Pressurizer Relief Line 410' 2-3/4" X
k HS-67 Pressurizer Relief Line 410' 2-3/4" X
HS-68 Pressurizer Relief Line 410' 2-3/4" X
X HS-69 Pressurizer Relief Line' 410' 2-3/4" X
11S - 7 0 Pressurizer Relief Line 391' 0"
X X
X HS-71 Pressurizer Relief Line 367' 6"
X X
X 115 - 7 2 Pressurizer Relief Line 357' 0"
X X
X HS-88 Pressurizer Relief Line 370' 0"
t X
X H-A-1 Pressurizer Relief Line 400' 0"
(
X X-H-A-2 Pressurizer Relief Line 399' 0"
.(
X X
i:-B-1 Pressurizer Relief Line 400' 0"
T.
X X
H-B-2 Prau rizer Relief Line 391' 0"
1.
X X
H-C-1 Pressui.zer Relief Line 410' 2-3/4" X
X H-C-2 Pressurizer Relief Line 394' 0"
X X
HS-3 Main Steam Line A 425' 0"
X X
HS-4 Main Steam Line A 408' 6"
X HS-5 Main Steam Line A 428' 0"
X HS-7 Main Steam Line B 420' 0"
X HS-15 Main Steam Line A 408' 6"
X HS-16 Main Steam Line B 423' 2"
X X
HS-17 Main Steam Line B 423' 2"
X X
HS-18 Main Steam Line B 408' 6"
X HS-19 Main Steam Line B 396' 0"
X X
115 - 2 0 '
Main Steam Line a 4'08' 6"
X HS-22 Main Feedwater Header B 376' 4-11/16" X
X HS-23 Main Feedwater Header B 376' 4-11/16" X
X O Modifications to this Table due to changes in high radiation areas should be submitted to the NRC as part of the next license amendment.
Amendment,No. 23
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Table 3.16-1 (Cont.)
. SAFETY RE1.ATED SHOCK SUPPRESSORS (SNUBBERS)
Snubber No.
Location Elevation Snubber in High Snubbers Snubbers Snubbers Radiation Arca Especially Inaccessible
- Accessible
- During Shutdowrf Difficult to' During Normal During Norma:
Remove Operation Operation y
a HS-24.
Main Feedwater Header B 376' 4-11/16".
X X
X HS-25 Main Feedwater Header B 376' 4-11/16" X
X X
HS-26 Main Feedwater Header B 376' 4-11/16" X
X I-
'HS-27 Main feedwater lleader B 376' 4-11/16" X
X l
HS-28 Main Feedwater Header B 376' 4-11/16" X
X X
HS-29 Main Feedwater lleader B 376' 4-11/16" X
X X
HS-30 Main feedwater Line A 361' 0"
X HS-31 Main Fcedwater Header A 376' 4-11/16" X
X HS-32 Main Feedwater Header A 376'.4-11/16" X
X l
HS-33 Main Feedwater Header A 376' 4-11/16" X
X j
HS-34 Main Feedwater Header A 376' 4-11/16" X
X HS-35 Main Feedwater Header A 376' 4-11/16" X
X HS-36 Main Feedwater Header A 376' 4-11/16" X
X X
HS-37 Main feedwater Header A 376' 4-11/16" X
X HS-38 Main Feedwater Header A 376' 4-11/16" X
X HS-21 Emergency Feedwater Line B 394' 0"
X X
X I
1A Reactor Coolant Pump A 390' 10" X
X i
2A Reactor Coolant Pump A 390' 10" X
X 1B Reactor Cenlant Pump B 390' 10" X
X 28 Reactor Ccolant Pump B 390' 10" X
X i
IC Reactor Coolant Pump C 390' 10" X
X i
i 2C Reactor Coolant Pump C 390' 10" x
y 10 Reactor Coolant Pump D 390' 10" X
X 2D Reactor Coolant tump D 390' 10" X
X
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O Hodifications to this Table due to changes in high radiation areas should be submitted to the NRC as part of the, next license amendment.
Amendment No.23 661
4.16' SHOCK SUPPRESSORS (Snubbers)
Applicability Applies to all shock suppressors (snubbers) protecting the primary system and any other safety related system or component.
-Objective Verify an acceptable level of operability of the shock suppressors protecting the primary system and any other safety related system or component.
Specification 4.16.1 The following surveillance requirements apply to all hydraulic shock suppressors listed in Table 3.16-1.
4.16.1.1 All hydraulic shock suppressors whose seal material has been demonstrated by operating experience, leb testing or analysis to be compatible with the operating environment shall be visu-ally inspected. This inspection shall include, but not neces-sarily be limited to, inspection of the hydraulic fluid res-ervoir, fluid connections and linkage connection to the piping and anchor to verify shock suppressor operabi.Lity in accordance with the following schedule:
Number of Hydraulic Shock Next Required Suppressors Found Inoperable Inspection During Inspection or During Interval Inspection Interval O
18 months ! 25%
1 12 months 25%
2 6 months ! 25%
3,4 124 days 25%
4 5,6,7 62 days 25%
->8 31 days t 25%
The required inspection interval shall not be lengthened more than one step at a time.
Shock suppresasors may be categorizad in two groups, " accessible" or " inaccessible", based on their accessibility for inspection during reactor operation. These two groups may be inspected independently according to the above schedule.
4.16.1.2 All hydraulic shock suppressors whose seal materials are other than ethylene propylene or other material that has beeo demon-strated to be compatible with the operating environment shall be visually inspected for operability every 31 days.
110e
/,mendment No. 23
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1 4.16.1.3 The initial inspection of accessible snubbers shall be performed j
within 6 months (125%) from February 23, 1977. For the purpose of entering the schedule in Specification 4.16.1.1, it shall be assumed that the facility had been on a 6 month inspection interval for accessible snubbers. Based on results of an inspection completed February 23, 1977 during which no inoperable inaccessible snubbers were found, inaccessible snubbers are assumed to be on a 12 month inspection interval. The first inspection of inaccessible snubbers shall be performed at 12 months (125%) from February 23, 1977.
4.16.1.4 Once each refueling shutdown, a representative sample of 10 hydraulic shock suppressors or approximately 10% of the hydraulic shock suppressors, whichever is less, shall be functionally tested for operability including verification of proper piston movem-nt, lock up and bleed. For each unit and subsequent unit found inoperable, an additienal 10% or ten hydraulic shock suppressors shall be tested until no more failures are found or all units have been tested.
Shock suppressors of rated capacity greater than 50,000 lb need not be functionally tested. Shock suppressors in high radiation areas during shutdown or those especially difficult to remove need not be selected for functional testing provided their operability was previously verified.
Bases All safety related hydraulic shock suppressors are visually inspected for overall integrity and operability. The inspection will include verifica-tion of proper orientation, adequate hydraulic fluid level and proper attachment of suppressor to piping and structures.
i Ihe inspection frequency is based upon maintaining a constant level of shock suppressor protection. Thus the required inspection interval varies inversely with the observed hydraulic shock suppressor failures. The number of inoperable shock suppressors found during a required inspection determines the time interval for the next required inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
Experience at operating facilities has shown that the required surveillance program should assure an acceptable level of hydraulic shoca suppressor performance provided that. the seal materials are compatible with the operating anvironment.
Hydraulic shock suppressors containing seal material which has not been demonstrated by operating experience, lab tests or analysis to be compatible with the operating environment should be inspected more frequently (every month) until material compatibility is confirmed or an appropriate changeout is completed.'.
110f Amendment No. 23
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Bases (Contd)
Examination 'of defective hydraulic shock suppressors at reactor facilities and material tests performed at several laboratories (Reference 1) has shown' that millable gum polyurethane deteriorates rapidly under the temperature and moisture conditions present in many shock suppressor locations. Although molded polyurethane exhibits greater resistance to these conditions, it also may be unsuitable for application in the higher temperature environments. Data are not currently available to precisely define an upper temperature limit for the moldad polyurethane.
Lab tests and in-plant experience indicate that seal materials are available, primarily ethylene propylene compounds, which should give satisfactory performance under the most severe conditions expected in reactor installations.
To further increase the assurance of hydraulic shock supprersor reliability, functional tests should be performed once each refueling cycle.
These tests will include stroking of the shock suppressors to verify proper piston movement, lock-up and bleed. Ten percent or ten shock suppressors, whichever is less, represents an adequate sample for such test-Observed failures on these samples should require testing of additional units.
Those shock suppressors designated in Table 3.16 -1 as being in high radiation areas or especially difficult to remove need not be selected for functional tests provided operability was previously verified. Shock suppressors of raced capacity greater :.han 50,000 lb are exempt from the functional testing requirements because of the impracticality of testing such large units.
s (1) Report H. R. Erickson, Bergen Paterson to K. R. Goller, NRC, October 7,1974,
Subject:
Hydraulic Shock Sway Arrestors 3
4 Amendment flo. 23 v
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