ML19326C403

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Proposed Changes to Tech Specs 3.16 & 4.16 for Shock Suppressors
ML19326C403
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/10/1976
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19326C401 List:
References
NUDOCS 8004220950
Download: ML19326C403 (11)
v • d • e


Text

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ENCIDSURE 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS Replace existing pages 1, ii,110e,110f and 110g of the Technical Specifications contained in Appendix A to the license with the attached revised pages bearing the same numbers and add pages 661, 66j,

66k, 110 f, 110g, 110h, and 1101. The changed areas on the revised pages are identified by a marginal line. The only changes to pages 110h and 1101 are new page number designation.

i 5

4 iS004 22 o 78D

m,

..s TABLE OF CONTEhTS SECTION TITLE PAGE

- 1.

DEFINITIONS 1

,1.1 RATED PCWER 1

1.2 REACTOR OPERATING CONDITIONS 1

l' 3 OPERA 3L:

7 1.4 PROTECTION INSTRUMD.TATION LCGIC 2

1.5 INSTRUMENTATION SURVEILLN;CE 3

1.6 QUAD? ANT PONER TILT 4

1.7 REACOR SUILDING 4

2.

SAFETY LIMITS AND LI'IITING SAPETY SYS E M SETTING 3 7

7.1 SAFETY LIMITS, RfACTOR CORE 7

2.2 SAFETY LD1ITS, REACTOR SYSTE' PRESSURE 10 2.3 LDf1 TING SAFETY SYSTD1 SETTINGS, PROTECTIVE INSTRU-MENTATION 11 3.

LDlITING CONDITIONS FOR OPERATION 16 3.1 REACTOR CCCLANT 5YSTat 16 3.1.1 Occrational Concenents 16 3.1.2 Pressuri:::..cn. nea:nu =d C oldewn Limita:icns 1S 3.1.3 Minime Condi:.ons for Critical:.tv 21 3.1.4 Reactor Coolan: systen Ac::vt:v 22 3.1.5 Chenistry 25 3.1.6 Leakare 27 3.1.7 Modere:or Tercerature Coefficient of Resetivity 30 3.1.8 Low Power Pavsics Tes::n Res:::ctiens 31 3.1.9 Centrol itoc C:eratten 32 3.2 MAKEUP AND CHSlICAL ADDITICN SYSTE'!S 34 3.3 EMERGENCY CORE CCOLING, REAC OR BUILDING COOLING,

. AND REACTOR BUILDING SPRAY SYSTDiS

.4 3.4 STEAM AND PCNER CONVERSICN SYSTDI

  • i, 3.5 INSTRUMENTATION SYSTD!S 42 3.S.1 Operational Safety Instrumentation 42 3.5.2 Control Roc Grot.m anc cwer Dist foution Limits 46 3.5.3 Safety Features Actus: en ivs e setecints 49 3.5.4 In-Core Instr'.::enta: en 51 3.6 REACTOR SUILDING S4 3.7 AUXILIARY ELECTRICAL SYSTDI 56 3.8 FUEL LOADING AND REFUELING 58 3.9 C0hTROL RCCM DIERGENCY AIR CONDITIONING SYSTDi 60 3.10 SECONDARY SYSTDI ACIVITY 66 3.11 EMERGENCY CCCLING POND 66a 3.12 MISCELL\\SECUS PADICACTIVE MATERIALS SCURCES 66b 3.13 PENETRATION RCCM VENTILATICN SYSTDI 66c 3.14 HYDRCGEN PURGE SYSTEM 66e 3.15 FUEL !!ANDLING AREA VENTIIATICN SYSTEM 66g 3.16 SHOCK SUPPRESSORS 66i L

s SECTION TITLE PAGE 4.

' SURVEII.LMICE P.F.CUIREfE!TS 67

4.1 OPERATIC

AL SMbiY 1751S 67 4.2 REACOR CCOLxlT SYSTE! SURVEILL* dice 76 4.5 REACTOR C00LRiT SYSTSI IhTEGRITY FOLLONING ESTRY 78 4.4 REACTOR BUILDING 79 4.4.1 Reactor Buildine Lenkcce Tes 79 4.4.2 Structural Integr::v 85 4.S SERGENCY CCRS C;0LI.NG SYSTE! N!D REACOR BUILDING COOLING SYSTE11 PERIODIC TESTING 92 4.5.1 E=errency Core Ccoling Svste:

92 4.5.2 Reactor Euildinz cociing S<sters 95 4.6-

- AUXILIARY ELECTRICAL SYSTE: TESTS 100 4.7 REACTOR CONYROL ROD SYSTE! TESTS 102 4.7.1 Control Rod Drive System Functional Tests 102 4.7.2 Control Rod Prot:2= Verliica: ion 104 4.8 EtERGENCY PEEi3ATER PLSiP TESTING 105 4.9 REACTIVITY RIC5tALIES 106 4.10 CONTROL ROOh! BERGENCY AIR CONDITICNING SYSTE4 SURVEILLANCE 107 4.11 PENETRATION R0051 VENTILATICN SYSTDI SURVEILLANCE 109

-4.12 HYDROGEN PURGE SYSTE11 SURVEILLANCE 109b 4.13 DERGENCY COOLING POND

- 110a 4.14 RADI0 ACTIVE StATERIALS SOURCES SUR7EILLX:CE 110b 4~15 AUG5fEhTED INSERVICE INSPECTION ?ROGRMI FOR HICH ENERGY LINES CUTSIDE OF CONTAIRENT 110c 4.16 SHOCK SUPPRESSORS 110e 4.16.1 Hydraulic Shock Sunoressors '

110e 4.17.

. FUEL HANDLING AREA VEhTILATICN SYSTEI SURVEILLANCE 110h S.

DESIGN FEATURES 111 S.1 SITE 111 S.2

- REACIOR SUILDING 112 S.3 REACTOR 11 4 S.4 NEW AND SPENT FUEL STORAGE FACILITIES 116 6.

ADhtINISTRATIVE CONTROLS 117 6.1 RESPONS13ILITY 117 6.2 PLANT STAFF ORGANITATION 117 6.3 QUALIFICATIONS 118 6.4 REVIEN AND AUDIT 121' 6.5 ACTION TO BE TAKEN IN THE EVELT OF A REPORTA3LE OCCURRENCE DESCRIBED IN TECHNICAL SPECIFICATION 6.12 3 1 127 6.6 ACTION TO BE TAKEN IF A SAFETY LDlIT IS EXCEEDED 128 6.7 PLANT CPERATING PROCEDURES 129 6.8 RADIATION AND RESPIRATORY PROTECTION PROGRMI 130 6.9 DIERGENCY PLN;NING 136 6.10 INDUSTRIAL SECURITY PRCCRN!

137 6.11 RECORDS RETESTICN 138 6.12 PLANT REPORTING REQUIRDIESTS 140 11

s s

s 3.16 Shock Suppressors Applicability Applies to all shock suppressors listed in Table 3.16-1.

Objective To assure adequate shock sg pression 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.

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 to Table 3.16-1 is included 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-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 protection 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-tent 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.

O 661

Table 3.16-1 4

SAFETY REl.ATED. S110CK SUPPRESSORS Snubber No.

Location Elevation Snubber in liigh Snubbers Snabbers Snubbers Radiation Area Especially Inaccessible

  • Accessible During Shutdown
  • Difficult to During Normal During Normal Remove Operation Operation 115 - 1 0 Pressurizer Relief Line A 409' 2-3/4" X

llS-Il Prescurizer Relief Line A 410' 2-3/4" X

115-12 Pressurizer Relief Line A 410' 2-3/4" X

115 -1 3 Pressurizer Relief Line A 400' 0"

X 115-14 Pressurizer Relief Line A 400' 0"

X llS-66 Pressurizer Relief Line C 410' 2-3/4

X llS-67 Pressurizer Relie.f Line C 410' 2-3f4" X

11S - 6 8 Pressurizer Relief Line C 410' 2-3/4" X

11S - 6 9 Pressurizer Relief Line B 410' 2-3/4" X

11S-70 Pressurizer Relief Line B 391' 0"

X

'115-71 Pressurizer Relief Line A 367' 6"

X 11S-72 Pressurizer Relief Line A 357' 0"

X li-A-1 Pressurizer Relief Line A 400' 0"

X ll-A-2 Pr: mrizer Relief Line A 399' 0"

X

-f Il-B-1 Pre h izer Relief Line B 400' 0"

X 11-B-2 Pressurizer Relief Line B 391' 0"

X ll-C-1 Pressurizer Relief Line C 410' 2-3/4" X

ll-C-2 Pressurizer Relief Line C 394' 0"

X llS-3 Main Steam Line A 425' 0"

X 115-4 Main Steam Line A 408' 6"

X 11S - 5 Main Steam Line A 428' 0"

X 11S-6 Main Steam Line B 346' 0"

X 11S-7 Main Steam Line B 420' 0"

X 115-15 Main Steam Line A 408' 6"

X 115 - 1 6 Main Steam Line B 423' 2"

X 115-17 Main Steam Line B 423' 2"

X 115 -1 8 Main Steam Line B 408' 6"

X 11 S - 1 9 Main Steam Line B 396' 0"

X 11 S - 2 0 Main Steam Line B 4'08' 6"

X 11S-22 Main Feedwater lleader B 376' 4-11/16" X

115 - 2 3 Main Feedwater lleader B 376' 4-11/16",

X

^

  • Modifications to this Table due to changes in high radiation areas should be submitted to the NRC as part of the next license amendment.

661

Table 3.16-1 (Cont.)

SAFETY RELATED S110CK SUPPRESSORS Snubber No.

Location Elevation Snubber in sligh Snubbers Snubbers Snubbers Radiation Arca Especially Inaccessible

  • Accessible.

u During Shutuowrf Difficult to During Normal During Norma:

Remove Operation Operatien HS-24 Main Feedwater Header 3 376' 4-11/16" X

11S-25 Main feedwater Header B 376' 4-11/16" X

IIS-26 Main Feedwater Header B 376' 4-11/16" X

HS-27 Main feedwater Header B 376' 4-11/16"

-X HS-28 Main Feedwater Header B 376' 4-11/16" X

11S-29 Main Feedwater Header B 376' 4-11/16" X

HS-30 Main Feedwater Line A 361' 0"

X X

11S-31 Main Feedwater Header A 376' 4-11/16" 11 S - 3 2 Main Feedwater Header A 376' 4-11/16" X

11S-33 Main Feedwater Header A 376' 4-11/16" X

HS-34 Main Feedwater Header A 376' 4-11/16" X

lis-35 Main Feedwater lleader A 376' 4-11/16" X

lis-36 Main feedwater lleader A 376' 4-11/16" X

11S - 3 7 Main Feedwater lleader A 376' 4-11/16" X

HS-38 Main Feedwater Header A 376' 4-11/16" X

11S-21 Emergency Feedwater Line B 394' 0"

X 1A Reactor Coalant Pump A 390' 10" X

2A Reactor Coolant Pump A 390' 10" X

18 Reactor Coolant Pump B 390' 10" X

28 Reactor Coolant Pump B 390' 10" X

IC Reactor Coolant 7 ump C 390' 10" X

2C Reactor Coolant Pump C 390' 10" X

1D Reactor Coolant Pump D 390' 10" X

2D Reactor Coolant Pump D 390' 10"

.X

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  1. Modificatione to this Table due to changes in high radi.ation areas should be submitted to the NRC as part of the next lices.ae amendment.

66k

4.16 SHOCK SUPPRESCORS Applicability Applies to all shock suppressors protecting the primary system and any other safety related system or component.

Objeerive 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, lab testing or analysis to be compatible with the operating environmert 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 operability in accordance with the following schedule:

Number of Hydraulic Shock Next Required Suppressors Found Inoperable Inspection During Inspection or During Interval Inspection Interval j

0 18 months : 25%

1 12 months : 25%

2 6 months 25%

3,4 124 days 25%

5,6,7 62 days 25%

>8 31 days

25%

The required inspection interval shall not be lengthened more than one step at a time.

Shock suppressors may be categorized in two groups, " accessible" or " inaccessible", based on their accessibility for inspection i

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 been demon-strated to be compatible with the operating environment shall be visually inspected for operability every 31 days 7 e

110e

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)

l 4.16.1.3 The initial inspection shall be -perfor=ed within 6 =enths from the date of issuance of these specifications. 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, i

4.16.1.4 Once each refueling cycle, a representative sa=ple of 10 hydraulic shock suppressors or approximately 10% of the shock suppressors, whichever is leas, shall be functionally tested '

for operability including verification of proper piston cove-ment, lock up and bleed. For each unit and subsequent unit found inoperable, an additional 10% or can 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 testad.

3ases 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.

The inspection frequency is based upon =aintaining 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 shoch suppressors found during a required inspection determines the time interval for the next required inspection.

Inspections perfor=ed before that interval has elarsed 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.

i

, Experience at operating facilities has shown that the required surveillance program should assure an acceptable level of hydraulic shock auppressor performance provided that the seal materials are compatible with the operating anvironment.

Hydraulic shock suppressors containing seal =aterial 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 N

month) until material compatibility is confirmed or an appropriate changeout is completed.

110f e

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i 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 polyurathane deteriorates rapidly under the temperature and moisture conditions present in =any 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 camperature limit for the molded polyurethane.

i Lab tests and in-plant experience indicate that seal materials are available, primarily ethylene propylene compounds, shich should give satisfactory performance under the most severe conditions expected in reactor installations.

To further increase the assurance of hydraulic shock suppressor 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 suppr ssors, whichever is less, represents an adequate sample for such tet.4 Observed failures on these samples should require testing of additional units. Those shock suppressors designated in Table 3.16 -1as bei.sg in high radiation areas or especially difficult to remove need not be selected for functional tests provided operability was previously verified. Shock suppressors of rated capacity greater than 50,000 lb are exempt from the functional testing requirements because of the impracticality of testing such large units.

(1) Report H. R. Erickson, Bergen Paterson to K. R. Go11er, NRC, October 7,1974,

Subject:

Hydraulic Shock Sway Arrestors 110g

4.17 FUEL HANDLING AREA VENTILATION SYSTEM SURVEILLANCE Applicability Applies to the surveillance of the fuel handling area ventilation sys:cm.

Objective To verify an acceptable level of efficiency and operability of the fuel handling area ventilation systen.

Specification 4.17.1 A: least once per refueling period (not to exceed 13 conths) the following conditions shall be demonstrated:

Pressure drop across the co=bined HEPA filters and charcoal

a. ' adsorber banks is less than 6 inches of water at system design flow rate (+ 10%).

b.

Air distribution is uniform within + 20% across HEPA filters and charcoal adsorbers.

4.17.2.a.

The tests and sample analysis of Specification 3.15.1.a,b,5 c.

shall be performed within 720 systen operating hours prior to irradiated fuel handling operations in the auxiliary building, and prior to irradiated fuel handling in the auxiliary build-ing following significan: painting, fire or chemical release in any ventilation :ene cc =unicating with the system.

i b.

Cold DOP testing shall also be performed prior to irradia:cd fuel handling in the auxiliary building after each complete or partial replacement of a REPA filter bank or after any structural =aintenance on the sys:em housing.

Haiogenated hydrocarbon testing shall also be performed prior c.

to irradiated fuel handling,in the auxiliary building after each complete or partial replacement of a charcoal adsorber bank or after any structural maintenance on the systen housing.

4.17.3 The system shall be operated for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> prior to initia-tion of irradiated fuel handling operations in the auxiliary building.

Bases Since the fuel handling area v-ntilation syste may be in operation when fuel is stored in the pool but not being hand'c] its operability must be verified before handling of irradiated fuel. Oper. tion of the system for 10 hcurs before irradiated fuel handling operaticas and performance of Specification 4.17.2 will deconstrate operability of the active system components and the filter and adsorber systens.

110h

Pressure drop across the combined 1 EPA filters and charecal adsorbers of less than 6 inches of water at the system design ficw rate will indicate tha: the filters and adsorbers are not cle;;ged by excessive amou:1:s of foreign catter.

Pressure drop and air distribution should be deter =ined 2: icas: once per refueling period to show systcu performance capability.

tte frequency of tests and sample analysis are accessary to show that the HEPA filters and charcoal adsorbers can perfom as evaluated.

Tne charecal adsorber efficiency test procedures should allow for obtaining at Icas: two samples.

Each sa=ple should be at least two inches in die.=eter and a length equal to the thickness of the bed. Tests of the charcoal adsorbers with halogenated hyd. scarbon refrigerant and of the HEPA filter bank with CCP aerosol shall L r perfomed in accordance with ANSI."510 (1975) "S tandard for testing-of r Air Cleaning Systems." Any HEPA filters found defective sha' 1, aced with filters qualified according to Re;ulatory Position C.3.d.

. tory Guide 1.52.

Radioactive methyl iodide removal efficency :n saall be perfomed in accordance wi h RDT Standard M16-IT.

If laboratory test results are unaccept,2ble, all charcoal adsorbents in the system shall be replaced with charcoal adsorbents qualified according to Regulatory Guide 1.52.

e 1101 l

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