ML20247B260
| ML20247B260 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/21/1989 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20247B248 | List: |
| References | |
| NUDOCS 8903290324 | |
| Download: ML20247B260 (13) | |
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ENCLOSURE 1 Proposed Technical Specification Changes i
G903290324 890321 PDR ADOCK 05000458 ik P PDC
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.INDEX !
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION MGE j i
CONTAINMENT SYSTEMS (Continued) l 3/4.6.4 PRIMARY CONTAINMENT AND ORWELL ISOLATION VALVES. . . . . . . . 3/4 6-31 3/4.6.5 SECONDARY CONTAINMENT Secondary Containment Integrity - Operating............. 3/4 ,6-48 Secondary Cont'ainment Integrity - Fuel Building......... 3/4 6-50 Secondary Containment Automatic Isolation Dampers....... 3/4 6-51: )
i Standby Gas Treatment System............................ 3/4 6-55 Shield Building Annulus Mixing System. . . . . . . . . . . .. . . . . . . 3/4 6-57 Fue'l Building Venti 1atton............................... 3/4 6-58 4 3/4.6.6 ATMOSPHERE CONTROL' Primary Containment Hydrogen Recombiner Systems......... 3/4 6-61 Primary Containment /Drywell Hydrogen Mixing System...... 3/4 6-62 Primary Containment /Drywell Hydrogen Ignition System.................................................. 3/4'6-64 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Standby Service Water System............................. 3/4 7-1 Ultimate Heat Sink....................................... 3/4 7-3 3/4.7.2 MAIN CONTROL ROOM AIR CONDITIONING SYSTEM. . . . . . . . . . . . . . . . 3/4 7-5 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM.................... 3/4 7-8 3/4.7.4 ................................... 3/4 7-10 3/4.7.5 SEALED SOURCE CONTAMINATION......... .................... 3/4 7-16 RIVER. BEN 0;- UNIT 1 viii
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SEP 0 S 1988 INDEX SDC LIST OF FIGURES FIGURE TITLE PAGE 3.2.1-1 Maximum Average Planar Linear Heat Generation Rate (BP85R8094).................................... 3/4 2-2 3.2.1-2 Maximum Average Planar Linear Heat Generation Rate (BP85R8163)..................................... 3/4 2-3 3.2.1-3 Maximum Average Planar Linear Heat Generation Rate (BP85RB248)..................................... 3/4 2-4 3.2.1-4 Maximum Average Planar Linear Heat Generation Rate (BP85RB278)..................................... 3/4 2-5 3.2.1-5 Maximum Average Planar Linear Heat Generation Rate (BP85R8299)..................................... 3/4 2-6 3.2.1-6 Maximum Average Planar Linear Heat Generation Rate (BP85R8305)..................................... 3/4 2-6A 3.2.3-1 MCPR ..............................................
f 3/4 2-9 3.2.3-2 MCPR ..............................................
p 3/4 2-10 3.4.1.1-1 Thermal Power versus Cor6 F1ow..................... 3/4 4-3 l 3.4.6.1-1 Minimum Temperature Required Versus Reactor
...................m .... 3/4 4-24
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- - -( -i---1: ^1:n ':r in d= :r N :ti:: 1 T::t.' " ??f xX-E__ 3/' ' 'l B 3/4 2.3-1 Power Flow Operating Map...........................' B 3/4 2-6 8 3/4 3-1 Reactor Vessel Water Leve1......................... B 3/4 3-8 8 3/4.4.6-1 Fast Neutron Fluence (E>l MeV) at 1/4 T as a Function of Service Life........................... B 3/4 4-8 5.1.1-1 Exclusion Area..................................... 5-2 5.1.2-1 Low Population Zone................................ 5-3 ]
5.1.3-1 Map Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents....'... 5-4 i
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RIVER BEND - UNIT 1 xxii Amendment No. 13,27
.y PLANT SYSTEMS 3/4.7,4 LIMITING CONDITION FOR OPERATION 7.4 All snubbers shall be OPERA 8LE. The only snubbers excluded from this re irement are those installed on nonsafety-related systems and then only f thei failure or failure of the system on which they are installed would no ad ave se effect on any safety related system.
APPLICA8I TY: OPERATIONAL CONDITIONS 1, 2 and 3, and OPERATIONAL '0ITIONS 4 and 5 for s CONDITIONS. %bbers located on systems required OPERA 8LE in those ORATIONAL A
ACTION:
With one or more sn ers inoperable on any system, withi 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> replace or restore the inoperable nubber(s) to OPERA 8LE status and erform an engineering.
evaluation per Specifica on 4.7.4.g on the attached c onent or declare the attached system inoperable nd follow the appropriat ACTION statement for that system.
SURVEILLANCE REQUIREMENTS
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4.7.4 Each snubber shall be d6monstrate OPERA 8LE by performance of f.he following augmented inservice inspectio ogram and the requirements of Specification 4.0.5.
- a. Inspection Types As used in this spec ication, type of s ber shall mean snubbers of the same design nd manufacturer, irres ctive of capacity,
- b. Visual Inspecti s Snubbers are ategorized as inaccessible or access le during reactor operation. Each of these groups. (inaccessible and a essible).may be~inspe ed independently according to the schedule low.. The first inservi visual inspection of each type.of. snubber sha be performed s .
after months but within 10 months of commencing. POWER 0 RATION and all include all snubbers. If all snubbers of each t are fo d OPERA 8LE during the first inservice visual inspection, e cond inservice visual inspection shall be performed at the f st refueling outage. Otherwise, subsequent visual inspections shal be performed in accordance with the following schedule:
RIVER BEND - UNIT 1 3/4 7-10
NT SYSTEMS SU It. LANCE REQUIREMENTS s ,
No. of Inoperable Snubbers of Subsequent Visual ach Type per Inspection Period Inspection Period *6 0 18 months i 25%
1 12 months 1 2 2 6 months i 3, 4 124 days c 5%
5,6,7 62 days 25%
8 or more 31 day 1 25%
- c. Visual Inspe tion Acceptance Criteria Visual inspect ns shall verify that: (1) here are no visible indi-l cations of damag or impaired OPERA 8ILI and (2) attachments to the foundation or sup rting structure are ERA 8LE, and (3) fasteners for attachment of t a snubber to the onent and to the snubber anchorage are OPERA 8 . Snubbers wh h appear inoperable as a result of visual inspections ay be data ned OPERA 8LE for the purpose of establishing the next v ual insp tion inurval, provided that:
(1) the cause of the rej tion clearly established and remedied i for that particular snubbe an .for other snubbers irrespective of i type on that system that ma e generically susceptible; and (2) the affected snubber is functic ly tested in the.as-found condition and determined OPERABLE p Sp ification 4.7.4.f.
- d. Transient Event Inspec on An inspection shall e performed of 11 mechanical snubbers attached to sections of sys s that have expe fenced unexpected, potentially damaging transie s, as determined fr a review of operational data or a visual ins etion of the systems, thin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for accessible areas and wit n 6 months for inaccessib1 areas, following this deter-mination. I addition to satisfying the v ual inspection acceptance criteria, f eedom-of-motion of mechanical sn bars shall be verified using at ast one of the following: (1) man 11y induced snubber movemen or (2) evaluation of in place snubbe piston setting; or (3) st king the mechanical snubber through its ull range of ,
trav .
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- T inspection interval for each type of snubber shall not be lengthe d more an one step at a time.
he provisions of Specification 4.0.2 are not applicable.
I RIVER BEND - UNIT 1 3/4 7-11 4
1 SYSTEMS SU ILt.ANCE REQUIREMENTS (Continued) 1 4
- e. Functional Tests ring the first refueling shutdown and at least once per 8 months t reafter during shutdown, a representative sample of s bbers shall be sted using one of the following sample plans for ch type of sn r. The sample plan shall be selected prior to e test period and ca t be changed during the test period.. The C Regional Admin-1strato shall be notified in writing, prior to t test period, of the samp plan selected, or the sample plan us in the prior test period sha be implemented:
- 1. At least 0% of the total of each Aype snubber shall be func-tionally stad either in place or in bench test. For each snubber of type that does not meet he functional test accep-l tance criter of Specification 4.7 4.f. an additional 10% of that type of s ubber shall be fu tonally tested until no more failures are fo d or until all ubbers of that type have been functionally tes d; or-
- 2. A representative s le of a ch type of snubber shall be function- 1 ally tested in acco e 'th Figure 4.7.4-1. ;"C" is the t.otal number of snubbers of found not meeting the acceptance requirements of Speciff t. ion 4.7.4.f. The cumulative number of snubbers of a type s is denoted by "N".- At the end-of-each day's testing, values of "N" and "C"'(previous day's
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total plus current 's inc nta) shall be plotted on Figure 4.7.4-1. at any ti the point plotted falls in the
" Reject" region 11 snubbers of t type shall be functionally 1 tested. If at ny time the poin lotted falls in the " Accept"
. region, testi of snubbers of the type may be terminated.
When the po t plotted lies in the entinue Testing" region, additional snubbers of that type shal be tested'until the point e " Accept" region or the "R falls in ect" region, or all the-snubbe of that type have been tested; r ]
- 3. An 1 itial representative sample of 55 sn es shall be function- j al tested. For each snubber type which do not meet the func- 1 onal test acceptance criteria, another samp 'of at least one- 1 a1f the size of the initial sample shall be to ted until the total number tested.is equal to the initial samp size multiplied by the factor,1 + C/2, where "C" is the number o snubbers found which do not meet the functional test acceptance er aria. The: i results fros'this sample plan shall be' plotted using. n'" Accept" line which follows the equation N = 55(1 + C/2). Each nubber.
point should be plotted as soon as the snubber is teste If the point plotted falls on or below the" Accept" line, to ting of that type of snubber may be terminated. If the point p tted '
falls above.the " Accept" line, testing must continue until e point falls in the " Accept" region'or all the snubbers of tha ;
j type been tested.
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\t.ANTSYSTEMS S ILLANCE REQUIREMENTS (Continued) i
- 4. For each type of snubber, an initial representative samp of 68 snubbers shall be functionally tested. .Three snubb s l of.each type are allowed not meeting the functional t t accept-- 1 I
. ance criteria. - If the number of snubbers that faile the test ,
is greater than 3, an additional sample of that t of snubber I 1 to 22(A-3) shall be functionally tested, wh e "A" is , j total . number of snubbers failed during the f nctional test 1 of he representative sample. For each snubbe that failed during :
the. nctional' test of the resample, an addi onal sample of 22 '
snubb s of the same type shall be function ly tested. The 'l tests s 11 continue until no more failur are found or until -;
all snub rs of that type have been func onally tested.. 1 Testing equipmen failure during functions testing may invalidate i that day's testin and allow that day's sting to resume anew at a j later time, providi~ all snubbers tes with the failed equipment during the day of eqt :
nt failure er ratested. The representative. l sample selected for th. functional t t sample plans shall be randomly {
selected-from the snubb s of each e' end reviewed'before beginning the testing. The review 11 en re as -far as practical that the !
sample is representative o the arious configurations,l operating.
environments, range of size, capacity of snubbers of each type. !
Snubbers placed in the same 1 ations as snubbers which failed the i previous functional test s retested at the time'of the next- 1; functional test but shaf1 t be ncluded in the sample' plan.' If,L j during the functional te ing, a ional sampling is required due to i failure of only one typ of snubber, the functional testing results shall-be reviewed at a time to-dete ine if additional sangles 3 should be limited to he type of'snubb which has; failed the func-tional testing.
- f. Functional Test cceptance Criteria The snubber f ctjenal test shall verify that:
- 1. Activ ion M estraining action) is achieved ithin the specified ran in both tension and' compression;
- 2. F r mechanical snubbers, the force required to i itiate or main-in motion'of the snubber is within the specifie range in both directions of travel; and
. For snubbers specifically required not to displace un r contin- :
uous load, the ability of the snubbe? to withstand load ithout: "
displacement. i Testing methods may be used to measure parameters indirectly or ra-meters other than those specified if those results can be correlat to the specified parameters through established methods.
RIVER 8END - UNIT 1 3/4 7-13
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. DE LETE D NT SYSTEMS SU ILLANCE REQUIREMENTS (Continued) 1
- g. Functional Test Failure Analysis A engineering evaluation shall be made of each failure to et the fun tional test acceptance criteria to determine the caus of the fail . The results of this evaluation shall be used, applicable, in se cting snubbers to be tested in an effort to de ine the OPERA 8I TY of ither snubbers, irrespective of type, ich may be subject the scos failure mode.
For the snu ers fon diinoperable, an engineerin evaluation shall be performed the components to which the ino rable snubbers are attached. The urpose of this engineering av uation shall be to I determine if the omponents to which the ino rable snubbers.are attached were adv sely affected by the i erability of the snubbers, in order to ensure at the component r ns capable of meeting the designed service.
If any snubber selected or function . testing either fails'to. lock up or-fails to move, i.e., frozen-i place, the cause will be eval-usted and if caused by man actur or design deficiency', all snubbers of the same type subject.to ano defect shall be functionally . ,
tested. This testing requi t shall be independent of the require-ments stated in Specification 4. 4.e for snubbers riot meeting the functional tgst acceptance ite a.
- h. Functional Testina of Re ired and placed Snubbers Snubbers that fail t visual inspect 1 or.the functional test i
-acceptance criteria 11 be repaired or placed._ Replacement snuobers and snubb s that have repairs t might affect the func-tional test resu' shall be tested to meet a functional test criteria before installation in the unit.. hanical' snubbers shall have met the captance criteria subsequent to their most recent-service, a he freedom-of-motion test must ha been performed within 12 nths from the time the snubber was in talled in the unit.
- 1. Snubber ervice Life Procram The rvice life'of all snubbers shall be monitored to sure that th service life is not exceeded between surveillance in ections.
T maximum expected service life for various critical pa s shall be etermined and established based on engineering information nd shall.
be extended or shortened based on monitored test results and ail ure --
history. Critical parts shall be replaced so that.the maximum ervice life will not be exceeded during a period when the snubber. is r uired to be OPERABLE. The parts replacements shall be documented and t documentation shall be retained in accordance with Specification _6. 0.A, i l
RIVER BEND - UNIT 1 3/4 7-14 1
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RIVER BEND - UNIT 1 3/4 7-15
m ENCLOSURE 2 Revised Technical Specification Bases i
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INDEX j BASES SEC7 ION PAGE i I
CONTAINMENT SYSTEMS (Continued) 3/4.6.3 DEPRESSURIZATION SYSTEMS........................... B 3/4 6-5 3/4.6.4 PRIMARY CONTAINMENT AND ORYWELL ISOLATION VALVES... B 3/4 6-6 3/4.6.5 SECONDARY CONTAINMENT.............................. B 3/4 6-6 3/4.6.6 ATMOSPHERE CONTR0L................................. B 3/4 6-7 3/4.7 PLANT SYSTEMS 3/4.7.1 STAND 8Y SERVICE WATER SYSTEM....................... B 3/.4 7-1 3/4.7.2 MAIN CONTROL ROOM AIR CONDITIONING SYSTEM.......... B 3/4'7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM.............. B 3/4 7-1 {
3/4.7.4 h-u_wbb kh- _
.....s........................ B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION........................ B 3/4 7-3 3/4.7.6 FIRE SUPPRESSION SYSTEMS........................... B 3/4 7-3 3/4.7.7 FIRE-RATED ASSEMBLIES.............................. B 3/4 7-4 3/4.7.8 AREA TEMPERATURE MONITORING........................ B 3/4 7-4 1 3/4.7.9 MAIN TURBINE BYPASS SYSTEM......................... B 3/4 7-4 3/4.7.10 STRUCTURAL SETTLEMENT........................... .. B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS.............. B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES............ B 3/4 8-3 RIVER BEND - UNIT 1 xv L-_ - - - - _ - - - - - - _ _ - - - - - - - - - -
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I REACTOR CORE ISOLATION COOLING SYSTEM (Continued)
The surveillance requirements provide adequate assurance that RCIC will '
be OPERA 8LE when required. Although all active components are testable and full flow.can be demonstrated by. recirculation during reactor operation, a complete functional test requires reactor shutdown. The pump discharge piping is maintained earliest possible fullmoment.
to prevent water hammer damage and to start cooling at the 3/4.7.4 w: -
All. snubbers are required OPERABLE to ensure that the structural inte ty o
duri he reactor coolant _ system and all other safety related systems is ma ained and following a seismic or other event that initiates dynamic 1, ds.
Snu size. For rsample, are classified and grouped by design and manufacturer ut,not by 2-kip,10-kip, and 100-kip capacity mechanic snubbers utilizing th ame design features and manufactured by Company same type. The ame design mechanical snubbers manufactured
" are of the Company "B" I would be of a di rent type, for the purposes of this Tec cal Specification, a's would hydraulic ubbers from either manufacturer.
A list of individu snubbers with detailed inf tion of snubber.loca-tion, size and system af ted shal) be available the plant. The accessi-bility of each snubber shal be determined and a ved by the Facility Review Committee. .The determination j all be based 1 the accessibility of the snubber during plant operations .g., radia on level, temperature, atmosphere, i location,etc.) The addition or lation .any hydraulic or mechanical snubber shall be made in accordance with Se on .59 of 10 CFR Part 50.
When a snubber is found inopera e, including the determination of the ubbern engineering evaluation is performed, de of failure, in order to deter- {
mine if any safety-related compo nt or syst has been adversely affected by the inoperability of the sn er. The eng ering evaluation shall determine i whether or not the snubber e of failure has i arted a significant effect or degradation on the supp ed component or syst To provide furthe assurance of snubber reH e ili a representative sample of the instal d snubbers will be functionally te d, during plant shutdowns, at 18 th intervals. Selection of a represen tive sample accord-ing to one of th four sample plans provides assurance that snubbers in the.
plant will.be RABLE.within acceptance limits. Observed.fai es of these sample snubb s will require functional testing of additional un .
The ervice life of a snubber is evaluated from manufacturer in and from c sideration of the snubber service conditions and associated in lla-tion nd maintenance records ,f.e., newly installed snubber, seal replace sp ng replaced, in high radiation area, in high temperature area, etc. . .
e requirement to monitor the snubber service life is included to ensure-RIVER BEND - UNIT 1 8 3/4 7-2
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PLANT SYSTEMS BASES l.
h g ntinued)'
that the snubbers per undergo a e .
evaluation in view of their age and operating condit e records will provide statistical bases for future con of snubber life. .The requirements for 4
j the maint records and of the snubber serv eview are not ~
to affect plant operation.
3/4.7.5 SEALED SOURCE CONTAMINATION 1'
The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR.70.39(c) limits for plutonium. This limitation will ensure-that leakage from byproduct, source, and special nuclear material sources will not exceed, allowable intake values.
Sealed sources are classified into three groups according to their use, with surveil'1ance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more.often than those which are not. Sealed sources which are l continuously enclosed within a shielded siechanism, i.e., sealed sources within I
- adiation monitoring devices,.are considered.to be stored and need not be tested unless they are temoved from the shielded mechanism. f
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3/4 7.6 FIRE SUPPRESSION SYSTEMS The OPERA 8ILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of.the facility where safety related equipment is located. The fire suppression systems consist of the water system, spray and/or sprinkler systems, Halon system and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire l protection program.
In the event that portions of the fire suppression systems are inoperable, i alternate backup fire fighting equipment is required to be made.available in the affected areas until the inoperable equipment is restored to service. When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate ;
means of fire fighting than if the inoperable equipment is the primary means '
of fire suppression.
The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression' systems are met. 'An j allowance is made for ensuring a sufficient volume of Halon in the Halon storage tanks by verifying the weight and pressure of the tanks. i In the event the fire suppression water system becomes inoperable, i immediate corrective measures must be taken since this system provides the. ,
major fire suppression capability of the plant. l RIVER BEND UNIT 1 8 3/4 7-3 i i
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