ML20094R700
| ML20094R700 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/18/1995 |
| From: | Fredrickson R, Haskell S, Petrenko A POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20094R695 | List: |
| References | |
| JAF-RPT-SLC-003, JAF-RPT-SLC-00336-R2, JAF-RPT-SLC-3, JAF-RPT-SLC-336-R2, NUDOCS 9512050111 | |
| Download: ML20094R700 (20) | |
Text
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ATTACHMENT IV to JPN-95-051 Reference 2 NYPA Report JAF-RPT-SLC-00336 Rev. 2 Epndby Llauid Control (SLC) Surveillance Extensions l
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J New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 I 9512050111 951130 PDR ADOCK 05000333
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FITZPATRICK 24 MONTH OPERATING CYCLE STANDBY LIQUID CONTROL (SIL)
SURVEIT I ANCE EXTENSIONS REPORT NO.: JAF-RPT-SLC-00336 REV.1 Prepared by: ,, r ; K-/8-f3'
~ ~S. Hasifell Date I&C Engineer Design Engineering Department Reviewed by: d A. Petrenko w
Date I&C Engineer 4
Approved by: -
" )CTrc#ridi!nin'
/f !// [/ f [
/ Date I&C Supervisor
, Design Engineering Department
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sNY PUUtk HUIMUkilY 1U;O61043U hub 10'93 14: 11 NO.UU6 P.U2 7
FITEPATRICE . 24 MONTH OPERATING CYCIA STANDBY LIQUID CONTROL (SLC)
SURVRilI ANCE EXTENSIONS REPORT NO.: JAF-RFT-SLC-00336 REV.1 l
Prepared by:
- I-/8-6
S,HadeR Date IAC Bagineer Dealgn Engineering Department Reviewed by: ,I/ A/es/ar
- f. Petrenko ' IJate 1&C R=g' rr
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! Approved by: ,
l R. Fredrickson Date IAC Supervisor
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Design Engiocering Department i
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. 24 MONTH OPERATING CYCLE I SLC SURVEILLANCE EXTENSIONS ,
TABLE OF CONTENTS I. EXECUTIVE
SUMMARY
1 II. PURPOSE 1 III. EVALUATION METHODOLOGY 2 IV. SAFETY FUNCTIONS AND EVALUATION 2 V.
SUMMARY
AND CONCLUSIONS 4 VI. REFERENCES 5 VII. ATTACHMENTS
- 1. TABLE 1 SI.C SURVEILLANCE TEST CHANGES 7
- 2. TECH SPEC MARK-UPS 8 Page i
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4 24 MONTH OPERATING CYCLE ;
- l SLC SURVEIH ANCE EXTENSIONS 4
- I. Executive Summary The FitzPatrick plant will be operating on a 24 month fuel cycle. This longer cycle length has a direct effect on surveillance, maintenance, and test activities that are currently performed on a 18 month or refuel outage basis. ,
At FitzPatrick, the Standby Uquid Control System (SII) components are routinely inspected, tested, and maintained to provide a highly reliable system. ,
Typically, the various components in the system are tested on a daily, monthly, and refueling basis. In addition, periodic preventative maintenance is performed on the system.
SLC test and calibration frequencies are mandated by Plant Technical Specifications and the ASME Section XI Inservice Test Program. Maintenance activities are based on operational feedback and manufacturers recommendations. ,
This study evaluates the changes to surveillance requirements to support a nominal twenty-four month fuel cycle. Justification is provided, where appropriate, to support test interval extensions.
The evaluations conclude that a portion of the SIL surveillance intervals can be safely extended to support a nominal 24 month operating cycle (see table 1).
Operational improvements include reduced test cycles on equipment. Cost _
savings and a reduction in worker occupational exposurn are also expected smce plant personnel and resources will not be diverted to perform unnecessary testing.
II. Purpose
'Ihe FitzPatrick plant will be operating on a 24 month fuel cycle. To avoid either an 18-month surveillance outage or a mid-cycle outage, changes are required to the SIL surveillance test intervals prescribed by the FitzPatrick Technical Specifications.
Substantiating the effects of the longer cycle length on SIL surveillance, and test activities requires a comprehensive review of the system, its individual components, and the integrated effect of all test activities on operability.
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, 24 MONTH OPERATING CYCLE J SLC SURVFIT I ANCE EXTENSIONS ,
I j III. Evaluation Methodolopy
! De once per cycle surveillance record for the applicable system components will .
l be evaluated for a time period defined in the evaluation section (Section IV). '
System instruments that will be having their calibration frequency extended to 24 months will have a drift evaluation developed. The drift evaluation will justify the calibration frequency extension or the calibration frequency will not change. l
, System components that will be having their surveillance frequency extended to 24 '
months will be evaluated in the following manner. If surveillance records reveals l
more than one failure to meet acceptance criteria per component, then the
- surveillance frequency can not be extended. One failure per component is
! viewed as acceptable. If exceptions are to be taken, they will be presented in the evaluation section (Section IV). ;
! IV. Safety Functions and Evaluation The Standby liquid Control System is a relatively basic system which is used only in a standby mode during normal operation.
I SLC test, and inspection activities were evaluated to determine the impact of a 24 month operating cycle. He longer cycle length requires an extension of the surveillance test interval for:
- 1. Manual initiation of the system and pump recirculation flow test. (ST-6B)
- 2. Explosive valve and primer assembly tests. (ST-6D)
- 3. Injection of demineralized water into the Reactor Vessel. (ST-6D)
- 4. Relief valve pressure setpoint test. (ST-6C/MP-59.07) ]
l S. Disassembly and inspa@n of one out of two explosive valve internals. )
(MST-11.11) l SLCS boron concentration is checked monthly (reference 24) by chemical analysis of the .
sodium pentaborate solution. De affect of the longer operating cycle on the 660 ppm j acceptance criteria was evaluated (Reference 23) by GE. The calculation shows that 660 1 ppm is adequate to shutdown the reactor for an equilibrium, uprated core loaded for a 24 month cycle.
Other SLC surveillances, such as, valve tests and pump tests are performed during power Page 2
24 MONTH OPERATING CYCLE
/ SLC SURVEIII ANCE EXTENSIONS l
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operation and are not directly impacted by the longer fuel cycle.
The operability of systems and components required by the plant's safety analyses is '
established by the surveillance requirements contained in the Technical Specifications.
Surveillance testing, by definition, can only identify that a component or a system is incapable of performing its safety function (i.e., inoperable). Preventive maintenance, however, reduces the number of failures found during plant operation or during testing.
Recurring problems are generally corrected by PM activities.
The design objective of the SLC system is to bring the reactor from full power to a cold, xenon-free shutdown condition in the event that sufficient control rods cannot be inserted, to accomplish reactor shutdown in the normal manner.
The system utilizes two squib activated shear explosive valves in parallel as a means of isolating each pump from the reactor vessel to prevent inadvertent injection of Boron to the RPV. 'Ihe valves are maintained in the closed position and are activated only in an l emergency to provide a flow path to the reactor vesset Additionally, the fidng circuit !
coutinuity for each valve is continuously monitored by pilot lights, ammete;ts, and a annunciator signaling loss of continuity in the control room to alert plant control room operators if problems with the circuit occurred. The valves were tested far operability by surveillances ST-6D and MST-11.11, the surveillance records yield the following results.
ST-6D was completed on 6/83,2/85,1/87,9/88,4/90,2/92,9/92 ad 1/95 and there were no failures identified. MST-11.11 was completed on 4/90,2/92,4/94 and 1/95 and there were no failures identified.
The system utilizes two positive displacement pumps capable of delivering greater than 50 gpm at a head of greater than or equal to 1275 psig. The pumps are tested monthly during normal plant operation. The pumps are tested for operability by surveillances ST-
! 6B and ST-6D, the surveillance records yield the following results. ST-6B was completed
- on 6/83,2/85,1/87,9/88,4/90,2/92,4/94 and 1/95 and there were no failures
- identified. ST-6D was completed on 6/83,2/85,1/87,9/88,4/90,2/92,9/92 and 1/95
! and there were no failures identified.
l The relief valves in the system protect the piping and pumps, which are nominally t
designed for 1500 psig, from over pressure. The valves are only used and pressurized
. during the brief system testing periods. The valves were tested for operability by
! completed on 6/83,2/85,1/87,9/88,1/90,4/90,2/92,9/92,4/94 and 1/95 and there ,
were no failures identified. Surveillana ST-6C has been deleted and MP-59.07 (Ref. 25) !
will take its place until a MST is developed.
f The system utilizes Sodium Pentaborate solution for the negative reactivity addition to !
the reactor. To protect the system piping against solution precipitation, the solution is l kept at least 10*F above solution saturation temperature. His is accomplished by a tank Page 3 i
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, 24 MONTH OPERATING CYCW I l
- SLC SURVEIII ANCE EXTENSIONS j heater and a piping heat tracing system. Temperature indication and alarms for the l
- system annunciate in the control room. If a problem were to develop, the above design i features would provide ample indications for plant personnel to remedy the situation.
The system temperature is checked daily and provides assurance that the system is '
L maintained as required by Technical Specifications. Plant temperature instrumentation
- installed on the SLC tank is capable of being calibrated (Ref.19) while the unit is at _ t power, technicians monitor the tank temperature during the calibration process. There is '
j no hardship in testing or calibrating these instruments at any time and the calibrations
- are not cycle dependent. Keeping these instruments on an 18 month calibration
- frequency will not be a burden to plant operation or personnet Based on past
- calibration history, the temperature instrumentation will not support frequency extension.
l Therefore, the calibration frequency will not change.
t :
_ Once the solution has been prepared in the tank, the concentration of boron will not :
- change unless more boron or water is added. Level indications and alarms are used to j detect whether the solution volume has changed, which might be indicative of a solution
! concentration change. The actual tank level is checked daily via two independent means l and would detect instrument level changes due to water addition, water evaporation or l i system leaks. The calibration (Ref. 20) of these instruments on an 18 month frequency ]
l will not be a burden to plant operation or personnel Based on past calibration history,
! the level instrumentation will not support frequency extension. Therefore, the calibration frequency will not change. The level instruments are capable of being i calibrated while the unit is at power the calibration frequency of 18 months is not cycle dependent.
l i- The SLC system is designed with two (2) check valves installed to isolate the reactor from the SLC system. These two check valves are presently tested on a refueling basis.
! (ST4D). The valves are tested for operability by surveillance ST4D, the surveillance l records yield the following results. ST4D was completed on 6/83,2/85,1/87,9/88,
- 4/90,2/92,9/92 and 1/95 and there were no failures identiSed. 'Ibese valves are used
- ' for containment isolation purposes and can only be leak rate tested when the reactor is
! in cold shutdown. In addition to the isolation requirement, the valves must also open to j provide a Dow path to the reactor during SLC initiation. This function can only be l tested during cold shutdown by injecting flow into the reactor. Therefore, this test is being extended to a 24 month freguency.
2 V. Summary and Conclusions To support the 24 month fuel cycle, changes are proposed to the SLC surveillance test intervals for the following system functional tests (See Table 1):
+ Recirculation Flow Test (ST4B) l + Explosive Valve Tests (ST4D) l Page 4 l
_ _ . ~ _ . _ _ __ . _ . . _ _ _ _ . _ . _ _ _____ _
s 24 MONTH OPERATING CYCLE
- i SLC SURVFITI ANCE EXTENSIONS I + Demineralized Water Injection Test (ST4D)
- + Relief Valve Setpoint Test (ST4C/MP-59.07) i
+ Explosive Valve Inspection Test (MST-11.11) t i SLC instrument calibrations and functional tests (Ret S ed 20) which are performed once every operating cycle can continue to be performed on an 18 i month schedule without an outage or being a burden to plant operation or safety.
4 VI. References ,
- 1. James A. FitzPatrick Nuclear Power Plant, Maintenance Department Preventative . ,
Maintenance Schedule. -
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- 2. James A. FitzPatrick Nuclear Power Plant, I&C Department Maintenance Program Master Schedule.
! 3. Operational Occurrence Report Imgs from 1986 to 1990.
! 4. James A. FitzPatrick Nuclear Power Plant, Technical Specifications.
l 5. James A. FitzPatrick Nuclear Power Plant, Updated Final Safety Analysis Report, 2 Section 7.2.
- 6. Flow Diagram, Standby Uquid Control System, DWG. No.11825-FM-21A.
t l 7. Operating Procedure OP-17, Standby Uquid Control System.
I
- 8. Operations Surveillance Test Procedure ST4A, Standby Uquid Control Pump 4
Functional Test.
P 4 9. Operations Surveillance Test Procedure ST4B, Standby Uquid Control
! Recirculation Test.
i
- 10. Operations Surveillance Test Procedure ST4C, Standby Uquid Control Relief ,
Valve Test (IST).
- 11. Operations Surveillance Test Procedure ST4D, Standby Uquid Control Initiation and Demineralized Water Injection into Reactor Vessel Test (IST).
- 12. Operations Surveillance Test Procedure ST4H, Standby Uquid Control Pump Inservice Test (IST).
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, 24 MONTH OPERATING CYCI.E
.t SLC SURVETII ANCE EXTENSIONS
- 13. Maintenance Procedure MP-11.1, Standby Uquid Control Pump Maintenance.
- 14. Maintenance Procedure MP-11.2, Standby Uquid Control Pump Maintenance.
- 15. Maintenance Procedure MP-11.3, Standby Uquid Control Safety Relief Valve Repair.
- 16. Maintenance Procedure MP-11.4, Standby Uquid Control Accumulator Repair.
- 17. Maintenance Procedure MP-11.10, Standby Uquid Control Explosive Valve Inspection and Replacement.
- 18. Maintenance Surveillance Test MST-11.11, Standby Uquid Control Explosive Valve Inspection and Replacement.
- 19. Instrument Surveillance Procedure ISP-82-1, Standby Uquid Control System Temperature Instrument Calibration.
- 20. Instrument Surveillance Procedure ISP-82, Standby Uquid Control Tank Level Instrument Calibration.
- 21. Instrument Maintenance Procedure F-IMP-11.1, Standby Uquid Control Pressure Instrument Calibration.
- 22. Instrument Maintenance Procedure F-IMP-11.2, Standby Uquid System Pressure Instruments Test and/or Calibration.
4 23. NYPA Memorandum G. L Rorke to R. Penny, dated January 6,1992, j documenting the results of a GE calculation showing SLCS capability for a 24
. month power uprate cycle.
- 24. SP-01.04, SIE Sampling and Analysis procedure.
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ATTACHMENT 1 TABLE 1 t
STANDBY LIQUID CONTROL SYSTEM SURVEILLANCE TEST CHANGES COMPONENT (S) PROCEDURE TS SECTION CHANGE Pumps ST-6B 4.4.A.2 18M to 24M 11 P-2A ST-6D 18M to 24M 11 P-2B Safety Valves 4.4.A.2 11 SV-39A ST-6C 18M to 24M 11 SV-39B MP-59.07 Check Valves ST-6D 4.4.A.2 18M TO 24 M 11 SLC-16 11 SIL-17 Explosive Valves MST-11.11 4.4.A.2&3 18M TO 24M 18M TO 24M j 11EV-14A ST-6D
! 11EV-14B Instruments (Temperature) ISP-82.1 4.4.C3.a Once per Cycle to 18M
, 11 TS-50 11 TS-59 3
11 TIC-60 11 TIC-48 (Level) ISP-82 4.4.C3.a Once per cycle to 18M 11 LT-45 l
11 LI-46 l 11 LI-66 l
11 LS-47 ;
11 LS-70 EPIC point A-1112 l I
1 2
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. . 24 MONTH OPERATING CYCLE i SLC SURVEILLANCE EXTENSIONS !
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ATTACHMENT 2 1 I
TECH SPEC MARK-UPS l
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JAntPP
- 3.4 LIhlTING_ Cot'DITtoteS ron OPERAT10tl 4.4 SuaVElt. LANCE _ REQUIREMENTS 3.4 STANDBLLIQUID_ CDNTRQL.SYST_EM 4.4 STAND 9Y J.IQu1D_CouTRot, STSTpg OPElICBhilltre Applissbility .
Applies to the operating status of the Standby Liquid AppIles to the periodic testing requirements for the Control System.
Standby Liguld Control System. ,
Ott}tstiva Objgstive To assure the availability of a system with the capability to shut down the reactor and maintain the To verify the operability of the Standby Liquid Control System.
shutdown condition without control rods. .
SPetilisations Specillgation:
A. Herpal_Dperating A. Mergnal Operation During periods when fuel is in the reactor and' The operability of the stoneer Laguna centret e stem Prior to startup from a cold condition, the r .
Standby Liquid Control System shall be operable shall be verified by performance of the following
-tests:
except as specified in 3.4.B below. This system need not be operable when the reactor is in the 1. At legat gagg att month -
cold condition, all rods are fully inserted and Specificatica 3.3.A is met.
Dominera11 sed water shall be recycled to the
[ i test tanit.
[ Pmmy minimum flow rate of 50 gym l shall be verified against a system head of.E 1,275 psig. ~
2 at Annat east dutlas mash operating crsin Manually laitiate the system, except the emplosive valves and t
Amendment No. 1I6 105 4 5
JAFNPP 4.4 (cont'&f pump solution in the recirculation path.
Explode one of three primer assembhes manufactured in same batch to verify proper function. Then install the two remaining primer assemblies et the same batch in the explosive valves.
Demoneralized water shall be intected into the reactor vessel to test that valves (except explosive valves) not checked by the recirculation test are not clogged Test that the setting of the system pressure relief valves is between 1,400 and 1,490 psig.
," 3. Disassemble and inspect one explosive valve so that it can be established that the valve is not clogged. Both valves .
shall be inspected in the course of two operating cycles.
B. _ Operation with inoperable COiripci&ds B. Operation with inoperable Components
, g . ,
From and after the date that a redundant coirpcr&4 is made or cGiripGr&4 shall be verified to be operable immediately and found to be inoperable, Specification 3.4.A shall be considered g daily thereafter, fulfilled, and continued operation permitted, provided that:
- 1. The component is returned to an operabic condition within 7 days.
Amendment No. ;)6,134 148 106
I JAFNPP 3.4 (Cont'd) 4.4 (Cont'd) 1 C. Sodern Penteborate Solution C. Sodium Panteborate Solutior -
The standby bquid control solution tank shell contain a boron The eveilobility of the proper boron bearing solution shell be i bearing solution with a minimum enrichment of 34.7 stom verified by performance of the following tests:
percent of B-10 that satisfies the volume-concentreteen requirements of Fig. 3.4-1 et all times when the Standby 1. At least once cor month -
, Liquid Control System is required to be operable end the solution temperature including that in the pump suction piping Baron concentration sheE be determined. In addition, the shall not be less then the temperature presented in Fig. 3.4-2. ,
baron concentration shall be determined any time water l Tank hester and the heet tracing system shell be oposable e, e or ennched sodium ponteborate is added or if the solution l whenever the SLCS is required in order to maintain solution temperature drops below the limits specified by I i temperature in accordance with Fig. 3.4-2. If these Fig. 3.4-2.
requirements are not met, restore the system to the above limits within eight hours or take action in accordance with 2. At least once cor dev - <
Specification 3.4.D. =
Solution volume and the solution temperature shell be checked.
- 3. At loest once nor onoraten cycle -
- e. The temperature and level elements shell be calibrated. !
~ ;
4./ Enrichment of B-10 (in atom percent) shall be checked.
$. AT LW MUT /EY /8 MYES D. If specifications 3.4.A through C are not met, the reactor shell D. Not Used l l be in at least hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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Amendment No.1/I ,192 107 i
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. . . - . - ..___ . __ _ . _.--m _ -. _ - . _ _ _ _ . _ _ . - - . - - . __ _ _ . __ _ . . . . _ _ _ . _ _ _ _ . _ . _ _ . - - - _ _ _
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JAFnPP
- 3.4 and 4.4 3Asgg The techalcal specifications assure that the A. Her_ mal Operation slaimum injecting time for the SLC System is 44 -*
salmetes and maximum lajection time 96 minutes, The design objective of the Standby Liquid thus meetleg the plaat design basig. In addition to Control System is to bring the reactor from meeting its original design basis, the system full power to cold, menon-free shutdoma must aise satisfy the Anticipated Transiest assuming that no control rods can be Without Scram (ATWS) Rule, le CFR 50.62 paragraph (c) (4).
laserted. To do this, the Steedby Liquid Control System is designed to inject a questity of boron which produces a mialmenn The A7W5 Rule requires a mialmum flow capacity concentration equivalent to See pga of and boros content equivaleet in control capacity natural boros in the reactor core. Sim to 06 gallens per minute of 13 melght percent hundred and sixty pre boros concentration in sodium poetaborate seletloa. The " equivalent la the reactor core is required to bring the control capacity" wordisq was clarified la reactor from full poner to a subcritical Generic Letter 85-03. Equivalence ces be condition considerlegt obtained by lacreasing the flow, boros
' concentration, or boros enrichment. For the <
o the reactivity lasettlom due to temperature FitsPatrick plant, the rule is met by using boron enriched to 34.7 atos percent boree-10 and a decrease caused by changing water density, pumping rate of 50 gym. The method used to show ,
o decay of meson poisoning
- o uncertaintles and biases in the analysos and equivalence with 10 CFR 50.62 is described in NEDE - 31094 - P-A o 25% margia for potentially leperfect mining of the sodians pentaborate solution la the >
reactor water. R/19.8 x C/13 a M251/M z 9/84 I where The design basis of the SIES requires that injection be completed la a time perled so less than 23 minutes and so greater than 125 E = beroe serictement = 34.7 stem %
minutes. The upper time limit (125 min) for 0 = stcs flew rate = 50 gym M=
complete lejection of the sodlus pentaborate mass of water la reactor vessel and recirculation system at het rated condition solutlos was selected to override the rate of 491,700 lbs. for FitsPatrick plant reactivity insertion due to cooldown of the M251 =
reactor following the menos poison peak. The mass of water in vessel and recirculation lower time limit (23 min) is based on the- system at bot rated condition (628,300 need to allow adequate mixing, so the boroe C=
Ibe.) for 251 - lach diameter vessel plant does not circulate in uneven concentrations sodium pentaborate solution concentration that could cause local power fluctuations. *
(weight percent) greater than or equal to 10 percent Amendment No. f(,116 108
. . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ _ _ __ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ m. _ _ _ _ _ _ _ _ _ > _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ - -__ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _
b.
'JAFNPP ATWS requirements are satisfied at all concentrations above 10 The relief valves in the Stan&y bquid Control System protect weight percent for a minimum enrichmerd of 34.7 atom percent of B-10. the system pipeng and positive displacement pumps, which are ;
nommally desegned for 1,500 psig, from overpressure The >
Figure 3.4-1 shows the permissible region of operation on a presswa rM vh hge M to h stan@y W sodium pentaborate solution volume versus concentration corm pump Moon M graph. This curve was developed for 34.7% enriched B-10 and B. Operation with inoperable Components a pumpeng rate of 50 gpm. Each point on this curve provides a mmimum of 600 ppm of equivalert natural boron m the reactor vessel upon ingection of St.C solution. At a solution volume of edW%WWmMh needed for operation. If one circuit is inoperable, there is no 2200 gallons, a weight concentration of 13 % sodum thrW to Wh < W, W e opam .
pentaborate, enriched to 34.7% boron-10 is needed to meet may conunue during W Assurance that h remaining i shutdown requirements. The maximum storage volume d the ,gg g g, % g, m g solution is 4780 gallons which is the not overflow volume in the E" E" " ,
SLClank. -
C.
i Sodum Pentaborate Solution Boron concentration, isotopic enrichment of boron-10, soluuon To guard against pr*%, the solution, includng that in 'the tempere.ture, and volume are checked on a frequency pump suction piping, is kept at least 10'F above saturation adequale to assure a high r=f of operation d the system temperature. Figure 3.4-2 shows the saturation temperature !
should it every be required. Experience with pump operability inclueng 10"F mergin as a function of sodum pentaborate indicates that monthly testing is adequate to detect if failures solution concentration. Tank heater and host tracing system ,
have occurred.
are provided to aneure eu,,f _,0. with this requirement. The The only practical time to test the Standby Liquid Control the N MW W h M h and '
System is during a refueling outage and by initiation from local heat tracing system are estatfched based on the =W stations. Components of the system are checked periodically e
h T w h W @ M h fw h as described above and make a functional test of the entire in h m m W PM is !
system on a frequency of more than once each refueling n a kequency to asswa a high h._ ._ ,. d opwaNon outage unnecessary. A test of explossve charges from one of the system should it ever be required.
manufacturing batch is made to assure that the charges are ;
satisfactory. A continuous check of the firing circuit continusty is provided by pilot lights in the control room.
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Amendment No. ;3ti. Mf5 148 '
trn N W=r--f.v &- ye*-- - y ,,v awwvs - wy1- w. _ _ - . __m ____m
= +'-A _+_w- ___m a -- . _ _ _ _ _ _ .
_ _ m ._ _ _ .
JAFNPP /
Once the solution is prepared, boron concentration does not vary, unless more enriched sodium penta-borate or more water is added. Eevel ladications and alarare ladicate whether the solution voltune has changed which might ladicate a possible solution concentration change. The test laterval .
has been estaL11shed considerlag these factors.
Boros enrichment (3-10 atos percent) does not very with the addition of enriched sodium pentaborate material or water to the SEE task provided 34.7% enriched (5-10 atose percent) is added. Therefore, a check once per operatlag cycle is adequate to ensure proper enrichment.
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FIG.3.4-1 ,
j SODIUM PENTABORATE SOLUTION (MINIMUM 3 VOLUME CONCENTRATION REQUIREMENTS.
4 A"inntaarit No. 116 110 1
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Amendment 116 l