ML20211B833
| ML20211B833 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/30/1986 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | Walker R PUBLIC SERVICE CO. OF COLORADO |
| Shared Package | |
| ML20211B839 | List: |
| References | |
| TAC-53417, NUDOCS 8606120078 | |
| Download: ML20211B833 (25) | |
Text
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+ Ig UNITED STATES i
[ ># g NUCLEAR REGULATORY COMMISSION L .. j W ASHINGTON. D. C. 20555
% ,,,,,* May 30, 1986 Docket No. 50-267 ,
1 Mr. R. F. Walker, President Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840
Dear Mr. Walker:
SUBJECT:
FORT ST. VRAIN - DRAFT SAFETY EVALUATION REPORT (SER) -
TECHNICAL SPECIFICATION CHANGES FOR CATEGORY I AND II INSERVICE INSPECTION AND TESTING PROGRAM (ISIT) ,
SURVEILLANCE REQUIREMENTS
References:
- 1. O. R. Lee (PSC) letter to H. N. Berkow (NRC), Proposed Technical Specification Changes " Inservice Inspection and Testing Requirements," November 27, 1985.
- 2. D. R. Hunter (NRC) letter and enclosure to 0. R. Lee (PSC),
" Evaluation of Technical Specification Changes for Inservice Inspection and Testing Requirements," August 27, 1985.
This letter transmits our draft SER (Enclosure 2) and marked up pages of acceptable Technical Specification changes (Enclosure 1) pertaining to the Category I and II ISIT at Fort St. Vrain (FSV). This draft SER evaluates nine of the 14 surveillance requirements submitted by Public Service Company of Colorado (PSC) in Reference 1. We find these nine surveillance requirements (one Category I and eight Category II requirements) acceptable subject to the enclosed changes. The five remaining surveillance requirements, for which additional information and review are needed, are:
l 1 SR 5.2.7 - Water Turbine Drive Surveillance 2 SR 5.2.21 b) - ACM Transfer Switches, Valves, and Instruments Surveillance 3 SR 5.4.4 - PCRV Cooling Water System Temperature Instruments Surveillance
- 4) SR 5.5.3 - Reactor Building Exhaust System Surveillance
- 5) SR 5.7.2 - Fuel Storage Facility Surveillance The first four of these surveillance requirements are Category II and the fifth is Category III. We are deferring action on these five surveillance requirements because they are being reviewed as part of the FSV Technical Specification Upgrade Program (TSUP). We have given these five surveillance requirements high priority in the TSUP review so that, if approved, they may be directly incorporated into the appropriate category (Category II and III)
Technical Specifications.
In Reference 2, we recomended that PSC follow the guidance of the ASME Code,Section IX, Division 2, wherever practical and reasonable. In Reference 1, PSC committed to use the ASME Code in the development of a detailed B60612OO7P 860530 l PDR ADOCK 05000267 P PDR
- - .= . . -. - ._ _ . _ . - _ _ . -
l Surveillance Procedures document. In order to reinforce this comitment, and to document the use of the ASME Code, we have added reference to the ASME Code to the affected sections of the Technical Specifications. These references to the ASME Code should be incorporated into the current plant Technical Specifications.
In addition to the five unreviewed Category II and III surveillance requirements mentioned above, the balance of the Category III and IV surveillance requirements remains outstanding. Because of the lower priorities of these Category III and IV surveillance requirements, they will be reviewed as part of the FSV TSUP.
This is a change from our originally agreed upon ISIT upgrade plan described in the November 30, 1979 letter from J. K. Fuller (PSC) to S. A. Varga (NRC).
In Reference 2, we stated that before we can consider PSC to be in compliance with its 1972 comitment on ISIT, PSC must review the listing of the surveillance requirements given in all four priority categories, make modifications if needed, and then certify to the program's completeness. In this regard, PSC should reconsider the discussion and recomendations contained in the December 22, 1981 document, " Review of the Public Service Company of Colorado Proposed Inservice Inspection Program," prepared by ASTA, Inc. This document contains several recommendations for ISIT at FSV. While we are aware that PSC has reviewed the ASTA document previously, we recomend that PSC reconsider this document in light of recent developments at FSV concerning: corrosion due to moisture ingress; the commitments of the TSUP (regarding PCRV depressurization); and our coments in Reference 2 with respect to visual inspections of the lower plenum. We request that you _
incorporate the changes and recomendations to the nine surveillance requirements contained in the enclosed draft SER and resubmit your proposed :
Technical Specification changes within 45 days of the date of this letter. >
If ycu have any questions or coments regarding the above, please contact Charles Hinson, NRC Co-Project Manager for your facility, at (301) 492-7930.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely,
- erbert N. Berkow, Director I
Standardization and Special Projects Directorate Division of PWR Licensing-B
Enclosures:
- 1. Approved Technical Specification Changes
- 2. Draft Safety Evaluation Report cc w/ enclosures:
See next page l
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. Mr. R. F. Walker Public Service Company of Colorado Fort St. Vrain cc: !
Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 30220 Denver, Colorado 80201 Mr. David Alberstein, 14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc. Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. L. W. Singleton, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Fort St. Vrain Nuclear Station Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. 0. Box 640 Platteville, Colorado 80651 Kelley, Stansfield & 0'Donnell Public Service Company Building Room 900 550 15th Street Denver, Colorado 80202 Regional Administrator, Region IV U.S. Nuclear Regulatory Consnission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1800 Lincoln Street Denver, Colorado 80203 8
e i ENC 1.05 uke ,1 Acceptabi e Technical Specifica'icn Changes
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Fort St. Vrain el Technical Specifications
- Amendment Page 5.2-1 5.2 PRIMARY COOLANT SYSTEM - SURVEILLANCE RECUIREMENTS ,
Applicability Applies to the surveillance of the primary (helium) reactor coolant system, excluding the steam generators, ,
l and to the surveillance of the reactor auxiliary systems.
Obiective To ensure the capability of the components of the primary reactor coolant system to maintain the primary reactor $
coolant envelope as a fission product barrier and to '
ensure the capability to cool the core under all modes of
, operation.
Specification SR 5.2.1 - PCRV and PCRV Penetration ;
Overpressure Protection Surveillance (
al Each of the two overpressure protection assemblies protecting the PCRV shall be tested at intervals not to exceed five years, on an alternating basis, with one overpressure protection assembly tested during each refueling cycle.
The PCRV safety valve containment tank closure bolting shall be visually examined for absence of surface ;
defects when the tank is opened for the abov4 testing. f Tank closure flange leak tightness shall be determined ,
following tank closure. SR 5.2.1.a shall be ,
implemented per Is! criterion C.
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Fort St. Vrain $1 Technical Specifications Amendment Page 5.2-16 and at the same intervals as the turbine water removal pumps and shall be calibrated annually.
Basis for Specification SR 5.2.7 The circulator water turbine drives are normally operated during an extended shutdown. Therefore the specified surveillance requirements are adequate to ensure water turbina operability, j Specification SR 5.2.8 - Circulator Bearing Water Pumps And Makeup Pump Surveillance 1
l The circulator bearing water pumps, bearing water makeup
, l pumps, and associated instruments and controls shall be tested as follows
! a) The Normal Makeup Pump shall be operated in the l recycle s4de every 92 days.
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b) The Eeergency Makeup Pump shall be functionally tested l l every 92 days.
l SR 5.2.8b shall be implemented per ISI criterion G.
c) The associatad instru;nents and controls shall be functionally tested in conjunction with an at the intervals specified in parts a) and b) above, and calibrated annually.
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Fort St. Vrain $1 Technical Specifications Amendment Page 5.2-17 l d) Each Bearing Water Pump, and the associated l instruments and controls shall be functionally tested l at each scheduled plant shutdown. In addition, the l instruments shall be calibrated annually, or at the l next scheduled plant shutdown if they were not l calibrated during the previous year provided that the l surveillance interval does not exceed 18 months.
l SR 5.2.3d shall be implemented per ISI Criterion F.
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Fort St. Vrain fl Technical Specifications Amendment Page 5.2-18 Basis for Specification SR 5.2.8 l The bearing water pumps and bearing water makeup pumps are l required to operate for safe shutdown cooling of the l reactor under accident conditions described in FSAR
! l Section 10.3.9. The specified tests and testing intervals l are sufficient to ensure adequate pump operation for the l performance of their required safety functions.
l Performance capability of the bearing water pumps is l verified by normal operation. Performance capability of l the normal bearing water makeup pump is verified when l operating the pump in the recycle mode. Performance l capability of the emergency bearing water makeup pump is l verified when testing the associated check valves as l required per SR 5.3.4.
l Specification SR 5.2.9 - Helium Circulator Bearing Water A-cumulators Surveillance The helium circulator bearing water accumulators, instrumentation, and controls shall be functionally tested l every 92 days and calibrated annually.
l SR 5.2.9 shall be implemented per ISI criterion E.
Basis for Specification SR 5.2,9 }
Helium Circulator bearing water is normally supplied from the bearing water system and is backed up by the backup bearing water system supplied from the Emergency Feedwater I
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Fort St. Vrain el Technical Specifications Amendment Page 5.2-19 Header. In the event of a failure in both of these systems, the water stored in the bearing water accumulators is adequate to safely shut down both helium l circulators in a loop. The specified tests and testing l intervals are sufficient to ensure operability of the l - accumulator controls, should they be called upon to l perform their required function.
Specification SR 5.2.10 - Fire Water System / Fire s
SuppressionWaterSystemSurveillsSe
/ A a) The fire water system shall be verified operable as follows:
- 1) The motor driven and engine driven fire pumps shall be functionally tested monthly. The associated instruments and controls shall be functionally tested monthly and calibrated annually.
- 2) The diesel engine fuel shall be inventoried monthly and sampled and tested quarterly.
- 3) The diesel engine shall be inspected during each refueling shutdown.
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- 4) The diesel engine starting battery and charger shall be inspected weekly for proper electrolyte level and overall battery voltage. The battery electrolyte shall be tested quarterly for proper specific gravity.
Fort St. Vrain el Technical Specifications Amendment Page 5.2-20
- 5) The batteries, cell plates, and battery racks, shall be inspected each refueling cycle for evidence of physical damage or abnormal degradation. The battery-to-battery and terminal connections shall be verified to be clean, tight, free of corrosion, and coated with anti-corrosion
, material each refueling cycle.
t b) The fire suppression water system shall be verified operable as follows:
- 1) Monthly by verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
- 2) Semi-annually by performance of a fire suppression water system flush.
- 3) Annually by cycling each testable valve in the fire suppression water system flow path through at least one complete cycle of full travel.
- 4) Each refueling cycle by performing a fire suppression water system functional test which includes simulated automatic actuation of the system throughout its operating sequence 4 ands (a) Verifying that each automatic valve in the flow path actuates to its correct position.
Fort St. Vrain el Technical Specifications Amendraent Page 5.2-2Ca (b) Verifying that each fire water pump develops j at least 1,425 gpm at a system head no less l than 119 psig. SR 5.2.10.b4b shall be l implemented per ISI Criterion G.
(c) Cycling each valve in the flow path that is not testable during plant operation through nt least one complete cycle of full travel.
(di verifyang that each firs water pump starts sequentially to maintain the fire suppression water system pressure at greater than or equal l to 275 feet water gauge.
- 5) Each three years by performing a flow test.
Basis for Specification SR 5.2.10 The fire water pumps are required to supply water for fire suppression and safe shutdown cooling. The specified testing interval is sufficient to ensure proper operation of the pumps and controls. The motor driven pump routinely operates intermittently.
The operabilityI of the fire suppression water system l
ensures that adegoate fire suppression and emergency safe shutdown cooling capability is available. The specified f
testing interval is sufficient to ensure proper operation of the system when required.
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a Fort St. Vrain #1 Technical Specifications
' Amendment Page 5.2- 26 shutdown if these valves have not been tested during the previous year.
SR 5.2.16.d shall be implemented per ISI Criterion B.
ei The check valves on the HTFA purge lines shall be tested at five calendar year intervals.
SR 5.2.16.e shall be implemented per ISI criterion B.
f) The check valves which are part of the HTFA or refueling penetrations shall only be tested when such a penetration is open for refueling or maintenance, if the check valves have not been tested in the last five years.
SR 5.2.16.f shall be implemented per ISI criterion B.
l g) Each helium purification cooler well closure shall be l leak tested, and the well pressure monitoring l instruments shall be calibrated, once during each l refueling cycle. In addition, the instruments and l controls. used to automatically isolate the l purification system shall be functionally tested at 9l the same frequency. h l SR 5.2.16g shall be implemented per ISI Criterion F.
, Basis for Specification SR 5.2.16 l
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1 Fort St. Vrain $1 Technical Specifications
- Amendment Page 5.2-27 ,
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l The interval specified for determining the actual primary and secondary closure leakage is adequate to assure compliance with LCO 4.2.9.
1 In ,the determina~ tion of closura leakage at the reference differential pressure, laminar leakage flow. shall be conservatively assumed, therefore in correcting the determined closure leakage to reference differential pressure, the ratio of the reference differential pressure, and test differential i
pressure shall be used.
The interval specified for functional testing and calibration of the instrumentation and alarma monitoring the penetration closure interspace pressurization gas flow will assure sensing and alarming any change in pressurization gas flow.
The interval specified for functional test and: calibration of the instrumentation and alarms monitoring the core support floor and columns will assure sensing and alarming any change in their structural integrity.
The interval specified for valve testing is adequate to assure proper valve operation when isolation of the closure auxiliary piping is required.
l The interval specified for testing the helium purification 1 cooler wells is adequate to verify the well integrity, as well l as that of primary coolant boundary components located therein.
Fort St. Vrain 91 ,
Technical Specifications I
. Amendment '
Page 5.2- 31 i
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l Specification SR 5.2.21 - ACM Transfer Switches, Valves, and l Instruments Surveillance l al Those valves and transfer switches that must be manually l positioned for actuation of the Alternate Cooling Method (ACM) l mode of cperation shall be tested for operability by partial l stroking of the valve twice annually at- an interval between l touts to be not less than four (4) months, nor greater than l eight (8) months. A full functional test shall be performed l annually, or at the next scheduled plant shutdown if such test l was not performed during the previous year provided that the l surveillance interval does not exceed 18 months. SR 5.2.21a l shall be implemented per ISI criterion F.
l b) Local indic ors for the he um purification / dryer in e't3 l temperatu , for the helium rification pumpdown line pressure
! l and c the reactor ant cooling water rge tank co r gas
/ l l pr sure shall be librated at ea plant shu down for I l refueling. SR 5. .21b shall be imp mented per IS CriterionF.}
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] 3 asis for Specification SR 5.2.21 l In the event that the ACM mode of operation must be implemented, it l is necessary to manually position valves (manual valves as well as l valves which would normally be pneumatically or electrically l operated) and to manually reposition electrical transfer switches.
([ Local instruments allow sy em monitoring ring the depres f'rization l phase of e PCRV and ring the subs ont cooling ase of the l react . The spec led tests and sting intervals re sufficient to l as re j
& delede sec %$ no+ approved
Fort St. Vrain $1 Technical Specifications Amendment Page 5.2-32 l
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l operabilit of these com nents should hey be calle upon for '
l perfo nee of their re ired safety f tions. I J
Specification SR 5.2.22 - PGX Graphite Surveillance PGX graphite surveillance specimens shall be installed into five (5) bottom transition reflector elements of the Fort St. Vrain core to provide a means for assessing the condition of the PGX graphite support blocks during operation of the reactor. These specimens (16 per reflector element) will be installed in reflector elements as indicated in Table 1 and will be removed at subsequent refueling intervals, as indicated in Table 1, unless the progressive examination of the specimens dictate otherwise.
Upon removal, these specimens will be subjected to examination, and compared with laboratory control specimens in evaluating oxidation rates, oxidation profiles, and general dimensional characteristics.
i The results of these tests and examinations shall be utilized to I assess the condition of the PGX core support blocks in the reactor l and shall also be utilized to modify, as necessary, the planned l
l removal of subsequent PGX surveillance specimens.
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, The results of these examinations shall be submitted to the N C staff 1
I for review.
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l Fort St. Vrain #1 Technical Specifications 1 Amendment Page 5.2-34 Specification SR 5.2.23 - Firewater Rooster Pump Surveillance Each firewater booster punp shall be tested annually by providing motive power to one water turbine drive in conjunction with the performance of SR 5.2.7. In addition each pump shall ce functionally tested quarterly. The associated instruments and controls shall functionally be tested quarterly and calibrated annually.
Basis for Specification SR 5.2.23 During accident conditions described in Final Safety
. Analysis Report, Section 14.4.2.1, one of the firewaEer booster pumps and one firewater pump are required to j provide adequate core cooling. The specified testing interval is sufficient to ensure proper operation of the pump and associated controls.
l Specification SR 5.2.24 - Reactor Auxiliary Cooling Water l Systems Surveillance l The reactor auxiliary cooling water systems shall be l l tested as follows:
l l a) The circulating water makeup pond minimum inventory shall be verified daily. The pond level instrumentation shall be functionally tested monthly and calibrated annually.
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Fort St. Vrain il l Technical Specifications l Ameninent Page 5.2-34a l b) Each circulating water makeup pump and the associated l instruments and controls (including firewater pump pit l instruments and controls) shall be functionally tested l monthly. In addition, the instruments shall be l calibrated, ard the pump performance capability (flow l and head) and mechanical condition' (vibration l amplitude and berring temperature) shall be verified, l annually or at the next scheduled plant shutdown if Q this was not performed during the previous year.
l SR 5.2.24b shall be implemented per ISI Criterion F.
c) The valve lineup of the flow path between the circulating water storage ponds and the fire water pump pits shall be verified correct monthly.
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Fort St. Vrain $1 Technical Specifications Amendment Page 5.2- 34b l d) Alignment and settlement of the circulating water makeup l pond embankments shall be verified at five calendar year l intervals. The embanknents and the water structures shall l be examined at the same intervals for abnormal erosion, l cracks, seepage, leakage, accumulation of silt or debris l (as applicable) which might indicate a deterioration of l structural safety or operational adequacy of the storage l ponds. SR 5.2.24d shall be implemented per ISI Criterion l F.
l e) Each service water pump and the associated instruments and l controls shall be functionally tested monthly. In l addition, the instruments shall be calibrated, and the l pump performance (flow and head) and mechanical condition l (vibration amplitude and bearing temperature) shall be l verified, annually or at the next scheduled plant shutdown l if this was not performed during the previous year h l SR 5.2.24e shall be implemented per ISI Criterion F.
l f) Each reactor plant cooling water pump and the associated l instruments and controls shall be functionally tested l monthly. In addition, the instruments shall be l calibrated, and the pump performance (flow and head) and l mechanical condition (vil ration amplitude and bearing l temperature) shall be verified, annually or at the next l scheduled plant shutdown if this was not performed during h iD the previous year. SR 5.2.24f shall be implemented per l ISI Criterion F.
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Fort St. Vrain $1 Technical Specifications
. Amendment Page 5.2-34c l g) Each purification cooling water pump and the associated l instruments and controla shall be functionally tested monthly.
l In addition, the instruments shall be calibrated, and the pump l performance (flow and head) shall be verified, annually or at l the next scheduled plant shutdown if this was not performed.
l during the previous year. SR 5.2.24g shall be implemented per
--> l ISI Criterion F. h l h) Instruments and valves, used for automatic isolation of portions l of the purification cooling water system and the reactor plant l cooling water system, that may be required for confinement of l reactor coolant and that are capable of being tested, shall be
, l tested for operability by partial stroking or full stroking of l the valves, as ' appropriate, twice annually at an interval l between tests to be not less than four (4) months, nor greater l than eight (8) months. Additionally, these instruments and l valves shall be functionally tested annually or at the next l scheduled plant shutdown if such test was not performed during l the previous year, ovided that the surveillance interval does h ---> l not exceed 18 months. R 5.2.24h shall be implemented per ISI Criterion F.
l Basis for Specification SR 5.2.24 l The reactor auxiliary cooling water systems (including water makeup l
l system, service water system, reactor plant cooling water system, and l purification cooling water system) are required to operatef for l reactor cooling under h dd) ~ "The ddnite) Sweecitlture refairemo,t5S N b e i., ewer al ^CCcM 0 M
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Fort St. Vrain el Technical Specifications
' Amendment Page 5.2- 34d l postulated loss of forced circulation cooling accident conditions.
l Except for the purification cooling water system, they are also l required for safe shutdown cooling of the reactor under other l postulated accident conditions. The circulating water makeup system i also s2pplies water for fire suppression. These systems routinely l operate during normal plant operation. Rcutine operation in l conjunction with the specified tests and testing intervals are l sufficient to ensure adequate system and/or component operation for j the performance of their required safety functions.
l Measuring the position of survey markers and evaluating the changes l in position of these markers will allow changes in embankment l alignment and settlement to be determined, as well as their possible l impact on the structural integrity of the storage pond. Examination l cf the embankments and of the water structures will provide for an l additional ve:1fication that no phenomenon occurs which might be l detrimental to the ability of the storage pond to perform its safety l function. Measurement of the silt accumulation in the storage pond l will allow a verification that the minimum water inventory required l by LCO 4.3.5 is available for Safe Shutdown Cooling of the reactor.
l The interval specified for instruments and valves is adequate to l assure their automatic isolation function, if degradation were to l occur in the integrity of the reactor coolant boundary, redulting in l primary coolant leakage into the system.
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Fort St. Vrain #1 Technical Specifications
. Amendment Page 5.3-6 Specification SR S.3.4 - Safe Shutdown Cooling Valves Surveillance l The following valves shall be tested for operability by partial l stroking every 92 days unless they cannot be operated during l normal plant operation.* A full functional test shall be l performed annually, or at the next scheduled plant shutdown if l such test was not performed during the previous year provided h l) that the surveillance interval does not exceed 18 month h
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~ Pneumatically, hydraulically, or electrict.ly operated l valves that are required to operate for actuation of the j safe shutdown cooling mode of operation l (implemented per ISI Criterion B);
l Normally closed check valves that are required to open for l actuation of the safe shutdown cooling mode of operation l (implemented per ISI Criterion B); and l - Valves (including normally power operated valves) that l must be manually positioned for actuation of the safe l shutdown cooling mode of operation l (implemented per ISI Criterion G).
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Fort St. Vrain il Technical Specifications Amendment Page 5.3-6a Basis for Specification SR 5.3.4 The Safe Shutdown Cooling mode of operation utilizes systems or portions of systems that are in use during normal plant operation. In many cases,- those valves required to initiato Safe Shutdown Cooling are not called upon to function during normal operation of the plant, except to stand fully clossd or open.
Testing of these valves will assure their operation if called upon to initiate the Safe Shutdown Cooling mode of operation.
During reactor operation, the instrumentation required to monitor and control the Safe Shutdown mode of cooling is normally in use and any malfunction would be immediately brought to the attention of the operator. That instrumentation not normally in use is tested at intervals specified by other surveillance requirements in this Technical Specification.
Safe Shutdown Cooling, the systems or portions of systems involved, are discussed in Sections 10.3.9 and 10.3.10 of the FSAR and are represented in FSAR, Figure 10.3-4.
Valve testing will include, as applicable, full gtroking l each valve, or an observation that the valve stem or disc travels from the valve normal operating position to the position required to perform the safety function, an
Fort St. Vrain il Technical Specifications Amendment Page 5.3-7 observation that the remote position indicators accurately reflect actual valve position, and a measurement of the full stroke time for the hydraulically actuated automatic valves.
Speelfication SR 5.3.5 - Hydraulie Pewer System Surveillance The pressure indicators and low pressure alarms on the hydraulic oil accumulators pressurizing gas and on the hydraulic power supply lines shall be functionally tested once every three nonths and calibrated once per year.
Basis for Specifiestion SR 5.3.3 The hydraulic power system is a normally operating system.
Malfunctions in this system will normally be detected by failure of the hydraulic oil pumps or hydraulic oil accumulators to maintain a supply of hydraulic oil at or above 2500 psig. Functional tests and calibrations of the pressure indicators and low pressure alarms on the above basis will assure the actuation of these alarms upon a malfunction of the hydraulic power system which may compromise the capability of operating critical valves.
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Fort St. Vrain #1 Technical Specifications Amendment Page 5.3- 18a Specification SR 5.3.9 - Safetv Valves Surveillance N
lM h The steam generator superheater and reheater safety valves l and the steam / water dump tank safety valves shall be l tested at five calendar year intervals to verify their (3) 4 setpoints.
l SR 5.3.9 shall be implemented per ISI Criterion F.
@l Basis for Specificatien SR 5.3.9 l Safety valves protect the integrity of the plant l components which are part of the primary or secondary l reactor coolant boundary, and also the integrity of j l systems required to safely shutdown and cool the reactor valve $k h)gl under accident conditions.
s) will io (L e c orda,,c e sai u- _+L e sig ;as.sure Testing the safet Lie provcs;o.,5 that the 04 Mc A5mE pressure within e
the equipment remains within design limits. ,7 N fWhen p 'actical, test ng of the sa ty ~ valves E ll be
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Fort St. Vrain 81 Technical Specifications Amendment Page 5.4- 13b l Specification SR 5.4.5 - PCRV Cooling Water System Flow l Instruments Surveillance l A PCRV Cooling System scanner flow readout shall be taken and l normal mode alarms functionally checked monthly. The scanner l and alarms, and six (6) subheader flowmeters shall be l calibrated annually, or at the next scheduled plant shutdown l if they were not calibrated during the previous year provided l that the surveillanco interval does not exceed 18 months, l SR 5.4.5 shall be implemented per ISI Criterion G.
Basis for Soweification SR 5.4.5 l Flow scanning acts as a backup to temperature scanning and l initiates no autematic protective actions, only an alarm.
l Because a restriction or a leak in the system would develop l over a period of time, the specified interval for comparing l flow readouts is sufficient to detect any long term change in l the system.
Specification SR 5.4.6 - Core Delta P Indicater -
Surveillance Requirement The core Delta P instrumentation shall be calibrated on a once per refueling cycle interval.
f Basis for Specification SR 5.4.6 Core differential pressure is an indication of gross blockage of flow in the core.
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