ML20207S195
| ML20207S195 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/09/1987 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207S190 | List: |
| References | |
| NUDOCS 8703190109 | |
| Download: ML20207S195 (31) | |
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/ 'o UNITED STATES E' . ,- ( , ' ,i NUCLEAR REGULATORY COMMISSION g, ' , #
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PUBLIC SEPVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. DPF-34
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by Public Service Company of Colorado (the licensee) dated September 4,1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied, i
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.D(?) of Facility Operating License No.
DPR-34 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 51 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSI.ON
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h it$ . i sw Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 9, 1987 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 51 TO FACILITY OPERATING LICENSE NO. DPR-34 DOCKET NO. 50-267 Replace the following peges of the Appendix A Technical Spec!"ications with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating tha areas of cnange.
Remove Insert 5.0-2 Amend. 36 10/13/83 5.0-2 .
5.2-1 Amend. 33 03/08/83 5.2-1 5.2-16 Amend. 33 03/08/83 5.2-16 5.2-17 Amend. 33 03/08/83 5.2-17 5.2-18 Amend. 33 03/08/83 5.2-18 5.2-19 Amend. 33 03/08/83 5.2-19 5.2-20 Amend. 33 03/08/83 5.2-20 5.2-26 Amend. 33 03/08/83 5.2-26 5.2-27 Amend. 33 03/08/83 5.2-27, 5.2-27a 5.2-31 Amend. 33 03/08/83 5.2-31 5.2-32 Amend. 33 03/08/83 5.2-32, 5.2-32a 5.2-34 Amend. 33 03/08/83 5.2-34, 5.2-34a, 5.4-34b, 5.2-34c, 5.2-34d, 5.2-34e 5.2-35 Amend. 33 03/08/83 5.2-35 5.3-5 Amend. 33 03/08/83 5.3-5 5.3-6 Amend. 33 03/08/83 5.3-6, 5.3-6a 5.3-7 Amend. 33 03/08/83 5.3-7
, 5.3-19 Amend. 39 01/25/84 5.3-19 l 5.4-13 Original 01/24/74 5.4-13 5.4-14 Original 01/24/74 5.4-14, 5.4-14a i
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. Fort St. Vrain #1 Technical Specifications Amendment # 51 Page 5.0-2 l
Amencment No. 33 by the Nuciear Regulatory Co= mission.
ISI Criterion C: The surveillance requirement shall be implemented before the beginning of fuel cycle 5.
ISI Criterion D: The surveillance requirement " shal l be implemented in the existing schedule of surveillance tests, following 90 days from the formal approval date of Amendment No. 33 Dy the Nuclear Regulatory Commission.
l ISI Criterion E: Same as ISI Criterion A but applicable to l AmeidmentNo.51 l ISI Criterion F: Same as ISI Criterion B but applicable to fuel l cycle 5 and Amendment No.51 .
l ISI Criterion G: Same as ISI Criterion B but applicable to l Amendment No. 51.
Fort St. Vrain #1 Technical Specif/' cations Amendment n *2 Page 5.2-1 5.2 PRIMARY COOLANT SYSTEM - SURVEILLANCE REQUIREMENTS Aoplicability Applies to the surveillanca of the primary (helium) reactor coolant system, excluding the steam generators, l and to the surveillance of the reactor auxiliary systems.
Objective 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.
p Specification SR 5.2.1 - PCRV and PCRV Penetration Overpressure Protection Surveillance a) 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 above testing.
Tank closure flange leak tightness shall be determined ~
following tank closure. SR 5.2.1.a shall be implemented per ISI Criterion C.
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- Fort St. Vrain #1 Technical Spagifications Amendments
Page 5,2-16 i Specification SR 5.2.8 - Helium _C_ir,culator Bearing Water Pumps And Makeup Pump Surveillance l The circulator ' bearing water pumps, bearing water makeup i pumps, and associated instruments and controls shall be ,
tested as follows:
a) The Normal Makeup Punp shall be operated in the I recycle mode every 92 days. SR 5.2.8a shall be .
I implemented per ISI Criterion G.
b) The Emergency Makeup Pump shall be functionally tested l every 92 days. SR 5.2.8b shall be implemented per ISI l Criterion G.
c) The associated instruments and controls shall be functionally tested in conjunction with and at the intervals specified in parts a) and b) above, and calibrated annually.
I d) Each Bearing Water Pump, and the associated l instruments and controls shall be functionally tested I at each scheduled plant shutdown. In addition, the l instruments shall be calibrated annually, o" at the l next scheduled plant shutdown if they were not I calibrated duri.ng the previous year provided that the I surveillance interval does not exceed 18 months. SR _
l 5.2.8d shall be implemented per ISI Criterion F.
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. Eqrt St. Vrain #1 Technical Specifications Amendment Page 5.2-17 -
Basis for Soecification SR'5.2.8 i l- The bearing water pumps and bearing water makeup pumps are l required to operate for sa fe shutdown cooling of the I rea.ctor under accident conditions described in FSAR -
l Section 10.3.9. The specified tests and testing intervals l are sufficient to ansure adequate pump operation for the l performance of their required safety functions.
l Performance capability of the bearing water pumps is
- I verified by normal operation. Perfo'rmance capability of l the normal bearing water makeup pump is verified when I 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.
Specification SR 5.2.9 - Helium Circulater Bearing Water Accumulators Surveillance The helium circulator bearing water accumulators,
! instrumentation, and controls shall be functionally tested l every 92 days and calibrated annually. SR 5.2.9 shall be i implemented per ISI Criterion E.
- Basis for Specification SR 5.2.9 l
Helium Circulater bearing water is normally supplied from -
l the bearing water system and is backed up by the backup bearing water system supplied from the Emergency Feedwater l
Fort St. Vrain #1 Technical Specifications Amendment * '
Page 5.2-18 Header. In the event of a failure in both of these j ,
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 /Fi re Suppression Water System Surveillance a) The fire water system shall be verified operable as follows:
- 1) The motor driven and engine driven fire pumps
. shall be functionally testec 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 i . refueling shutdown.
- 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.
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- Fort St. Vrain #1 Technical Specifications Amendment
- Page 5.2-19 i i
- 5) The batteries, cell plates, and battery racks,I 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.
b) The fire suppression water system shall be verified operable as follows:
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- 1) Monthly by veri fying that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured
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in position, is in its correct position.
- 2) Semi-annually by performance of a fire suppression water system flush.
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- 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, and: -
(a) Verifying that each automatic valve in the flow path actuates to its correct position.
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Fort St. Vrain #1 Technical Specifications Amendment:
- Page. 5.2 '20 (b) Verifying that each fire water pump develops I at least 1,425 gpm at a discharge pressure no l less than 119 psig. SR 5.2.10.b4b shall be j implemented per ISI Criterion G.
(c) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.
(d) Verifying that each fire water pump starts sequentially to maintain the fire suppression water system pressure at greater than or equal
.I to 119 psig.
- 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
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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 operability of the fire suppression water system ensures that adequate fire suppression and emergency safe shutdown cooling capability is available. The specified testing interval is sufficient to ensure proper cperation of the system when required.
Fo.t St. Vrain #1
-Technical Specificatiens Amendment #
Page 5.2-26 9
shutdown if these valves have not been tested duringi the previous year. SR 5.2.16 d shall be implemented per ISI Criterion B.
e) The check valves on the HTFA purge lines shall be tested at five calendar year intervals. SR 5.2.16.e shall be imler.ented per ISI Criterion B.
fi 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.
I g) Each helium purification cooler well closure shall be i leak tested, and the well pressure monitoring i instruments shall be calibrated, once during each I refueling cycle. In addition, the instruments and I controls used to automaticaTly isolate the i
l purification system shal.1 be functionally tested at
! l the same frequency. SR 5.2.16g shall be implemented
[ per ISI Criterion F.
l Basis for Soecification SR 5.2.16 l _
- Fort St. Vrain #1 Technical Specifications Amendment
- Page 5.2-27 4
i The interval specified for determining the actual primary and
-secondary closure leakage is adequate to assure compliance with LCO 4.2.9.
In the determination of closure 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 ,
- p. essure shall be used.
The interval specified for functional testing and calibration of the instrumentation and alarms 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 I cooler wells is adequate to verify the well integrity, as well _
l as that of primary coolant boundary components located therein.
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Fort St. Vrain #1 Technical Specifications Ame'tdsnt $1 Page 5.2-27a Specification SR 5.2.17 - Helium Circulator Pelton Wheels .I -
DELETE SEEf.IFICATION SR 5.2.17 IN ITS ENTIRETY [
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' Specification SR 5.2.18 - Helium Circulators Surveillanm
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a) At the time of the first main turbine generator "
overhaul, one helium circulator unit shall be removed in its entirety from the PCRV and thoroughly inspected for siges of abnormal wear or component degradation.
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- 1) Such . ins'pection shall , include examination of ;
bearing surfaces, seal su'rfa ce s, brake system, ~
buffer seal system, and labyrinth seals. '
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.y 'E Fort St. Vrain #1 Technical Specifications Amendment *bI Page,5.2-31 l Soecification SR 5.2.21 - ACM Transfer Switches, Valves, and I l Instruments Surveillance l Those valves and transfer switches that must be manually positioned l for actuation of the Alternate Cooling Method (ACM) mode of operation ~
l shall beI, tested for operability by partial stroking of the valve I twice an.qually at,an interval between tests to be not less than four l (4) months, nor gr/Ater. than eight (8) months. A full functional l test shall be performed annually, or at the next scheduled plant
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[ shutdown if such test was not performed during the previous year
, provided that the surveillance interval does not exceed 18 months.
l SR 5.2.21 shall be implemented per ISI Criterion F.
[' l Basis for Specification SR 5.2.21
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l In the event that the ACM mode of operation must be implemented, it
, I is necessary to manually position valves (manual valves as well as l valves which would normally be pneumatically or electrically
[ operated) and to manually reposition electrical transfer switches.
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' Fort St. Vrain #1 Technical Specifications Amendment * !l
? Page 5.2- 32
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SoecificationSR5.2.22-PGIGrachiteSurveillance 1;
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PGX graphite surveillance spicimens 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 dictatesotherwise.
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n Upon removal, these specimens will be subjected to examination, and e
compared with laboratory control specimens in evaluating oxidation f
P
.o rates, oxidation profiles, and ger.eral dimensional characteristics.
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The results of these tests and examinations shall be utilized to issess the condition of the PGX core support blocks in the reactor and shall also be utilized to modify, as necessary, the planned removal of subsequent PGX surveillance specimens.
The results of these examinations shall be submitted to the NRC staff '
for review.
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Fort St. Vrain #1 Technical Specifications Amendment ".
Page 5.2-32a Basis for Soecification SR 5.2.22 The PGX graphite specimens will be placed in modified coolant i channels in five (5) transition reflector elements in the hottest columns of regions 22, 24, 25, 27, and 30. The surveillance test '
specimens will be subje:ted to the prima ry coolant conditions, as well as other reactor parameters that are normally seen by the PGX core support blocks. Examination and tests of the surveillance test specimens at regular intervals can readily be utilized to assess oxidation rates, oxidation profiles, as well as general degradation of the PGX : ore support blocks to adequately predict the structural integrity of the core support blocks over the operating life of the reactor. -
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Fort St. Vrain #1 Technical Specifications Amendment *-
Page 5.2-34 Specification SR 5.2.23 - Firewater Boester pumoI Surveillance Each firewater booster pump 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 be 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 firewater booster pumps and one firewater pump are required to 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 Coolina Water l Systems Surveillance l The reactor auxiliary cooling water systems shall be
] tested as follows:
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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J Fort St. Vrain #1 Technical Specifications Amendment *'
Page 5.2- 34a l j b) Each circulating water makeup pump and the associated I 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, and the pump performance capability (flow '
l and discharge pressure) and mechanical condition l (vibration amplitude and bearing temperature) shall be j
verified annually or at the next scheduled plant ,
j shutdown if this was not performed during the previous
- l year. SR 5.2.24b shall be implemented per
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ISI l 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
- p '1 Page 5/2-34b I d) Alignment and settlement of the circulating water makeup; l pond embankments shall be verified at five calendar year j
intervals. The embankments and the water structures shall l be examined at the same intervals for abnormal erosion, l . cracks, seepage, leakago, 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 1 F. .
l .e) Each service water pump and the associated instruments and I controls shall be functionally tested monthly. In l addition, the instruments shall be calibrated, and the l pump performance (flow and discharge pressure) and I
. mechanical condition (vibration amplitude and bearing l temperature) shall be verified annually or at the next l
scheduled plant shutdown if this was not performed during i the previous year. SR 5.2.24e shall be implemented per l ISI Criterion F. '
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- Fort St. Vrain #1 Technical Specifications Amendment }. 7 Page 5.2- 34c l f) Each reactor plant cooling water pump and the associatedi l instruments and controls shall be functionally tested l monthly. In addition, the instruments shall be l calibrated, and the pump performance (flow and discharge l pressure) and mechanical condition (vibration amplitude '
l and bearing temperature) shall be verified annually or at l the next scheduled plant shutdown if this was not l performed during the previous year. SR 5.2.24f shall be-1 implemented per ISI Criterion F.
- l g) Each purification cooling water pump and the associated I instruments and controls shall be functionally tested i monthly. In addition, the instruments shall be l
calibrated, and the pump performance (flow and discharge
. l pressure) shall be verified annually or at the next I
scheduled plant shutdown if this was not performed during l the previous year. SR 5.2.24g shall be implemented per i ISI Criterion F.
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- Fort St. Vrain #1 Technical Specifications Amendment A :
Page 5.2-34d l h) Instruments and valves, used for automatic isolation ofi .
l portions of the purification cooling water system and the l reactor plant cooling water system, that may be required l for confinement of reactor coolan. and that are capable of j being tested, shall be tested for operability by partial ~
- l. stroking or full stroking of the valves, as appropriate, l twice annually at an interval between tests to be not less l than four (4) months, nor greater than eight (8) months.
l Additionally, these instruments and valves shall be i functionally teste.d annually or at the next scheduled l plant shutdown if such test was not performed during the
( , previous year, provided that the surveillance interval l does not exceed 18 months. SR 5.2.24h shall be l implemented per ISI Criterion F.
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Fort St. Vrain #1 Technical Specifications Amendment 4 Page 5.2-34e l Basis for Specification SR 5.2.24 I l The reactor auxiliary cooling water systems (including water makeup l system, service water system, reactor plant cooling water system, and l purification cooling water system) are required to operate for l reactor cooling under postulated loss of forced circulation cooling i accident conditions. Except for the purification cooling water l system, they are also required for safe shutdown cooling of the l reactor under other postulated accident conditions. The circulating l water makeup system also supplies water for fire suppression. These l systems routinely operate during normal plant operation. Routine 1 op'eration in conjunction with the specified tests and testing l intervals are sufficient to ensure adequate system and/or component l operation for 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 i of the embankments and of the water structures will provide for an l additional verification 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.
4 l The interval specified for instruments and valves is adequate to I assure their automatic isolation function, if degradation were to l occur in the integrity of the reactor coolant boundary, resulting in l primary coolant leakage into the system.
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"' Fort St. Vrain #1 Technical Specifications Amendmeng
- bJ Page 5.2*35 -
Specification SR 5.2.25 - Core Su6 port Block Surveillance I The top surface of the core support block for fuel regions fitted with PGX graphite specimens shall be visually examined by remote TV for indica' tion of cracks, in particular in areas where analysis shows '
the highest tensile stresses exist, at the refueling shutdown when the PGX graphite specimens are scheduled to be removed from the core t
in accordance with Technical Specification SR 5.2.22.
SR 5.2.25 shall be implemented per ISI Criterion D.
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- - Fort St. Vrain #1 Technical Specifications Amendment
- b3 Page 5.3-5 The main steam bypass valves divert up to 77% steam flowI (via desuperheaters) to the bypass flash tank on turbine trip or loop isolation, so that the steam is available for driving helium circulators, boiler feedpump turbines, etc.
The main steam power operated relief valves divert the -
remaining steam flow to atmosphere.
The six hot reheat steam bypass valves and the power operated pressure relief valves ensure a continuous steam flow path from the helium circulators for decay heat removal. _
The tests required on the above valves will demonstrate that each valve will function properly. Test frequency is considered adequate for assuring valve operability at all
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- Fort St. Vrain #1 Technical Specificatters
^ Amendment *r- -
page 5.3-6 Specification SR 5.3.4 - Safe Shutdown Cooling Valves i Surveillance i
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 l that the surveillance interval does not exceed 18 months. ,
l Pneumatically, hydraulically, or electrically operated l valves that are required to operate for actuation of the l safe shutdown cooling mode of operation (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 (implemented per ISI l Criterion G).
l * (implemented per ISI Criterion F)
Fort St. Vrain #1 l
, Technical Specifications '
Amendment * -
Page 5.3-6a Basis for Soecification SR 5.3.4 i
, 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 e
required to initiate Safe Shutdown Cooling are not called upon to function during normal operation of the plant, except to stand fully closed or open.
Testing of these valves wil.1 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 1
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
Valve testing will include, as applicable, full stroking l each valve, or an observation that the valve stem or disc e
travels from the valve normal operating position to the position required to perform the safety function, an 4 .e e . eme e a e e e e me, w e - , - - ,, ,,.,.-4,a ,,,.,m., ..,,,_,.p.- - _ , _ - _ _ _ - , , ,rw,,,,,,,, e~_m,,,,,,,,,__4 _ .,,_._,,,m_g -m.-.,,y ,, .,yp_ ,
Fort St. Vrain #1 Technical Specifications Amendment
- Page 5.3-7 observation that the remote position indicators accurately i reflect actual valve position, and a measurement of the full stroke time for the hydraulically actuated automatic valves.
Specification SR 5.3.5 - Hydraulic Power 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 months and calibrated once per year.
Basis for Specification SR 5.3.5 The hydraulic power system is a normally operating system, c 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.
- Fort St. Vrain #1 Technical Specifications Amendment
- Page Si3-19 Specification SR 5.3.10 - Secondary Coolant SystemInstrumentatied Surveillance The secondary coolant reheat steam instrumentation used:
a) for control and indication of emergency condensate flow to the reheaters and reheater backpressure, in case of safe shutdown cooling, b) to automatically open the reheater discharge bypass on high pressure, and c) to monitor reheater discharge bypass temperature, and reheater inlet temperature, shall be functionally tested and calibrated annually, or at the next scheduled plant shutdown if such surveillance was not performed during the previous year.
SR 5.3.10 shall be implemented per ISI Criterion B.
e Tort St. Vrain #1' Teaba*a=1 3pecifications Amendment *g Page 5;4-13* 3 Snecification SR 5.k.k - Pepv coolina Water System Twrature Seannef-Surveillance Recuirement i PCRT Cooling Systen temperature scanner readings shall be checked by comparison of representative liner cooling tube thermocouple outputs to their respective subheader temperatures and associated alaras tested once per month dwing power operation. ' -
- All thirty-six (36) outlet subheader temperature indicators shall be salibrated == P y. In addition, ninety-seven (M) liner cooling tube outlet thermocouples shall be calibrated ma===y.
Emais for Snecification SR 5.k.h .
The temperstwo scanner for the PCRY cooling system provides for eastimous taperstwo monitoring of the outlet water temperatwo of each individual liner cooling tube and alarming of high outlet temperstwes.
The surveillance interval specified is sufficiest to " detect any drift in the output of the individual thermocouples or scanner electronics to assure the temperature limitations of the PCRT cooling system are not exceeded..
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The ninety-seven (M) thermoccupies shall be distributed among the '
thirty-six (36) subheaders so that between 16.75 and 215% of the total in each subheader are calibrated each year. Thna, the ==i== time between calibration of any' one thermocouple, or any ecstplate subheader, shall not exceed six (6) years. The overall percentage of thermocouples calibrated per year exceeds 185 The surveillance interval for calibration, ocumbined with that for
! eheeking, assures sufficient accuracy of temperature measurement to adequately preteet the PCRY soncrete.
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o 0 Fort St. Vrain 01 Technical Specifications
, Amendegnt 6 51 .
Page 5'.4-14 l Soecificatien SR 5.4.5 - PCRV Cooling Water System Flowi
[ Instruments Surveillance i A PCRV Cooling System scanner flow readout shall be taken and l
normal mode alarms functionally checked mo!(thly. The scanner l and alarms, and six (6) subheader f?bwmeters shall be I calibrated annually, or at the next scheduled plant shutdown l if they were not calibrated during the previous year provided l
that the surveillance interval does not exceed 18 months.
I SR 5.4.5 shall be implemented per ISI Criterion G.
Basis for Specification SR 5.4.5 I Flow scanning acts as a backup to temperature scanning and
[ , initiates no automatic 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 i flow readouts is sufficient to detect any long term change in I the system.
Specification SR 5.4.6 - Core Delta P Indicator -
Survefilance Reouirement The core Delta P instrumentation shall be calibrated on a once per refueling cycle interval.
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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Fort St. Vrain #1 Technical Specifications e
- Amendment Page 5.4-14a!
Specification SR 5.4.7 - Control Rocm Temperature I Surveillance Requirement The control room temperature control thermostat shall be
-functionally tested monthly and calibrated annually. ,
Basis for Specification SR 5.4.7 The surveillance interval specified for functional testing and calibration of the control room thermostat will assure ,
its ability to not only control the room temperature as desired, but to also indicate the correct room temperature within the accuracy of the instrument.
Specification SR 5.4.8 - Power to Flow Instrumentation - g Surveillance Requirement The power to flow indication shall be verified daily and shall be calibrated once per refueling cycle.
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