ML20214M784

Proposed Tech Specs Incorporating Phase II of Inservice Insp Program

ML20214M784
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/04/1986
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20214M777	List: ML20214M774 ML20214M784
References
TAC-53417, NUDOCS 8609110280
Download: ML20214M784 (36)

Text

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Fort St. Vrain #1 Technical Spectf1 cat 1ons I Amendment Page 5.0-1 Amendment No. 33 by the Nuclear Regulatory Coastssion.

I3I criterton C: The surveillance requirement shall be implemented before the beginning of fuel cycle 5.

I3I Criterton 0: The surveillance requirement shall be implemented in the eststing schedule of surveillance tests, following 90 days from the formal approval date of Ameedmont No. 33 by the Nuclear Regulatory Commission.

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I3I Criterton E: Same as ISI criterton A but app 1tcable to l

Amendment No. _ .

l 13! criterton F: Same as I3I Cetterton B but appitcable to fuel l cycle 5 and Amendment No. _ .

i l 151 Criterton G: Same as I5! Crfterion 0 but aspitcable to l

Amendment No. _ .

i I-0609110200 860904 PDR ADOCK 05000267 P PDR *

, Fort St. Vrain #1 Technical Sp:;cifications Amendment Page 5.2-1 5.2 PRIMARY COOLANT SYSTEM - SURVEILLANCE REQUIREMENTS Applicability Applies to the surveillance of the primary (helium)

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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.

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.

Fort St. Vrain #1 Technical Specifications Amendment Page 5.2-16 l Specification SR 5.2.8 - Circulator Bearing Water Pumps And Makeup Pump Surveillance 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 mode every 92 days. SR 5.2.8a shall be l 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.

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. SR l 5.2.8d shall be implemented per ISI Criterion F.

Fort St. Vrain #1 Technical Specifications Amendment Page 5.2-17 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. Perfo'rmance 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.

Specification SR 5.2.9 - Helium Circulator Bearing Water Accumulators Surveillance The helium circulator bearing water accumulators, instrumentation, and controls shall be functionally tested I every 92 days and calibrated annually. SR 5.2.9 shall be l 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

Fort St. Vrain #1 Technical Specifications Amendment Page 5.2-18 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 accumulator controls, should they be called upon to l

l perform their required function.

Specification SR 5.2.10 - Fire Water System / Fire 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 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.

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 #1 Technical Specifications Amendment Page 5.2-19

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.

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, and:

(a) Verifying that each automatic valve in the flow path actuates to its correct position.

Fort St. Vrain #1 Tcchnical Specificaticns Amendment Page 5.2- 20 (b) Verifying that each fire water pump develops l at least 1,425 gpm at a discharge pressure no l less 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 r.t 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 l 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 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 operation of the system when required.

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- 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.

e) 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 I 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 isoiate the l purification system sna11 be functionally tested at

-l the same frequency. SR 5.2.16g shall be implemented l- per ISI Criterion F.

Basis for Specification SR 5.2.16 1

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Fort St. Vrain #1 Technical Sp2cifications Amendment Page 5.2-27 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 pressure 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.

Fort St. Vrain #1 Technical Specifications Amendment Page 5.2-27a Specification SR 5.2.17 - Helium Circulator Pelton Wheels DELETE SPECIFICATION SR 5.2.17 IN ITS ENTIRETY Specification SR 5.2.18 - Helium Circulators Surveillance 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 signs of abnormal wear or component degradation.

1) Such inspection shall include examination of _

bearing surfaces, seal surfaces, brake system, buffer seal system, and labyrinth seals.

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Fort St. Vrain #1 Technical Specifications Amendment Page 5.2-31 l Specification SR 5.2.21 - ACM Trant,fer Switches, Valves, and 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 be tested for operability by partial stroking of the valve l twice annually at an interval between tests to be not less than four l (4) months, nor greater than eight (8) months. A full functional l test shall be performed annually, or at the next scheduled plant l shutdown if such test was not performed during the previous year l 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 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.

Fort St. Vrain #1 Technical Specifications Amendment Page 5.2- 32 f

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.

The results of these tests and examinations shall be utilized to assess 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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Technical Specifications Amendment Page 5.2-32a Basis for Specification SR 5.2.22 The PGX graphite specimens will be placed in modified coolant 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 subjected to the primary 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 core support blocks to adequately predict the structural integrity of the core support blocks over the operating life of the reactor.

Fort St. Vrain #1 Technical SpGcifications Amendment Page 5.2-34 Specification SR 5.2.23 - Firewater Booster Pump 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 centrols 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 Cooling Water l Systems Surveillance l The reactor auxiliary cooling water systems shall be l 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.

Fort St. Vrain #1 Technical SpIcifications AmIndmsnt 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, and the pump performance capability (flow l and discharge pressure) and mechanical condition l (vibration amplitude and bearing temperature) shall be l verified annually or at the next scheduled plant l shutdown if this was not performed during the previous l year. SR 5.2.24b shall be implemented per 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.

a --gn &Mr Fort St. Vrain #1 Technical Specifications Amendmsnt 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 embankments 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 I centrols shall be functionally tested monthly. In l addition, the instruments shall be calibrated, and the l pump performance (flow and discharge pressure) and l 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 l the previous year. SR 5.2.24e shall be implemented per

[ ISI Criterion F.

Fort St. Vrain #1 Technical Specifications Amandment Page 5.2- 34c 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 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 l implemented per ISI Criterion F.

l g) Each purification cooling water pump and the associated l ir:struments 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) 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 l ISI Criterion F.

Fort St. Vrain #1 Technical Sptcifications Amendment Page 5.2-34d l h) Instruments and valves, used for automatic isolation of 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 coolant and that are capable of l 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 l functionally tested annually or at the next scheduled l plant shutdown if such test was not performed during the l 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.

Fort St. Vrain #1 Technical Sptcifications Amendment Page 5.2-34e l Basis for Specification SR 5.2.24 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 l 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 l operation in conjunction with the specified tests and testing l intervals are sufficient to ensure adequate system and/or component I operation for the performance of their required safety functions.

l Measuring the position of survey markers and evaluating the changes I 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 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 I 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, resulting in i primary coolant leakage into the system.

Fort St. Vrain #1 Technical Sp2cifications Amendment Page 5.2-35 Specification SR 5.2.25 - Core Support Block Surveillance The top surface of the core support block for fuel regions ~ fitted with PGX graphite specimens shall be visually examined by remote TV for indication 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 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 Page 5.3-5 The main steam bypass valves divert up to 77% steam flow (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 times.

Fort St. Vrain #1 Technical Specifications Amendment -

Page 5.3-6 Specification SR 5.3.4 - 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 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 l 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) i

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Ttchnical Spscifications 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 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 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 t'

the FSAR and are represented in FSAR, Figure 10.3-4.

Valve testing will include, as applicable, full stroking i each valve, or an observation that the valve stem or disc I

travels from the valve normal operating position to the l position required to perform the safety function, an l

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Fort St. Vrain #1 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.

Specification SR 5.3.5 - Hydraulic Power System Surveillance 2

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.

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 comprcmise the capability of operating critical valves.

Fort St. Vrain #1 Technical Sptcifications Amendment Page 5.3-18 to verify proper piston movement, lock-up, and bleed. The number of each type of snubber represented by use of either plan presented in Section 5.3.8.c) of this specification is an adequate sample for such tests.

Observed failures on these samples should require testing of additional units.

The required surveillance program will assure a higher degree of snubber functional reliability.

Fort St. Vrain #1 Technical Specifications Amsndmint Page 5.3-18a Specification SR 5.3.9 - Safety Valves Surveillance Safety valves shall be tested as follows:

l a) The steam generator superheater and reheater safety valves and l the steam / water dump tank safety valves shall be tested at five l calendar year intervals to verify their setpoints. SR 5.3.9a l shall be implemented per ISI Criterion F.

l b) All other Class 1 safety valves (not covered by specific l Technical Specification Surveillance Requirements) shall be l tested at five calendar year intervals to verify their i setpoints. SR 5.3.9b shall be implemented per ISI Criterion F.

l Basis for Specification SR 5.3.9 l Safety valves protect the integrity of the plant components which are l part of the primary or secondary reactor coolant boundary, and also l the integrity of systems required to safely shutdown and cool the l

l reactor under accident conditions. Testing the safety valves will assure that the pressure within the equipment remains within design limits.

Fort St. Vrain #1 Technical Specifications Amendment Page 5.3-19 Specificatien SR 5.3.10 - Secondary Coolant System Instrumentation 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 i

during the previous year.

I SR 5.3.10 shall be implemented per ISI Criterion B.

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l Fort St. Vrcin #1' Technical Specifications Amendment Page 5.4-13 sneeification ER 5.k.h - PCRV Coolina Water System Tennerature Scanner-Surveillance Recuirement PCRV Cooling System temperature scanner readings shall be checked by camparison of representative liner cooling tube thermocouple outputs to their respective subheader temperatures and associated alarms tested once per month during power operation.

All thirty-six (36) outlet subheader temperature indicators shall be ,

calibrated ====117 In addition, ninety-seven (97) liner cooling tube outlet thermocouples shall be calibrated ====11y.

Basis for Snecification SR 5.k.h The temperature scanner for the PCRV cooling system.provides for continuous temperature monitoring of the outlet water temperature of each individual liner cooling tube and alarming of high outlet t aperatures.

The surveillance interval specified is sufficient to ' detect any drift

., in the output of the individual theraccouples or scanner electronics to assure I

the temperature limitations of the PCRY cooling system are not exceeded. .

The ninety-seven (97) thermocouples shall be distributed among the l thirty-six (36) subheaders so that between 16 7% and 215% of the total in each subheader are calibrated each year. Thus, the maximum time between calibration of any' one thermocouple, or any complete subheader, shall not exceed six (6) years. The overall percentage of thermocouples calibrated per year exceeds 185.

The surveillance interval for calibration, combined with that for checking, assures sufficient accuracy of temperature measurement to adequately protect the PCRV concrete.

Fort St. Vrain #1 Technical Specifications Amendment Page 5.4-14 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 surveillance interval does not exceed 18 months.

l SR 5.4.5 shall be implemented per ISI Criterion G.

Basis for Specification SR 5.4.5 l Flow scanning acts as a backup to temperature scanning and l 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 l flow readouts is sufficient to detect any long term change in l the system.

Specification SR 5.4.6 - Core Delta P Indicator -

Surveillance Requirement 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.

Fort St. Vrain #1 Technical Specifications e Amendment Page 5.4-14a Specification SR 5.4.7 - Control Room Temperature -

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 -

Surveillance Requirement The power to flow indication shall be verified daily and shall be calibrated once per refueling cycle.

ATTACHMENT 3 SIGNIFICANT HAZARDS CONSIDERATION FOR THE FSV INSERVICE INSPECTION AND TESTING PROGRAM UPDATE I

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SIGNIFICANT HAZARDS CONSIDERATION FOR THE FSV INSERVICE INSPECTION AND TESTING PROGRAM UPDATE

1. BACKGROUND The Fort St. Vrain Inservice Inspection and Testing Program is specified by the Plant Technical Specification Surveillance Requirements (Ref. 1).

In response to a commitment in the 1972 Safety Evaluation Report (Ref. 2) Public Service Company has been reviewing, as a continuing effort, the Inservice Inspection and Testing Program for Fort St. Vrain to feedback the acquired operating experience with the plant, and to update the program in light of more recent rules and regulations.

The original 1972 Safety Evaluation Report (Ref. 2) included a commitment to review the Inservice Inspection Program for the primary coolant system after five years of reactor operation.

The status of the review effort was originally described by Public Service Company, together with the planned approach to follow in conforming with the 1972 Safety Evaluation Report commitment (Ref. 3). A review of Public Service Company plans was performed by the Nuclear Regulatory Commission, who also identified priority items to be addressed beyond the scope of the original Safety Evaluation Report commitment (Ref. 4). The general Inservice Inspection and Testing Program review plan and the priority items were further discussed in letters and at meetings between the Nuclear Regulatory Commission and Public Service Company until a basic agreement was reached between both parties (Ref. 5 through 10). A schedule was established for the review of surveillance requirements for all major plant systems and equipment by subdividing them in priority categories as requested by the Nuclear Regulatory Commission (Ref. 11).

In the first phase of the program review and update, implemented by Amendment No. 33 to the Operating License (Ref 12.), the surveillance requirements pertaining to plant systems and equipment identified as priority category I were addressed (namely the prestressed concrete reactor vessel (PCRV),the reactor internals, the reactor primary and secondary coolant systems, and the PCRV auxiliary system).

Public Service Company's plan to proceed with a review and update of the surveillance requirements for other reactor auxiliary process systems and equipment important to safety were outlined in a letter to NRC (Ref. 3).

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2. METHODOLOGY AND REVIEW PROCESS The adequacy of the surveillance requirements for individual systems and components was reviewed in light of the importance of their safety functions to prevent or. mitigate the consequences of postulated accidents that could cause undue risks to the health and safety of the public.

The highest importance to safety was assigned to those systems and components which are critical for the mitigation of a postulated permanent loss of forced circulation cooling accident where potential for fuel damage exists (Design Basis Accident No.1), under the PCRV liner cooling mode of operation.

Following were those systems and components which are critical for the mitigation of postulated loss of normal forced circulation cooling accidents, under the Safe Shutdown Cooling mode of operation. This cooling method applies to accidents initiated by environmental disturbances (earthquake, tornado) or by equipment failures such as feedwater or steam pipe rupture.

Next those systems and components required to mitigate the consequences of a PCRV depressurization accident were considered (Maximum Credible Accident and Design Basis Accident No. 2).

Finally, the review included those systems and components required to mitigate the consequences of a loss of normal cuoling of a spent fuel storage well.

For each accident outlined above, the various auxiliary

> systems and components were systematically evaluated for l indentification of their critical safety functions.

Existing Technical Specification Surveillance Requirements were then reviewed to assess their adequacy for ensuring

! operability of these identified systems and components,

should they be called upon for the performance of their l required safety functions. Credit was taken, as appropriate, for routine operation of systems and components l during plant operation as a factor in the demonstration of i

their operability. System operational readiness as well as operability of pumps, compressors, fans, valves, controls and instrumentation were all addressed.

In addition, systems and components with a primary or secondary reactor coolant pressure boundary function, or with a containment isolation function, were also reviewed for adequacy of the related surveillance requirements. As previously indicated in Amendment No. 33 to the Operating License, the emphasis was placed on monitoring the structural integirty of the reactor coolant pressure boundaries wherever practical.

3. EVALUATIONS AND CONCLUSIONS The proposed changes to the Technical Specification Surveillance Requirements generally expand the scope of inservice examination and testing that is currently-performed at the Fort St. Vrain Nuclear Generating Station.

These proposed changes were initially submitted to the NRC in December, 1983 (Ref. 14), and again in November, 1985 (Ref. 16). This resubmittal is based on comments received in August, 1985 (Ref. 15) and June, 1986 (Ref. 17). This, in essence, provides greater assurance of plant safety and reliability.

Individual surveillance requirements have been evaluated in detail by Public Service Company. The results of these reviews revealed that existing surveillance requirements generally were adequate in light of plant operating experience, importance to safety, unique design features and limitations, and ASME Code development for large HTGR designs. Minor modifications to surveillance intervals were made to reflect operating experience, and to provide operating flexibility. Additional tests were included to assure the operability and accuracy of instrumentation which can be used for monitoring the structural intergrity of major plant equipment. Additional component testing was recommended, as a result of detailed reviews of plant systems, either when components important to safe plant shutdown and cooling were not in the scope of the current Technical Specifications, or when the testing method could be improved to provide additional assurance of component reliability.

Since the proposed changes to the Technical Specifications reflect additional surveillances as required by inservice inspection and testing requirements it can be concluded that the proposed amendment will not:

1) Involve a significant increase in the probability or consequnces of an accident previously evaluated; or

2) Create the possibility of a new or different kind of accident from any previously evaluated; or

3) Involve a significant reduction in a margin of safety.

Therefore, no significant hazards consideration is raised.

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4. REFERENCES

1. Plant Technical Specifications.

2. Safety Evaluation Report of January 20, 1972, Section 3.3.

3. Public Service Company letter dated October 13, 1978 (P-78169), Inservice Inspection - Fort St. Vrain.

4. Nuclear Regualtory Commission letter dated January 15, 1979, Inservice Inspection and Testing Program for Fort St. Vrain.

5. Public Service Company letter dated March 15, 1979 (P-79058), Inservice Inspection Program for Fort St. Vrain.

6. Nuclear Regualtory Commission letter dated June 5, 1979, Summary of Meeting Held on May 2, 1979, to Discuss Inservice Inspection.

7. Public Service Company Progress Report. Meeting held on August 20, 1979, between the Nuclear Regulatory Commission and Public Service Company.

8. Public Service Company letter dated August 22, 1979 (P-79176), Fort St. Vrain Inservice Inspection and Testing Program.

9. Nuclear Regulatory Commission letter dated October 5, 1979, Proposed Plan of Inservice Inspection and Testing for Fort St. Vrain.

10. Public Service Company Progress Report. Meeting held on November 1, 1979, between the Nuclear Regulatory Commission and Public Service Company.

11. Public Service Company letter dated November 30, 1979 (P-79289), Fort St. Vrain Inservice Inspection and Testing Program.

12. Fort St. Vrain Nuclear Generating Station, Amendment No. 33 to Facility Operating License DPR-34, dated March 8,1983.

13. Public Service Company letter dated June 1, 1983 (P-83195)

Inservice Inspection and Testing Status Update.

14. Public Service Company letter dated December 30, 1983 (P-83416) Proposed Technical Specification Changes - Inservice Inspection and Testing Requirements.

, 15. Nuclear Regulatory Commission letter dated August 27, 1985 (G-85361) Inservice Inspection and Testing Requirements.

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16. Public Service < Company letter dated November 27, 1985 (P-

- 85444) Proposed Technical Specifications -

Inservice

'. Inspection and Testing' Requirements.

17. Nuclear Regulatory Commission letter dated May 30, 1986 (G-

- 86286) Inservice Inspection and Testing Requirements.

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