ML20236A135
| ML20236A135 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/27/1989 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236A129 | List: |
| References | |
| NUDOCS 8903160403 | |
| Download: ML20236A135 (11) | |
Text
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' NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATIf!G LICENSE Amendment flo. 68 License No. DPR-34
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The appl: cation for amendment by Public Service Company of Colorado (the licensee) dated December 19, 1988, 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 Ch6pter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance: (1)thattheactivitiesauthorized by this einendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cortpliance with the Comission's regulations; D. The issuance of this license amendment will not be inimical to the cour.on defense and security or to the health and safety of the public; and 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.
8903160403 890227 7 DR ADOCK 0500
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- 2. Accordingly, the license is amended by char.ges to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. DPR-34 is hereby anended to read as follows:
(2) Technical Specifications ,
The Technical Specifications contained in Appendices A and B, as l revised through Amendment No. 68. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specification.s.
- 3. The ifcense amendn.ent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dj , LC$v LCt<~'
Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 27, 1989 l
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ATTACHMENT TO LICENSE AMEilDMENT N0. 68
_TO FACILITY OPERATING LICENSE NO. DPR-34 ,
l DOCKET NO. 50-267 Replace the following pages of the Appendix A Technical Specifications with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
] Remove Insert 4.4-6a 4.4-6a 4.4-6b 4.4-6b 4.4-6c 4.4-6c 4.4-12b 4.4-12b 4.4-12c 4.4-12c j- 4.4-13 4.4-13 5.4-11c 5.4-11c
- 5.4-11c.1 i.
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Fort St. Vrain #1 '
- .. . . Technical Specifications
, Amendment # S . 68 Page 4.4-6a l
, Specification LCO 4.4.1 Table 4.4-3 (Continued)
PLANT PROTECTIVE SYSTEM. TRIP SETPOINTS - CIRCULATOR TRIP i
TRIP ALLOWABLE NO. FUNCTIONAL UNIT SETp0 INT VALUE 10a.. Steam Leak Detection 5 52.3 degrees F 52.8 degrees F Turbine Building per minute per minute l Loop 1 (ROR) rate-of-rise rate-of-rise
'10b Steam Leak Detection . $ 52.3 degrees F $ 52.8 degrees F Reactor Building per minute per minute j . Loop 1 (ROR) rate-of-rise rate-of-rise )
i 10c Steam Leak Detection < 52.3 degrees F < 52.8 degrees F
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Turbine Building 'per minute per minute l Loop 2 (ROR) rate-of-rise rate-of-rise 10d. Steam Leak Detection 1 52.3 degrees F 1 52.8 degrees F Reactor Building per minute p,er minute l Loop 2 (ROR) rate-of-rise rate-of-rise
- l 10e Steam Leak Detection < 171 degrees F < 173 degrees F .i l Turbine Building Tixed high fixed high :
l Loop 1 (FIXED) temperature temperature i 10f. Steam Leak Detection < 171 degrees F < 173 degrees F l Reactor Building 71xed high ~ fixed high l Loop 1 (FIXED) temperature temperature l 10g. Steam Leak Detection < 171 degrees F 1 173 degrees F l Turbine Building 71xed high fixed high }
l Loop 2 (FIXED) temperature temperature l 10h. Steam Leak Detection < 171 degrees F < 173 degrees F l Reactor Building Yixed high ~ fixed high l Loop 2 (FIXED) temperature temperature l
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. Fort Stc Vrain #1 Technical. Specifications
- Amendment 0 Ep, 68 Page 4.4-6b I
I Specification LCO 4.4.1 Table 4.4-3 (Continued) f PLANT PROTECTIVE SYSTEM. OPERABILITY REQUIREMENTS - CIRCULATOR TRIP TOTAL CHANNELS MINIMUM FUNCTIONAL NO. OF TO CHANNELS ACTION ,
NO. UNIT CHANNELS TRIP OPERABLE APPLICABILITY (NOTE 2) l 10a, Steam Leak 4 2 3 Note 1 1,2,3,4,5 Detection Turbine Building l Loop 1 (ROR) o ,
10b. Steam Leak 4 2 3 Note 1 1,2,3,4,5 Detection Reactor Building l Loop 1 (ROR) loc. Steam Leak 4 2 3 Note 1 1,2,3,4,5 Detection l
Turbing(Building Loop 2 ROR) ,
10d. Steam Leak 4 2 3 Note 1 1,2,3,4,5 Detection Reactor Building l Loop 2 (ROR) l 10e. Steam Leak 4 2 3 Note 1 1,2,3,4,5 l Detection l Turbine Building I Loop 1 (FIXED)
I 10f. Steam Leak 4 2 3 Note 1 1,2,3,4,5 1 Detection l Reactor Building l Loop 1 (FIXED) l 10g. Steam Leak 4 2 3 Note 1 1,2,3,4,5 l Detection l Turbine Building l Loop 2 (FIXED) l 10h. Steam Leak 4 2 3 Note 1 1,2,3,4,5 1 Detection l Reactor Building i Loop 2 (FIXED)
Note:
- 1. The reactor shall not be operated at power (above 2% rated thermal power) except as provided by these requirements and their associated ACTION statements.
l l 2. The requirement to shut down affected helium circulators, provided in the introduction to Specification 4.4.1, does not apply.
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Fort St. Vrain 01 Technical Specifications Amendment 0 ED, 68
, Page 4.4-6c Table 4.4-3 (Continued)
] ACTION STATEMENTS (for 104 through 10h Only)
ACTION 1 - With only 7 OPERABLE channels in either building or in both buildings, operation at power may continue provided the inoperable channel is placed in bypass within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or reduce power to below 2% within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The channel shall be returned to OPERABLE status within the following 7 days.
ACTION 2 - With only 6 OPERABLE channels in either building or in both buildings, place the inoperable channels in bypass and reduce power to below 2% within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Operation at power may continue if at least 7 OPERABLE channels in both buildings are placed in service.
ACTION 3 - With inos rable channels or loops other than as provided in /CTION 1 and 2 above, reduce power to below 2% within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 4 - With any one valve actuated by SLR0!$ or electrical wiring and circuits used to actuate that valve inoperable, restore the valve and/or associated components to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or reduce power to below 2*. within thJ next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION $ - With two or more valves actuated by $LRDIS or electrical wiring and circuits used to actuate those valves inoperable, restore the valves and/or associated components to OPEP.ABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or reduce power to below 2*. within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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t Fort St. Vrain 01 Technical Specifications
- ' Amendm?nt # f;0,68 Page 4.4-12b
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Basis for Specification LCO 4.4.1 (Continued)
Circulater Seal Malfunction (Low /High)
A high reverse differential of -6.1" H2O would be reasonable evidence that bearing water is leaking into
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the primary coolant differential pressure of system.
+76.1" H2O An increasing would be reasonable evicence that primary coolant is leaking into the bearing water and thus into the closed circulator service system. In both cases a Circul& tor trip witn brake and seals set is appropriate.
D Circulater Soeed - High Water
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The Trip Setpoint has been estab operating speed. Ecuipment testing,lished ensures above normal that this Trip Setpoint will prevent failure due to fatigue cracking.
Steam Leak Detection in the Reactor Bu11dina Steam Leak Detection in the Reactor Building is required for equipment qualification of Safe Shutdown l Cooling Systems. ALLOWABLE VALUES are set at 5 52.8 I degrees F oer minute rate-of-rise and < 173 degrees F l fixed high temperature in order to prevent exceeding the harsh environment temperature profile to which the safe shutoown electrical ecuipment is qualified, per l the requirements of 10CFR50.49, and to allow for l building access to perform manual operator actions. A setpoint calculation analysis pe rformed per ISA Standard $67.04 and RG1.105 results in the stated ALLOWABLE VALUE and TRIP SETPOINT as specified in the LCO and this basis. The TRIP SETPOINT has been established with sufficient margin between the technical specification limit for the process variable and the nominal TRIP SETPOINT to allow for
- 1) inaccuracy of the instruments; 2) uncertainties in the calibration; 3) instrument drift that could occur during the interval between calibrations; and 4) inaccuracies due to ambient temperature changes, vibration and other environmental conditions. The l TRIP SETPOINTS are set at < 52.3 degrees F per minute l rate-of-rise and <
171 degrees F fixed high
! temperature until ,such time as the drift characteristics of the detection system are better understood from actual plant operati.1g experience and the assumptions used in the setpoint analysis are verified.
SLR0!$ design incorporates two panel: each with its own set of sensors for the Reacto and Turbine l Buildings and ' dual logic trains in each par.el. The l SLRDIS programming is such that SLR015 actu4 tion will l occur upon receiving signals satisfying the 2 cut of 4 l sensing logic from both SLRDIS panels for either a l temperature high rate-of-rise condition, a fixed high
- l temperature condition, or any combination of fixed I high temperature and rate-of-rise signals. However,
, l only the rate-of-rise and fixed high temperature
! conditions are required. Therefore, the surveillance
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. Fw% E8. Weta 03 Technical Specifications Amendmant # M , 68 1 -
Page 4.4-12c i
l Basis for Specification LCO 4.4.1 (Continued) l do not include combinations of fixed high temperature j trips and rate-of-rise trips. The SLRDIS design preserves the single failure concept. A single failure will neither cause nor prevent SLRDIS actuation in the event of a high energy line break, h The probability of an inadvertent actuation is extremely small due to the matrix logic employed for circulator trip and valve actuation. The SLRDIS panels are referred to as " loops"; however, due to the way the outputs of the canels are combined to provide protective action and satisfy the single failure concept, the SLRDIS loops do not correspond to primary or secondary loops.
For each S'.RDIS loop, the OPERABILITY requirements and their respective ACTIONS represent good operating practices and judgment for a four channel detection system with a 2 of 4 coincidence trip logic. The fourth channel may be placed in bypass for test and/or maintenance purposes, subject to the ACTION statement restrictions, while preserving a 2 of 3 coincidence logic OPERABLE. The Steam Line Rupture Detection / Isolation System as designed and installed
. has spare channels available for input. Any of the available channels may be selected for input signal processing provided the surveillance are current on l the channels used. The SLRDIS actuation function is l required to be OPERABLE only at POWER (above 2*. rated thermal power). Analyses with rated reactor power at l 2% demonstrate that isolation can be accomplished l manually following receipt of a SLRDIS temperature l pre-trip alarm. The temperatures as analyzed in both the reactor and turbine buildings stay well below the temperature for which the equipment is qualified.
The ACTION statements foe inoperable SLRDIS detection and information processing equipment allow one channel in each building to be inoperable for up to 7 days; a second inoperable channel in either building recuires that power be reduced to below 2*. within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The 7 day ACTION time for a single detector channel is acceptable based on preservation of a 2 out of 3 coincidence detection system still in operation.
. ACTION 3 is applicable to other functions within the SLRDIS instrumentation panel such as ' loss of power from instrument buses, or otner failures in the logic trains and associated electronics. A 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period in ACTION 3 for inoperability of those associat.d SLRDIS functions minimized the time that SLR015 may operate with limited functional capability.
A1 inoperable valve or associated equipment is allowed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. High energy line break analysis for environmental qualification assumes the worst-case single active failure. Thus, a single valve inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is within the bounds of analysis. When two or more valves arid /or associated equipment is inoperable. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to restore the inoperable equipment. Repairs may be perfortid while the plant is at power, thus,
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1' Fort St. Vrain #1 '
1 Technical Specifications
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Amendment # 50. 60 68 Page 4c4-13.
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o Basis for Specification LCO 4.4.1 (Continued) minimizing thermal cycling of' plant and installed. i equipment.
Steam Leak Detection in the- Turbine Buildino is required for equipment qualification of Safe Snutdown Cooling Systems. Thus, the limits and basis are the same as discussed in the basis for steam . leak detection in the reactor building,
- d. Rod Withdrawal Prohibit Inouts
.The termination' of control rod withdrawal to prevent furtner re, activity addition wil.l~ occur with the
. following conditions:
'Startuo Channel - Low Count Rate l
Start-up Channel -
Low Count Rate is provided to i prevent control rod pair withdrawal and reactor' i startup without adequate neutron flux indication. The trip level is selected to be above the background
. noise level ~. .
Linear Channel - Low power RWp *
'l Linear Channel ( $'. Power) directs the. reactor'
- l operator's attention to either a downscale failure of '
a power . range channel or improper positioning of the Interlock Sequence Switch. (FSAR Sections 7.1.2.2 and 7.1.2.8) .
Linear Channel - Hioh power RWp Lineae Channel ( 30'4 Power) is .provided to prevent control rod pair withdrawal if reactor power exceeds the Interlock Sequence Switch limit for the
" Low Power" position. (FSAR Sections 7.1.2.2 and 7.1.2.8) i e
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Fort St. Vrain 0{
Technical Specifications
. . Amendment No. EB, 68
.- Page 5.4-11c TABLE 5.4-3 M!NIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS, AND TESTING OF CIRCULATOR TRID SYSTEM (Co,t'a) l CHANNEL CHANNEL ACTUATION l l FUNCTIONAL CHANNEL CALIBRA- FUNCTIONAL LOGIC I lNO. UNIT CHECK TION TEST TEST APPLICABILITY I l l8c. Steam Leak 0 R( a) R(a) R(e) At Power" l l Detection l l Turoine Building .
l ll Loop 1 (ROR) l l l
- 18b. Steam Leak 0 R(a) R(a) R(b) At Power" l 1 i Detection l l Reactor Building l ll Loop 1 (ROR) l l l l8c. Steam Leak 0 R(a) R(a) R(b) At Power" l l Detection l l Turbine Building l ll Loop 2 (ROR) l l l 18d. Steam Leak 0 R(a) R(a) R(b) At Power" l l Detection I l Reactor Building e'. '
II Loop 2 (ROR) i l
l l l l8e. Steam Leak 0 R(a) R(a) R(c) At Power" l ll Detection l ll Turbine Building l i lI Loap 1 (FIXED) l II I l l8f. Steam Leak 0 R(a) R(a) R(c) At Power" l ll Detection l ll Reactor Building l ll Loop 1 (FIXED) l ll 2 l
l l8g. Steam Leak 0 R(a) R(a) R(c) At Power" l ll Detection l ll Turbine Building l ll Loop 2 (FIXED) I l1 l l l8h. Steam Leak 0 R(a) R(a) R(c) At power" l ll Detection l il Reactor Building l ll Loop 2 (FIXED) l 1 i See Notes on following page
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Fort St. Vrain 01 Technical Specifications Amendment No. 68 Page 5.4- 11c.1 Notes to lines 8a.>through 8h, above only:
l (a) The calibration / test consists of verifying the rate-of-rise and l fixed setpoint and checking for opens and shorts in the sensor cable.
] (b) The SLRDIS Detection and Logic racks shall be verified to have a response time less than or equal to 7.1 seconds when a simulated rate-of-rise trip input signal i s used to actuate the output relay logic.
l (c) The fixed high temperature trip programming does not utilize the l confirmation timing intervals that the rate of-rise utilizes.
l Trip occurs when the trip setpoint is exceeded.
"R - At least once per Refueling cycle, not to exceed 18 months Applicable only above 2% RATED THERMAL POWER D - Daily O
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