ML20212B364
| ML20212B364 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/17/1986 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20212B357 | List: |
| References | |
| LAC-12018, NUDOCS 8612290230 | |
| Download: ML20212B364 (15) | |
Text
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DAIRYLAND POWER COOPERATIVE LAC-12018 DECEMBER 17, 1986 l
l PROPOSED PAGES OF TECHNICAL SPECIFICATIONS I
r 8612290230 861217 PDR ADOCK 05000409 p PDR
2.8.4 The drive mechanisms shall have individual scram accumulators which drive the hydraulic motors and which shall be connected to the gas charging system and to the hydraulic charging system through individual check valves.
2.8.5 Each control rod shall be decelerated near the end of its scram stroke by an internal hydraulic dashpot action.
2.8.6 A rod test circuit shall permit the withdrawal and testing of one selected rod when the rod test key switch is turned on, when one of the rods has been selected for testing, when all other rods are full in, and when the period exceeds 7 see on both source range channels. This test circuit shall measure the time from the dropping out of the "All Rods Scram" relay to the indication of full insertion of the rod. When the rod test key switch is turned on, occurrence of a period less than 7 see on either of the source range channels shall initiate a full scram.
2.8.7 Deleted 2.9 CONTROL SYSTEMS 2.9.1 The power level of the reactor shall be adjusted manually by the positioning of control rods or by changes in forced circulation pump speed, or automatically by pressure controlled changes in the forced circulation pump speed.
2.9.2 The position of the scoop tubes which control forced circulation pump speed shall be controlled manually or automatically by the pressure control system.
2.9. 3 Deleted.
2.9.4 An Initial Pressure Regulating System shall assume control of turbine inlet valves at low pressures so as to maintain turbine inlet pressure within a controlled band. The high pressure set point of the control band shall normally be set below the operating set point of the forced circulation pump automatic control system. To maintain rated turbine inlet pressure, the Initial Pressure Regulating System may be used without use of the forced circulation pump automatic control system.
Ch. ,Y,Chy d Ch.4 Amendment No.__
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. l - 2700 -
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LIMITING St.TETY' SYSTEM SETTINGS
(
Ft ASES FOR SECT _IO!! Ar) 2. 2 Main Stean Isolation valves - (Co'n't ' d) .
~-
Operation of the reactor at pressures Icwer than 1000 psig is permitted only when the reactor is starting up or shutting down -
with steam flow rates < 100,000 lbs/hr. The low main steam pressure channels are bypassed during,this time to prevent auto-matic closure of'the valve on low reactor pressure.
The Containoent nuilding main steam isolation valve is also automatically closed on either low condenser vacuum or low reactor water levcd. In any event, closure of the containment' Building or Turbine Building main steam isolation valve will initiate a scram nnd will also initiate operation of the shut-down condenser. These actions anticipate the pressure and flux transients that occur as a result of isolation valve closure.
Closure of the turbine stop valve initiates a PARTIAL SCP.AM.
This scram anticipates the pressure, neutron flux, and heat flux increase that would result from rapid closure of the turbine stop valve. Transient' analyses indicate that the reactor power
{ would go to a penh of 260% of RJ.TED Ti!ERMAL POWER if no credit is taken for a period nor partial scrar.i. Because of the Doppler shutdown effect and the time lag in heat flux, the fuel claddinc Safety Limit would not be exceeded. The opening of the turbine bypass valve (for which credit is not tahon) prevents the contin-ued buildup c f the reactor vessel pressure. In'thc event that the bypass valve does not open, the operation of the shutdown condenser is initiated at 1325 psig and thereby prevents further pressure increase, as would safety valve operation should pressure reach their settings.
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Amendment No. g L. ,
4.2.4.3 Deleted 4.2.4.4 The reactor shall not be operated at a power level above 1 Hwt with less than 72 fuel assemblies installed in the reactor.
4.2.4.5 The reactor shall have a negative temperature coefficient for all moderator temperatures from ambient to 577'F or shall be preheated to obtain a negative temperature coef ficient prior to withdrawal of control rods.
4.2.4.6 The core shall be subcritical by a least 0.5% delta k/k in the cold clean condition with the rod of maximum worth in its fully withdrawn position and with all other rods fully inserted.
6 4.2.4.7 The reactor may be operated with control rod drives inoperable provided that all other requirements of these specifications are met.
4.2.4.8 If an unexplainable change of greater than 0.6 percent in core reactivity is observed in a core which has undergone no physical change, the reactor shall be shut down. Except as required to investigate the reactivity change, the reactor shall not be operated until a satisfactory reason for the change has been found.
4.2.4.9 Following core reloading and/or core rearrangement, operation will be discontinued if the difference between the observed and predicted value of core reactivity exceeds 2 percent. If this difference is exceeded, the effect of the difference on further operation will be evaluated before operation is continued.
Amendment No.) [, [ -
4.2.6.7 During operation with the nuclear instrumentation channels in 2 of 4 trip logic, at least three of nuclear channels 5, 6, 7 and 8, including their automatic gain control subsystem channels, shall be OPERABLE. If nuclear channel 5 or 6 is inoperable, its scram contacts shall be placed in the trip position. If power is de-escalated, the tripped channel's output shall be bypassed prior to entering 1 of 2 logic, subject to Section 4.2.6.1 requirements. If nuclear channel 7 or 8 is inoperable in a manner affecting the operability of its corresponding power-flow channel, the power-flow channel shall be bypassed, pursuant to the time limitations of Section 4.2.6.1, and the scram contacts of the nuclear channel shall be placed in the trip position.
4.2.6.8 Safety channels directly backed up by an identical channel or channels may be bypassed for maintenance or testing. Safety channels in the partial scram circuit may be bypassed for maintenance or testing for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.2.6.9 Both reactor forced circulation pumps shall be automatically shut down by a high reactor pressure signal or by a low reactor water level signal.
Bases - The RPTS is a diverse and independent backup except for common current sensing loops to the normal scram system for rapid shutdown of the reactor.
To protect the primary system from an ATWS event in which either MSIV closes at power, thus climinating the main condenser as a heat sink, the recirculation pumps must be shut down to prevent damage to the primary system due to high pressure. A rapid shutdown of the recirculation pumps has the effect of causing an increase in the moderator voids in the reactor core. A substantial negative reactivity results and the power and pressure surges that might otherwise occur in the most limiting transient (MSIV closure) are substantially reduced. With the recirculation pumps shut down, the reactor power will be reduced to a steady state power level of less than 20% (based on natural circulation through the core).
4/5.2.7 CONTROL ROD DRIVE ACCUMULATORS MT,1,N,GgN,D1T,1,0,N,10LO,PJE, RAT,I O0N, 4.2.7.1 The gas pressure and hydraulic oil level in each control rod drive scram accumulator shall be above the setpoint of Table 1, Operating Limits, for the control rod drives to be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2 ACTION:
- a. With an accumulator with a low gas pressure trip, or low oil level trip, operation may continue.
- b. With more than one accumulator with a low gas pressure trip, or more than one accumulator with a low hydraulic oil level trip, restore to less than 2 trips within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or commence shutdown and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Change No. d',,2',
Amendment No. JZ', Jd, 36
ERMILIMCE EQUIRDENTS 5.2.7.1 In accordance with Specification 5.2.15 Items 21 and 22.
BASES Control Rod Drive Accumulators In the event of significant loss of oil or of gas pressure in any of the 29 control rod drive accumulators, the associated control rod will lose capability for scram. The safety system incorporates only a PARTIAL SCRAM for this malfunction, because the control rod will still scram at the inoperable
' accumulator setpoint. The arrangement for the trip of these two parameters is such that it requires a low oil level trip and a low gas pressure trip from any combination of accumulators to cause the PARTIAL SCRAM. The system incorporates an audible and visual alarm for low oil level or low gas pressure-in any accumulator. The control rod will insert even with an inoperable accumulator because the capability for an electric motor driven insertion will be unaf fected.
Amendment)fI j
36a
MINIMUM FREQUENCIES FOR TESTING. CALIBRATING. AND/OR CHECKING OF INSTRUMENTATION - (cont'd)
Channels Action Minimum Frequency
- 21. CRD Accumulators Low Test Prior to each plant startup Oil Level Trip Relay if test has not been per' formed within 30 days.
- 22. CRD Accumulators Low Test Prior to each plant startup Gas Pressure Trip if test has not been per-Relay formed within 30 days.
Check Weekly.
pressure indication
- 23. Turbine Stop Valve Test Prior to each plant startup if test has not been per-formed within 30 days.
- 24. Reactor Pressure Calibration At each refueling shutdown.
(RPTS)
- 25. Reactor Water Level Calibration At each refueling shutdown.
(RPTS)
- 26. Reactor Safety Valve Check Monthly.
Position Indication Calibration At each refueling shutdown.
- Test shall include tripping of the scram relays K-114.
5.2.16 Corrosion test coupons shall be inserted in the forced circulation loop to evaluate the corrosion deterioration of chromium-molybdenum piping; and that piping shall be replaced if the reduction in pipe wall thickness, as indicated by weight loss and metallographic evaluation of the test coupons, is greater than 0.190 inches. The replacement piping shall be stainless steel or chall be clad internally with stainless steel and shall meet the design requirement of Section 2.3.2.
Ch. )(, ,2' Amendment E. J[,% %
5-10
1 i
j TABLE 1 - OPERATING LIMITS - (cont'd) .
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! CONDITION CHANNEL OR SENSOR SET POINT ACTION KEYSWITCH BYPASS PROVISION
- 10. Turbine Turbine Building > 90% full open
- 1) Full Scram 1) May be bypassed
, Building Steam steam isolation travel 2) Shutdown condenser during testing.
j 1 solation valve closure 2) May be bypassed
- Valve Not relays 1 or 2 during plant startup
)
Fully Open l
l 11. Turbine Stop Limit switch Table 4.0.2.2.1-1 Partial scram 1) May be bypassed j Valve Not during testing.
1 Fully Open 2) May be bypassed when-ever the turbine load
, y' is less than 10 Mwe.
E j 12. Iow 011 Level Limit switches Table 4.0.2.2.1-1 Trip (Half-Partial 1) May be bypassed In Any Control scram) during testing and i Rod Drive maintenance.
l g Accumulator 2) May be bypassed prior j @ to withdrawing con-i g trol rods in order to a @ charge accumulators. +
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- 13. Low Gas Pressure switches Table 4.0.2.2.1-1 Trip (Half-Partial 1) May be bypassed
- 3 Pressure In scram) during calibration, i Any Control testing, and Rod Drive maintenance.
Accumulator 2) May be bypassed prior j
b to withdrawing con-trol rods in order to g
I, I charge accumulators.
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l DAIRYLAND POWER COOPERATIVE l
l LAC-12018 DECEMBER. 17, 1986 l
CURRENT PAGES OF TECilNICAL SPECIFICATIONS 1 '
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t 2.8.4 The drive mechanisms shall have individual scram accumulators which drive the hydraulic motors and which shall be counceted to the gas charging system and to the hydraulic chargina system through individual check valves.
2.8.5 Each control rod shall be decelerated near the end of its scram stroke by an internal hydraulic dashpot action. '
2.8.6 A rod test circuit shall permit the Eithdrawal and*cesting of one selected rod when the rod test key switch is turned on, when one of the rods has been sc1ceted for testing, when all other rods are full in, and when the period exceeds 7 see on both source range ch'annels.
This test circuit shall measure the time from the dropping out of the "All Rods Scram" relay to the indication of full insertion of the rod.
When the rod test key switch is turned on, occurrence of a period less than 7 see on either of the cource range channels shall initiate a full scram. . . ; ;
2.8.7 Sustained loss of voltage to Reactor Building Motor Control Center 1A.(which supplies the hydraulic charging pumps and the control rod
,- drive motors), or low gas pressure, or a low Icvel of hydraulic fluid in any scram accumulator shall initiate safety action as specified in
.) Table 1. -
2.9 CONTROL SYSTEttS 2.9.1 The power level of the reactor shall be adjusted manually
' by the positioning of control rods or by changes in forcedthe circulation pump speed, or automatically by pressure controlled changes in the forced circulation pump speed.'
2.9.2 The position of the scoop tubes which control the forced ion circulation pump speed shall be controlled manually or automatically by the pressure control system.l -
2.9.3 Delete . .
2.9.4 An Initial Pressure Regulating System shall assume control of turbine inlet valves at low pressures so as to maintain turbine inlet pressure within a controlled band. The high pressure set point of the control band shall normally be set below the operating set point of the
- forced circulation pump automatic control system. To maintain rated turbine inlet pressure, the Initial Pressure Regulating System may be used without use of the forced circulation pump automatic control system. -
ChangeNo./,/,4 e.
- 2700 -
LIMITING SATETY SYSTEM SETTINGS BASES FOR SECT _IO!! _d,r) 2_2
!'ain Steam Isolation Valves - (Con't'd) .
~~
Operation of the reactor at pressures Icwer than 1000 psig is permitted only when the reactor is starting up or shutting down -
with steam flow rates < 100,000 lbs/hr. The low main steam pressure channels are bypassed during,this time to prevent auto-matic closure of the valve on low reactor pressure.
The Containment Building mal'n steam isolation valve is also automatically closed on either low condenser vacuum or low reactor water leve). In any event, closure of the containment Building or Turbine Building main steam isolation valve will initiate a scram and will also initiate operation of the shut-down condenser. These actions anticipate the pressure and flux transients that occur as a result of isolation valve closure.
Closure of the turbine stop valve initiates a PARTIAL SCRAM.
This scran anticipates the pressure, neutron flux, and heat flux increase that would result from rapid closure of the turbine stop valvo. Transient' analyses indicate that the reactor power would go to a peak of 260% of RATED Tl!ERMAL POWER if no credit is
}- taken for a period nor partial scrani. Because of the Doppler shutdown effect and the time lag in heat flux, the fuel claddine Safety Limit would not be exceeded. The opening of the turbine bypass valve (for which credit is not taken) prevents the contin- i ued buildup of the reactor vessel pressure. In the event that the i bypass valve does not open, the operation of the shutdown condenser l is initiated at 1325 psig and thereby prevents further pressure .
increase, as would safety valve operation should pressure reach their settings.
Control Rod Drive Accumulators In the event of significant loss of oil or of gas pressure in any of the 29 control rod drive accumulators, the associated control
. rod will lose capability for scram. The safety system incorpor- l atos only a PARTI AL SCRAM for low oil level or low gas pressure :
in any accumulator, because the control rod will scram even at i I
the inoperable accumulator scram setpoints. The capability for an electric motor driven insertion will also be unaffected. l Miendment No. g g el
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4.2.4.3 Deleted 4.2.4.4 The reactor shall not be operated at a power level above 1 Hwt with less than 72 fuel assemblies installed in the reactor.
4.2.4.5 The reactor shall have a negative temperature coefficient for all moderator temperatures f rom ambient to 557,F or shall be preheated to obtain a negative temperature coef ficient prior to withdrawal of control rods.
4.2.4.6 The core shall be suberitical by a least 0.5% delta k/k in the cold clean condition with the rod of maximum worth in its fully withdrawn position and with all other rods fully inserted.
4.2.4.7 The reactor may be operated with control rod drives inoperable provided that the associated rods are secured in the fully inserted or fully withdrawn position by electrically disconnecting the clutch and drive member and provided that all other requirements of these specificiations are met.
4.2.4.8 If an unexplainable change of greater than 0.6 percent in core reactivity is observed in a core which has undergone no physical change, the reactor shall be shut down. Except as required to investigate the reactivity change, the reactor shall not be operated until a satisfactory reason for the change has been found.
(
j 4.2.4.9 Following core reloading and/or core rearrangement, operation will be discontinued if the difference between the observed and predicted value of core reactivity exceeds 2 percent. If this difference is exceeded, the effect of the difference on further operation will be evaluated before operation is continued.
Amendeont No. AA,47
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4.2.6.7 During' operation with the nuclear instrusentation channels in 2 of 4 -
) trip logic, at least three of nuclear channels 5, 6, 7 and 8, including their autoestic gain control subsystem channels, shall be OPERABLE. If nuclear channel 5 or 6 is inoperable, its scras contacts shall be placed in the trip position. If power is de-escalated, the tripped channel's output shall be
- bypassed prior to entering 1 of 2 logic, subject to Section 4.2.6.1 require-ments. If nuclear channel 7 or 8 is inoperable in a manner affecting the .
operability of its corresponding power-flow channel, the power-flow channel shall be bypassed, pursuant to the time limitations of Section 4.2.6.1, and the scram contacts of the nuclear channel shall be placed in the trip position. .
4.2.6 8 Safety channels directly backed up by an identical channel or- -
channels may be bypassed for maintenance or testing. Safety channels in the-partial scram circuit may be bypassed for maintenance or testing for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
'4.2.6.9 Both reactor forced circulation pumps shall be aute,eatically shut down by a high reactor pressure signal or by a low reactor water level signal.
Bases - The RPTS is a diverse and independent backup except for common current sensing loops to the nonnal scrar system for rapid shutdown of the reactor.
To protect the primary system from an ATWS event in which either MSIV closes at power, thus eliminating the main condenser as a heat sink, the recirculation pumps must be shut down to prevent damage to the primary system due to high pressure. A rapid shut down of the recirculation pumps has the effect of I causing an increase in the moderator voids in the reactor core. A substantial negative reactivity results and the power and pressure surges that might otherwise occur in the most limiting transient (MSIV closure) are substantially reduced. With the recirculation pumps shut down, the reactor power will be q reduced to a steady state power level of less than 20% (based on natural circulation through the core).
4.2.7 -
veleted -
36 ChangeNo./,/[,
Amendment No. 2 . 36
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) MINIHUM FREQUENCIES FOR TESTING, CALIBRATING, AND/OR CHECKING OF INSTRUMENTATION - (cont'd)
Channels Action Minimus Frequency
. 21. CRD Accumulators Low Test Prior to each plant startup Oil Level Scram Relay if test has not been per .
formed within 30 days.
- 22. CRD Accumulators Low Test Prior to each plant startup j Cas Pressure Scram if test has not been per-Relay formed within 30 days.
Check pressure Weekly.
indication l 23. Turbine Stop Valve Test Prior to each plant startup if test has not been per-formed within 30 days.
- 24. Reactor Pressure Calibration At each refueling shutdown.
(RPTS)
}
l 25. Reactor Water Level Calibration At each refueling shutdown.
l (RPTS) l l
l 26. Reactor Safety Valve Check Monthly.
Position Indication Calibration At each refueling shutdown.
i
- Test shall include tripping of the scram relays K-114.
l 5.2.16 Corrosion test coupons shall be inserted in the forced circulation loop to evaluate the corrosion deterioration of chroelum-molybdenum piping; and that piping shall be replaced if the reduction in pipe wall thickness, as indicated by weight loss and metallographic evaluation of the test coupons, is greater than 0.190 inches. The replacement piping shall be stainless steel or ;
shall be clad internally with stainless steel and shall meet the design requirements of Section 2.3.2.
1 5-10 Amendment No. $f, 36,3 g l
_ . . . . . . . . . 2 _ - _. ._. _. _ _ _ - _ _ -_. _. _ - _ _ _ _ _ . . . - _ - . _ _ _s...;
_--_ u.,.,... . . _ _ .
%d , O . , . J i . .
TABLE 1 - OPERATING LIMITS - (cont'd) . . ,
KEYSWITCH BYPASS CONDITION CHANNEL OR SENSOR SET POINT ACTION PROVISION
- 10. Turbine Turbine building > 90% full open 1) Full scram 1) May be bypassed
. Building Steam steam isolation travel 2) Shutdown condenser during testing.
, Isolation valve closure operates 2) Hay be bypassed Valve Not relays 1 or 2 during plant startup Fully Open or shutdown.
- 11. Turbine Stop Limit switch Table 4.0.2.2.1-1 Partial scram 1) May be bypassed
'; Valve Not during testing.
Fully Open 2) May be bypassed when-
- ever the turbine load is less than 10 Hwe.
Y I% Table 4.0.2.2.1-1 1) May be bypassed l 12. Low 011 Level Limit switches Partial scram i In Any Control during testing.
Rod Drive 2) May be bypassed prior Accumulator to withdrawing con-trol rods in order to charge accumulators.
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- 13. Low Cas Pressure switches Table 4.0.2.2.1-1 Partial scram 1) May be bypassed Pressure In during calibration Any Control and testing.
- 2) May be bypassed prior g Rod Drive Accumulator to withdrawing con-e
" trol. rods in order to charge accumulators.
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