ML18057A411

Proposed Tech Specs Deleting Sections 3.1.1e & 4.4 & Associated Basis & Changing Section 3.1.5 Basis as Indicated

ML18057A411
Person / Time
Site:	Palisades
Issue date:	08/21/1990
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18057A409	List: ML18057A407 ML18057A410 ML18057A411
References
NUDOCS 9008300141
Download: ML18057A411 (18)

Text

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A

--SECTION PAGE NO 4.0 SURVEILLANCE REQUIREMENTS 4-1

4. 1 INSTRUMENTATION AND CONTROL 4-:1 4.1.1 Overpressure Protection Systems 4-1 Table 4 .1.1 Minimum Freauencies for Checks, Calibrations and Testing of Reactor Protective System 4-3 Table 4.1.2 Minimum Freauencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls 4-6 Table 4.1.3 Minimum Freauencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls 4-10 4.2 EQUIPMENT AND SAMPLING TESTS 4-13 Table 4.2.1 Minimum Freauencies for Sampling Tests 4-14 Table 4.2.2 Minimum Freauencies for Eauipment Tests 4-15 Table 4.2.3 HEPA Filter and Charcoal Adsorber Systems 4-15c 4.3 SYSTEMS SURVEILLANCE 4-16 Table 4.3.1

• Primary Coolant Sys~em Pressure Isolation Valves 4-19 Table 4.3.2 Miscellaneous Surveillance Items 4-23 4.4 Deleted 4-24 I 4.5 CONTAINMENT TESTS 4-25

4. 5 ~ 1 Integrated Leakage Rate Tests 4-25 4.5.2 Local Leak Detection Tests 4-27 4.5.3 Recirculation Heat Removal Systems 4-28a 4.5.4 Surveillance for Prestressing System 4-29 4.5.5 End Anchorage Concrete Surveillance 4-32 4.5.6 Containment Isolation Valves 4-32 4.5.7 Deleted 4-32a 4.5.8 Dome Delamination Surveillance 4-32a 4.6 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS 4-39

4. 6. 1 Safety Injection System 4-39 4.6.2 Containment Spray System 4-39 4.6.3 Pumps 4-39 4.6.4 Valves (Deleted) 4-40 4.6.5 Containment Air Cooling System 4-40 4.7 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-42 4.7.1 Diesel Generators 4-42 4.7.2 Station Batteries 4-42 4.7.3 Emergency Lighting 4-43 4.8 MAIN STEAM STOP VALVES 4-44 4.9 AUXILIARY FEEDWATER SYSTEM 4-45.

4: 10 REACTIVITY ANOMALIES 4-46 4 .11 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-47 Table 4.11-1 Radiological Environmental Monitoring Program 4-49 Table 4.11-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 4-56 iv 900~300141* 900021

• Amendment No. Z7, ~S. ~z. ~7.

PDR ADOCK 05000255 r r ~$. U, l0S, US; P PNU TSP0790~0371A-NL02

3. 1 PRIMARY COOLANT SYSTEM Applic~biliJJ' Applies to the operable status of the primary coolant system.

Objective To specify certain conditions of the primary coolant system which must be met to assure safe reactor operation.

Specifications 3 .1.1 Operable Components

a. At least one primary coolant pump or one shutdown cooling pump with a flow rate greater than or eaual to 2810 gpm shall be. in operation whenever a change is being made in the boron concentration of the primary coolant and the plant is operating in cold shutdown or above, except during an emergency loss of coolant flow situation. Under these circumstances, the boron concentration may be increased with no primary coolant pumps or shutdown cooling pumps running.

b. Four primary coolant pumps shall be in operation whenever the reactor is operated above hot' shutdown, with the following exception:

Before removing a pump from service, thermal power shall be reduced as specified in Table 2.3.1 and appropriate corrective action implemented. With one pump out of service, return the pump to service within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (return to four-pump operation) or be in hot shutdown (or below) with the reactor tripped (from the C-06 panel, opening the 42-01 and 42-02 circuit breakers) within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Start-up (above hot shutdown) with less than four pumps is not permitted and power operation with less than three pumps is not permitted.

c. The measured four primary coolant pumps operating reactor 6

vessel flow shall be 124.3 x 10 lb/hr or greater, when corrected to 532°F.

d. Both steam generators shall be capable of performing their heat transfer function whenever the average temperature of the primary coolant is above 325°F.

e. Deleted I 3-lb Amendment No Jl, $$, ll$, ll9>

TSP0790-0371A-NL02

3.1 PRIMARY COOLANT SYSTEM (Continued)

3. 1. 1 Operable Components (Continued)

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f. Nominal primary system operation pressure shall not exceed 2100 psia.

g. The reactor inlet temperature (indicated) shall not exceed the value given by the following eauation at steady state power operation:

Tilt*~ 543.3 + .0575(P-2060) + 0.00005(P-2060)**2 + 1.173(W-120) -

n e .0102(W-120)**2 Where: Ti 1 = reactor inlet temperature in F 0 n et p nominal operating pressure in psia 6

W= total recirculating mass flow in 10 lb/h corrected to the operating temperature conditions.

When the ASI exceeds the limits specified in Figure 3.0, within 15 minutes, initiate corrective actions to restore the ASI to the acceptable region. Restore the ASI to acceptable values within one hour or be at less than 70% of rated power within the following two hours.

If the measured primary coolant system flow rate is greater than 130 M lbm/hr, the maximum inlet temperature shall be less than or eaual to the TI LCO at 130 M lbm/hr.

n 1 et 3-lc Amendment No it, Jt, SJ, tt7, ttS>

TSP0790-0371A-NL02

3.1 PRIMARY COOLANT SYSTEM (contd)

Basis (Contd)

The FSAR safety analysis was performed assuming four primary coolant pumps were operating for accidents that occur during reactor operation. Therefore, reactor startup above hot shutdown is not permitted unless all four primary coolant pumps are operating.

Operation with three primary coolant pumps is permitted for a limited time to allow the restart of a stopped pump or for reactor internals vibration monitoring and testing.

Reauiring the plant to be in hot shutdown with the reactor tripped from the C-06 panel, opening the 42-01 and 42-02 circuit breakers, assures an inadvertent rod bank withdrawal will not be initiated by the control room operator. Both steam generators are reauired to be operable whenever the temperature of the primary coolant is greater than the design temperature of the shutdown cooling system to assure a redundant hear removal system for the reactor.

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I The transient analyses were performeg assuming a vessel flow at hot zero power (532°F) of 124.3 x 10 lb/hr minus 6% of account for flow measurement uncertainty and core flow bypass. A DNB analysis was performed in a parametric fashion to determine the core inlet temperature as a function of pressure and flow for which the minimum DNBR is eaual to 1.17. This analysis includes the following uncertainties and allowances: 2% of rated power for power 3-2 Amendment No l~. jl, ltS, tit,,

TSP0790-0371A-NL02

3.1 PRIMARY COOLANT SYSTEM (Cont'd)

Basis (Cont'd) measurement; +/-0.06 for ASI measurement; +/-50 psi for pressurizer pressure; +/-7°F for inlet temperature; and 3% measurement and 3%

bypass for core flow. In addition, transient biases were included in the derivatio~ ~f the following eauation for limiting reactor inlet temperature:

4 Tinlet ~ 543.3 + .0575(P-2060) + 0.00005(P-2060)**2 + l.173(W-120) -

. 0102 (W-120) **2 The limits of validity of this eauation are:

1800 ~ Pre~sure ~ 2200 psia x lb/h 100.0 x 10 ~ Vessel Flow ~ 130 106 ASI as shown in Figure 3.0 With measured primary coolant system flow rates > 130 M lbm/hr, limiting the maximum allowed inlet temperature to the Tinlet LCO at 130 M lbm/hr increases the margin to DNB for higher PCS flow rates.

The Axial Shape Index alarm channel is being used to monitor the ASI to ensure that the assumed axial power profiles used in the development of the inlet temperature LCO bound measured axial power profiles. The signal representing core power (Q) is the auctioneered higher of the neutron flux power and the Delta-T power.

The measured ASI calculated from the excore detector signals and adjusted for shape annealing (YI) and the core power constitute an ordered pair (Q,YI). An alarm signal is activated before the ordered pair exceed the boundaries specified in Figure 3.0.

The reauirement that the steam generator temperature be ~ the PCS temperature when forced circulation is initiated in the PCS ensures that an energy addition caused by heat transferred from the secondary system to the PCS will not occur. This reauirement applies only to the initiation of forced circulation (the start of the first primary coolant pump) when the PCS cold leg temperature is < 430°F. However, analysis (Reference 6) shows that under limited conditions when the Shutdown Cooling System is isolated from the PCS, forced circulation may be initiated when the steam generator temperature is higher than the PCS cold leg temperature.

References (1) Updated FSAR, Section 14.3.2.

(2) Updated FSAR, Section 4.3.7.

(3) Deleted I (4) ANF-87-lSO(NP), Volume 2, Section 15.0.7.1 (5) ANF-88-108 (6) Consumers Power Company Engineering Analysis EA-A-NL-89-14-1 3-3 Amendment No n, '1, U7, tu' UtJ TSP0790-0371A-NL02

'3.1 PRIMARY COOLANT SYSTEM (contd)

The steam generator tube leakage limit ensures that the dosage I contributed from the tube leakage will be limited to a small I fraction of Part 100 linrits in the event of a steam generator tube I rupture or steam line break. The leakage limit also ensures that I steam generator tube integrity is maintained in the event of a mairi I steam line rupture or under LOCA conditions. I Operation during short periods of time when the leakage measurement sensitivity is reduced is provided for by an added allowance to the leakage limit. Leakage limits are not reauired when the plant is not at power.

References (1) FSAR, Amendment 15, Question 4.3.

(2) FSAR, Section 11, Table 11-6.

3-22 Amendment No V/JJ TSP0790-0371A-NL02

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES August 21, 1990 11 Pages TSP0790-0371A-NL02

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPE~1JIX A

___SECTION . DESCRIPTION PAGE NO 4.0 . SURVEILLANCE REQUIREMENTS 4-1

4. 1 INSTRUMENTATION AND CONTROL 4-1

4. 1.1 Overpressure Protection Systems 4-1 Table 4.1.1 Minimum Frequencies for Checks, Calibrations and Testing of Reactor Protective System 4-3 Table 4.1.2 Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls 4-6 Table 4.1.3 Minimum Frequencies _for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls 4-10 4.2 EQUIPMENT AND SAMPLING TESTS 4-13 Table 4.2.1 Minimum Frequencies for Sampling Tests 4-14 Table 4.2.2 Minimum Frequencies for Equipment Tests 4-15 Table 4.2.3 HEPA Filter and Charcoal Adsorber Systems 4-15c 4.3 SYSTEMS SURVEILLANCE 4-16 Table 4.3.1 Primary Coolant System Pressure Isolation Valves 4-19 Table 4.3.2 Miscellaneous Surveillance Items .4-23 4.4 PRIM..'\&¥ GOOJ:..AJJT SYST~ INTEGRITY TESTING lJ.e. te.+~<:.f 4-24 I 4.5 CONTAINMENT TESTS 4-25 4.5.1 Integrated Leakage Rate Tests ...4-25 4.5.2 Local Leak Detection Tests 4-27 4.5.3 Recirculation Heat Removal Systems* 4-28a Y 4.5.4 Surveillance for Prestressing System 4-29 4.5.5 End Anchorage Concrete Surveillance 4-32 r 4.5.6. Containment Isolation Valves 4-32 y 4.5.7 Deleted 4-32a I" 4.5.8 Dome Delamination Surveillance 4-32a .Y 4.6 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS 4-39 4.6.1 Safety Injection System 4-39 4.6.2 Containment Spray System 4-39 4.6.3 Pumps 4-39 4.6.4 Valves (Deleted) 4-40 4.6.5 Containment Air Cooling System 4-40 4.7 EMERGENCY POWER SYSTEM.PERIODIC TESTS 4-42 4.7.1 Diesel Generators 4-42 4.7.2 Station Batteries 4-42 4.7.-3 Emergency Lighting 4-43 4.8 MAIN STEAM STOP VALVES 4-44 4.9 AUXILIARY FEEDWATER SYSTEM 4-45 4.10 REACTIVITY ANOMALIES 4-46 4.11

• RADIOLOGICAL ENVIRONMENTAL MONITORING 4-47 Table 4.11-1 Radiological Environmental Monitoring Program 4-49 Table 4.11-2

• Reporting Levels for Radioactivity Concentrations in Environmental Samples 4-56 iv Amendment No. 37, is, 63, 67, 0, U, 108, ,l~

&eptembe1 5, 1989 TSP0689-0136-NL04

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3. l

• PRIMARY COOLANT SYSTEM

_Apelicability Applies to the operable status of the primary coolant system.

Objective To specify certain conditions of the primary coolant system which must be met to assure safe reactor operation.

Specifications

3. 1. l . Operable Components

a. At least one primary coolant pump or one shutdown cooling pump with a flow rate greater than or equal to 2810 gpm shall be in operation whenever a change is being made in the boron concentration of the primary coolant and the plant is operating in cold shutdown or above, except during art emergency loss of coolant flow situation. Under these circumstances, the boron concentration may be increased with no primary coolant pumps or shutdown cooling pumps running.

b.* Four primary coolant.pumps shall be in operation whenever the reactor is operated above hot shutdown. with the following exception:

Before removing a pump from service, thermal power shall be reduced as specified in Table 2.3.l and appropriate corrective action implemented. With one pump out of service, return the pump to service within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (return to four-pump operation)

-* or be in hot shutdown (or below) with the reactor tripped (from the C-06 panel, opening the 42-01 and 42-02 circuit breakers) within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Start-up (above hot shutdown) with less than four pumps is not permitted and power operation with less than three pumps is not permitted.

c *. The measured four primary coolant pumps operating reactor vessel flow shall be 124.3 x 106 lb/hr or greater; when corrected to 532°1.

d. Both steam generators shall be capable of performing their heat transfer function whenever the average temperature of the primary coolant is above 32S 0 P.

D.e.. l c... +.e...cJ.

e. Mawimtml p* 1 mer;y eystem preesu~* differefttials shall noe e*eeed /

cbe felleving:

-(1) Deleted 3-lb.

Amendment No Jl, SJ. UI, M1; Deeemhe.* 12, 19&a.

TSP1088-0181-NL04

~. 1 e

PRIMARY COOLANT SYSTEM (Continued)

3. 1.1 Operable Components (Continued)

( Hydrostatic tests shall be conducted in accorda applicable paragraphs of Section XI ASME Boil &

essure Vessel Code (1974). Such tests sh 1 be con cted with sufficient pressure on the secondary side of the steam generators to restrict pri ary to secondary pressure ifferential to a maximum of 380 psi. Maximum hydrostati test pressure shall not xceed 1.1 Po plus 50 psi where is nominal operat g pressure.

(3) Primary side l.eak operating pressure~

with applicable fractu materials and shall be s differential pressure steam generator tubes is not greater than 1

• (4) Maximua **~ondary ydrostatic tea ressure shall not exceed 1250 psi

• A minimua tempera ure of 100°F ia required. On ten cycle* are permitt d.

(5) ondary leak test pressure not exceed A minimum temperature of required.

(6) rforming the.tests identified in 3.1.1.e(

.l.e(5), above, the secondary pressure shall ot xceed the primary pres.sure by more than 350 psi.

f. Nominal primary system operation pressure shall not exceed 2100 paia.

-* g. The reactor inlet temperature (indicated) shall not exceed the value given by the following equation at steady state I power operation:

Ti l 8 t S 543.3 + .0575(P-2060) + O.OOOOS(P-2060)**2 + 1.173(W-120) - I n * .0102(W-120)**2' I Where: Tinlet p

• reactor inlet temperature in r*

• nominal operating pressure in psia 6 W

• total recirculating mass flow in 10 lb/h --.

corrected to the operating temperature conditions.

When the ASI exceeds the limit* specified in Figure 3.0, within I 15 minute*, initiate corrective actions to re*tore the ASI to I .

the acceptable region. Restore th* ASI to acceptable values I within one hour or be at less than 70% of rated power within I the following two hours. I If the measured primary coolant system flow rate is greater I

.than 130 K lbm/hr, the maximum inlet temperature shall be I less than or equal to the Tinlet LCO at 130 K lbm/hr *. I 3-lc Amendment No Jl, JI, U., tl7, JI.~

Me~ . .~er lS, 1988 TSP1088-0181-NL04

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3. l PRIMARY COOL~ SYSTEM (Cont'd)

3. l. l Operable Components (Cont'd)

h. Forced circulation (starting the first primary coolant pump) I shall not be initiated unless -one of the following conditions is I-met: I (1) Primary coolant cold leg temperature is > 430°F. /

(2) PCS cold leg temperature is S 430°F and S/G secondary /

temperature is less than PCS cold leg temperature. /

(3) Shutdown cooling is isolated from the. PCS AND PCS 'cold leg /

temperature is > 210°F AND S/G secondary temperture is less /

than 100°F higher than PCS temperature. /

(4) Shutdown cooling is isolated from the PCS AND PCS cold leg I temperature is ~ 170°F and ~ 210°f AND S/G secondary I temperature is less than 20°F higher than PCS cold leg I

• temperature. I (5) *Shutdown cooling is isolated from the PCS AND PCS cold leg /

temperature is ~ 120°F and < 170°F AND S/G secondary I temperature is less than 100°F higher than PCS cold leg /

temperature. I

i. The PCS shall not be heated or maintained above 325°F unless a minimtim of 375 kW of pressurizer heater capacity is available from both buses lD and lE. Should heater capacity from either bus lD and lE fall below 375 kW, either restore the inoperable heaters to provide at least 375 kW of heater capacity from both buses lD and lE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or 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 />.

Basis When primary.coolant boron concentration is being changed, the*

process must be uniform throughout the primary coolant system volume to prevent stratification of primary coolant at lower boron concentration which could result in a reactivity insertion.

Sufficient mixing of the primarrcoolant is assured if one shutdown cooling or one primary coolant pump is in ~peration. (l) The shutdown cooling pump will circulate the primary system volume in less than 60 minutes when operated at rated capacity. By imposing a minimum shutdown coolinR pump flow rate of 2810 gpm, sufficient time is provided for the operatof jo terminate the boron dilution under 5

asymmetric flow* conditions. The pressurizer volume is relatively inactive, therefore will tend to have a boron concentration higher than rest of the primary coolant system during a dilution operation.

Administrative proc*edures will provide for use of pressuri~er sprays

• to maintain a nominal spread between the boron concentration in ( 2)

'the pressurizer and the primary system during the addition of boron.

3-ld Amendment No 67. SJ. 117. llS. 131 April 26, 1990 TSP0290-0262-NL04

.}

. 3. l "'RIMA.RY CO.NT SYSTEM (contd)

~ (Contd) rhe FSAR safety analysis was performed assuming four primary coolant pumps were operatin~ for accidents that occur during reactor operation. Therefore, reactor startup above hot shutdown is not permitted unless all four primary coolant pumps are operating.

Operation with three primary coolant pumps is permitted for a limited time t_o allow the restart of a stopped pump or for reactor i: ~rnals vibration monitoring and testing.

Requiring ::'."le plant to be in hot shutdown with the reactor tripped from the C-06 panel, opening the 42-01 and 42-02 circuit breakers, assures an inadvertent rod bank withdrawal will not be initiated by the control room operator. Both steam generators are required to be operable whenever the temperature of the primary coolant is greater than the design temperature of the shutdown cooling system to assure a redundant hear removal system for the reactor.

3 tial of 1380 psiC > can be withstood by a tube u thinned to.. 36% of its original nominal wall

( 64% degrada:t.j,on)

, while maintaining:

(1) A factor-of safety of three between, e actual pressure differential and the pressure diffuential required to cause bursting-... .- ,..

(2) Stresses within the y_ield'"~tress for. Inconel 600 at operating temperature.<.

_,/,' *** .. ,_

(3) Acceptable stre$s~s

/

during accident *...

conditions.

Secondary side hydro~~~c and leak test~~g requirements are consistent with AsME BPV Section XI (1971). The differential maintains stre~s~s in the steam generator tube walls within code allowable st.re'sses. '

- ~

m!~ ste~

The temperature of 100°F for pressurizing the

~:~:;. sec:amda~ide--!s--s&t- by._the ND1'T of the manway~er The transient analyses were perf ormeg assuming a vessel flow at hot zero power (532°F) of 124.3 x 10 lb/hr minus 6% of account for flow measurement uncertainty and core flow bypass. A DNB analysis was performed in a parametric fashion to determine the core inlet temperature as a function of pressure and flow for which the minimum DNBR is equal to 1.17. This analysis includes the following uncertainties and allowances: 2% of rated power for power 3-2 Amendment No ZG. Jl, lll.~

-April 26, 1990.

TSP0889-0101-MD01-NL04

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3. l PRIMARY COOLANT SYSTEM (Cont'd)

~ -(Gont'd) measurement; :0.06 for ASI measurement; :SO psi for pressurizer pressure; !7°F for inlet temperature; and 3% measurement and 3%

bypass for core flow. In addition, transient biases were included in the derivatio? 9f the following equation for limiting reactor inlet 4

temperature:

Tinlet S 543.3 + .0575(P-2060) + O.OOOOS(P-2060)**2 + l.173(W-120) -

.0102(W-120)**2 The limits of validity of this equation are:

1800 S Pre~sure S 2200 psia 100.0 x 10 S Vessel Flow S 130 x 10 6 lb/h ASI as shown in Figure 3.0 With measured primary coolant system flow rates > 130 M l~~/hr, limiting the maximum allowed inlet temperature to the T LCO at

. 1 n 1 et 130 M lbm/hr increases the margin to DNB for higher PCS flow rates.

The Axial Shape Index alarm channel is being used to monitor the AS! to ensure that the assumed axial ppwer profiles used in the development of the inlet temperature tco* bound measured axial power**

profiles. The signal representing core power (Q) is the auctioneered higher of the neutron flux power and the Delta-T power *.

The measured ASI calculated from the excore detector signals and adjusted for shape annealing (Y ) and the core power constitute an 1

ordered pair (Q,Y ). An alarm signal is activated before the 1

ordered pair exceed the boundaries specified in Figure 3.0.

The requirement that the steam generator temperature be S the PCS temperature when forced circulation is initiated in the PCS ensures that an energy addition caused by heat transferred from the secondary system to the PCS will not occur. This requirement applies only to the initiation of forced circulation (the start of the first primary coolant pump) when the PCS cold leg temperature is < 430°F. However, analysis (Reference 6) shows that under limited conditions when the Shutdown Cooling System is isolated from the PCS, forced circulation may be initiated when the steam generator temperature is higher than the PCS cold leg temperature.

References (1) Updated FSAR, Section 14.3.2.

(2) Updated FSAR, Section 4.3.7.

P-altsades 19BJl1984 Steam Cenerater E~aluatton and Repatr-

---

'~

I 1!.l'egram Report, SeetiQa 4, April lQ, ~934 I (4) ANF-87-lSO(NP), Volume 2, Section 15.0.7.l (5) ANF-88-108 *

(6) Consumers Power Company Engineering Analysis EA-A-NL-89-14-1 3-3

'Amendment No Jl, Jl, ll7, lll, )15~

April. 26, U!JO TSP0889-0101-MD01-NL04

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'*: 'i 'J J. l PRIMARY COOLANT. SYSTEM (Contd)

J. l. 5 Primarv Coolant System Leakage Limits Specification a, If the primary coolant system leakage exceeds l gpm and the source of .the leakage is not identified, reduce unidentified primary coolant system lealtage co less than 1 gpm within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or place the reactor in hoc shutdown condition within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*

b. If leakage from the primary co.olanc system exceeds 10 gpm, reduce primary coolant system leakage to less chaa 10 gpm within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or place the reactor.in hoc shucdow condition within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown condition within th*

following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. If the specific activity of the secondary coolant in a steam generator exceed* 0.1 uCi/gram dose equivalent I-131, the reactor shall be placed ia hoc shutdOVft within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within th* following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

d. The prim.ary to secondary leakage in*a sceaa generator shall not exceed 0.3 gp1a for any period of scsady state operation greater than 24 con*ecucive hours.

During periods of start-up and major load changes, vhe~ the leakage measurement senaitivicy is reduced, the calculated leak.age shall not exceed 0.6 gpm for any period of greater than 24 consecutive hours *

.-* fil!!.

Industry experience ha* shova that while a limited amount of leakage is expected from the primary coolant system, the unidentified portion of this leakage can be reduced co a threshold value of less than 1 gpm. Thie threshold value i* sufficiently lov to ensure early detection of additional leakage. Wbe11 th* 1ource of the leakage can be identified, cha condition shall be evaluacad to determine if operation can safety continue.

• Ju*tiflcatioa for continued operation with identified leakage in axe*** of 1 gpa 1bal.1 be docu.ented in writing and approved by th* Plant General Manager or hi* repreaentativa.

A aias111u11 allowable primary coolant sy*t** leak race of 10 gpm ha* been e1tabli1had. Thi* limitation do** not include the primary coolant pump seal leak-off* which is directed co cha volWll* control tank *. The 10 gpa limitation provide* allowance* for a liait*d amount of leakage from known sources whose presence will not interfere with the detection of unidentified leakage. A primary coolant system leak race in excess of 10 gpa i* indic-.

ative of a failure of sufficient mapicude co warrant shutdown for repair.

3-20 Amendment No. ZS, 95 January. JO, 1986 TSP0485-0184D-NL04

{!o r ~d'r\.. ft~ '/-7

,, o e--AUVJ ~ 1

\.!¥

3. l. PRI~.ARY COOLANT SYSTEM (Contd)

Basis (Contd)

The LO gpm limitation is well within the 40 gpm capacity of one charging pump which would be.available even under a loss of off-site power condition.

The initial 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period following indication of unidentified primary coolant system leakage in excess of l gpm, or total*primary coolant system leakage in excess of 10 gpm, provides sufficient time to facilitate identification and confirmation of the leakage source with the Plant being maintained in a stable condition. When the source ~f the leakage cannot be identified or reduced, th* following 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period is sufficient to brin.g the Plane to hoc shutdown

• condition in an orderly manner. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period which follows provides adequate time to bring the Plant to cold shutdown condition in an orderly fashion and to correct minor deficiencies. If major repairs are necessary, a cold shutdown condition would b* in order.

The limitations on secondary system specific activity ensure that the resultant off-site radiation* dos* will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dos* also includes the effects of a coincident l.O gpm primary co secondary cube leak in the steam gener~tor of the affected steam line and a concurrent loss of offsit* electrical power.

3-21 Amendment No. Zt, 95 January 30, 1986 TSP0485-0184D-NL04

3.l f'1>rf-* I~ 1:-~ h lint /,t~ le

• 1k

,,~ ,,,,.,,, ,;, ;"' "

u,..,/,r LOC;I . ~,.. e/t'l-i- .s

• and analysis have been performed shovtng that the effect, on

• the structur -E:~ of' r. tube, wa.U crack superimposed On-a-64

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gpm leakage ;u to provide less Operation during short periods of' time when the leakage measurement .

sensitivit:r is reduced is provided. for by an added allowance to the leakage limi.t. Leakage limits are not required when the plant is not at power.

References (l) FSAR, Amendment 15, Question 4.3.

(2) FSAR, Section .ll, Table U-6.

3-22 Amendment Yo ,Zfl, April 26, 197a

4.4 req,uiremcts tor p?'ima.z'7 cool.an~ system inte tor :pr"~ systc lloviug aor:&l opening,

a. e :prima:-/ coola:t system u er. it haa beeD opened..

be leak tested. at :iot

• 2135 ;>lig prior to the crlt!c&l.. A test tempera: shall be selected. such

&turatiO!l) pressure v1ll the d.itter~ti&l pres-gi-e&ter tha: l380 psi *

c. Whenever :iicd.1:1c&tio 1:1 the pri:llaz7 coolmt system t!la.t involve ne ccm;ionents greater the 2-uc:li*. d.iueter, t!le :iev r9Cei ve both & sun'a.c:e and iooS volumetric :eet a.:.i* applicable code

~q;uiremenu.

c. Whenever codifications t~e pr~ coolmt systa t!la.~ l.d!i on cc:::;ionen-:s 2~1.nch d!a:eter or smaller, ":he ve & su::."ace ex*:i -:ation.

~

or nor:al ope!l!ng, the i in ter:u ot

~/stem ~essure

~re:igth, at 2135 psig (~erst"

!'l*

.. egrit;r unc!:A:igeci.

ot tb.e :p~ -1 coolan~ system.

It tb.e sy tem dces :iot !eak pnssure + 50 psi; : 50 ~s i is no:":l!&l

t!.ozi)(l), it will"oe leak~- _cim"'.;ig I! the pressure goes above 2l35 p

ior:ial. operation.

es&.

, the vent I

I n 1:leezi p~or.:ed. to iemautr~te -=~t c ce *"1.taa~ood. by s. tuQe *.m.!!;i--lJ -;~e-i <:

ot 1a!a't7 o'! -:;::-ee 'bet*..-ee:i t~e &ctuL. ::ressu:-e di.

-:!:la pnssu:a c!i!!'ere:rt!a.l n~ui:ed t~ cs.~e 1:1-.i:ni=g.

11ald. st:ess !or Z:conel ~co at st:esses d~!ne a.cci!en~ :oc.ditioz.s.

- *-. ~*---'.

4.4 ~IMABY .C_90LABT SYSTEM DT$!L""":Y T!ST:ilG ( Coz:td.)

P.S ozi coii&poncts greatv tl:wl 2-1.nch d.bg~o~

iondestnc:t1 estiz:!.a gives a verr biil:l d.8gioee the 1ntegr1t,y ot the ~i.m.l'<rT

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