Text

Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control
	ML20111C276
Person / Time
Site:	Pilgrim
Issue date:	05/01/1996
From:	Boulette E; BOSTON EDISON CO.
To:	;
Shared Package
ML20111C275	List: BECO-96-042, Application for Amend to License DPR-35,revising Note 7 to Table 3.1.1,note 6 to Table 3.2.C.1 & Section 3/4.4, Standby Liquid Control; ML20111C276;
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ATTACHMENTB: REVISED TECHNICAL SPECIFICATION PAGES l

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l 3/4.1-2 l 3/4.1-4 3/4.2-19 3/4.2-20 3/4.2-22 3/4.4-1 3/4.4-2 B3/4.4-1 B3/4.4-2 I B3/4.4-3 i B3/4.4-4 l B3/4.4-5 ,

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l 9605160013 960501 PDR ADOCK 05000293 P PDR

PNPS Table 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Operable Inst. Modes in Which Function Trip Function Trip Level Setting Must Be Operable Action III Channels per Refuel Startup/ Hot Run Trio System (1)

Standbv Minimumi Avail.

X(7) X X A l 1 1 Mode Switch in Shutdown X(7) X X A 1 1 Manual Scram IRM A 4 High Flux 5120/125 of full scale Xt7) X (5) 3 X (5) A 3 4 Inoperative X(7)

APRM High Flux (15) (17) (17) X A or B 2 3 Inoperative (13) X(7) X(9) X A or B 2 3 A or B 3 High Flux (15%) 115% of Design Power X(7) X (16) 2 High Reactor Pressure 11063.5 psig X(10) X X A 2 2 High Drywell Pressure 12.22 psig X(8) X(8) X A 2 2 X(10) X X A 2 2 Reactor Low Water Level 111.6 in. Indicated Level SDIV High Water Level: X(2)(7) X X A l 138 Gallons 2 2 East 2 2 West 4 4 Main Steam Line Isolation Valve Closure 110% Valve Closure X(3)(6) X(3)(6) X(6) A or C 2 2 Turbine Control Valve 1150 psig Control Oil Fast Closure Pressure at Acceleration Relay X(4) X(4) X(4) A or D 4 4 Turbine Stop Valve 110% Valve Closure X(4) X(4) X(4) A or D Cicsure Amendment No.15, 5 2, SS, 92, ' ' ?, 423, ' 57,151,152,154,1 Si 3/4.1-2

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NOTES FOR TABLE 3.1.1 (Cont)

2. Permissible to bypass, with control rod block, for reactor protection system reset in refuel and shutdown positions of the reactor mode switch.

3. Permissible to bypass when reactor pressure is <576 psig.

4. Permissible to bypass when turbine first stage pressure is less than < 112 psig.

5. IRM's are bypassed when APRM's are onscale and the reactor mode switch is in the run position. ;

6. He design permits closure of any two lines without a scram being initiated.

7. When the reactor mode switch is in the Refuel position, the reactor vessel head is removed, and control rods are inserted in all core cells containing one or more fuel assemblies, these scram functions are not !

required.

8. Not required to be operable when pnmary containment integrity is not required. l

9. Not required while performing low power physics tests at atmospheric pressure during or after i refue!ing at power levels not to exceed 5 MW(t).

10. Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.

11. Deleted

12. Deleted

13. An APRM will be considered inoperable if there are less than 2 LPRM inputs per level or there is less than 50% of the normal complement of LPRM's to an APRM. l

14. Deleted

15. He APRM high flux trip level setting shall be as specified in the CORE OPERATING LIMITS )

REPORT, but shall in no case exceed 120% of rated thermal power.

16. He APRM (15%) high flux scram is bypassed when in the run mode.

I 17. The APRM flow biased high flux scram is bypassed when in the refuel or startup/ hot standby modes.

18. Deleted.

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Amendment No. 6,15,27,12,36,!17,!13,133,147,151,152,154 3/4.1-4

~ . - .. - . - - - _ _- -----___---_--- - ___--_-__-_--- __------_- --_- - - --- - - - - - - - - _ - _ - _ _ _ _ _ - - - - - _ - - - - _ - - - _ _ _ _ - - _ - - - - - - - - - - - _ - . - _ - _ _ - - _ _ . - - - - - - - _ - - - _ _

PNPS TABLE 3.2.C.1 INSTRUMENTATION THAT INITIATES ROD BLOCKS Operable Channels per Trio Function Required 1 Trin Function Minimum i Available Operational Conditions - Notes APRM Upscale (Flow Biased) 4 6 Run ,. (1)-

I APRM Upscale 4 6 Startup/ Refuel (1)(6) l APRM Inoperative 4 6 Run/Startup/ Refuel (1)l6) l APRM Downscale 4 6 Run (1) l Rod Block Monitor 2 2 Run, with limiting control rod (2)(5)

(Power Dependent) pattern, and reactor power > LPSP .

Rod Block Monitor 2 2 Run, with limiting control rod (2)(5) l Inoperative pattern, and reactor power > LPSP l Rod Block Monitor 2 2 Run, with limiting control rod (2)(5)

Downscale pattern, and reactor power > LPSP :

IRM Downscale 6 8 Startup/ Refuel, except trip is (1)(6) l bypassed when IRM is on its lowest range !

IRM Detector not in 6 8 Startup/ Refuel, trip is bypassed (1)(6) l Startup Position when mode switch is placed in run

IRM Upscale 6 8 Startup/ Refuel (1)(6) l

~

lRM Inoperative 6 8 Startup/ Refuel (1)(6) l t

Amendment No. 15,27,12,55,72,79,'10,129,123,'47 3/4.2-19 [

PNPS TABLE 3.2.C.1 (Cont)

INSTRUMENTATION THAT INITIATES ROD BLOCKS Operable instrument Channels per Trio Function Required Trio Function Minimum 1 Available Qgerational Conditions Notes SRM Detector not in 3 4 Startup/ Refuel, except trip is bypassed (1)(4)(6) l Startup Position when SRM count rate is 1100 counts /second or IRMs on Range 3 or above SRM Downscale 3 4 Startup/ Refuel. except trip is bypassed (1)(4)(6) l when IRMs on Range 3 or above SRM Upscale 3 4 Startup/ Refuel, except trip is by- (1)(4)(6) l passed when the IRM range switches are on Range 8 or above SRM inoperative 3 4 Startup/ Refuel, except trip is by- (1)(4)(6) l passed when the IRM range switches are on Range 8 or above Scram Discharge 2 2 Run/Startup/ Refuel (3)(6) l Instrument Volume Water Level - High Scram Discharge 1 1 Refuel / Shutdown (3)(6) l Instrument Volume-Scram Trip Bypassed Amendment No. 438, ' , ? 59 3/4.2-20

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l o. e' NOTES FOR TABLE 3.2.C-1

1. With the number of operable channels:

a. One less than required by the minimum operable channels per trip function' requirement, restore an inoperable channel to operable l status within 7 days or place an inoperable channel in the tripped condition within the next hour.

l b. Two or more less than required by the minimum operable channels l per trip function requirement, place at least one inoperable channel in the tripped condition within one hour.

2. a. With one RBM Channel inoperable:

(1) restore the inoperable RBM channel to operable status within i 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; otherwise place one rod block monitor channel in i i

the tripped condition within the next hour, and; !

l l (2) prior to control rod withdrawal, perform an instrument j function test of the operable RBM channel. 1

b. With both RBM channels inoperable, place at least one inoperable l rod block monitor channel in the tripped condition within one hour.

3. If the number of operable channels is less than required by the minimum l operable channels per trip function requirement, place the inoperable i channel in the tripped condition within one hour, i

4. SRM operability requirements during core alterations are given in Technical Specification 3.10.

5. RBM operability is required in the run mode in the presence of a limiting rod pattern with reactor power greater than the RBM low power setpoint (LPSP). A limiting rod pattern exists when:

MCPR < 1.40 for reactor power 2 90%

MCPR < 1.70 for reactor power < 90%

The allowable value for the LPSP is $ 29% of rated core thermal power. l

6. When the reactor mode switch is in the Refuel position, the reactor vessel head is removed, and control rods are inserted in all core cells containing one or more fuel assemblies, these Rod Block functions are not required.

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nccision 17' Amendment No. 15, 27, 12, 05, '7, 110, 100 3/4.2-22 l

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l

3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM

! Soecification: 1. When tested as specified in 3.13 Two SLC subsystems shall be ve y at each pump delivers l

" 8"8 ' "9" 8 8 8Y8 ""

OPERABLE.

head of 1275 psig. j Acolicabilitv: 2. Manually initiate one of the Run and Startup MODES an % Q id Control System loops and pump demineralized Ooeration with Inocerable wa er n e reactor vessel )

Eauiement eve monds on a S N ERED l

TEST BASIS.

A. With concentration of boron in "*

solution not within limits but

Y#" ** ****

> 8%, restore concentration of "#9* * * "Y8' i

boron in solution to within 4. Verify available volume of )

limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND 10 sodium pentaborate solution is l days from discovery of failure within the limits of Figure 3.4- l to meet the LCO. 1 or 2 4000 gallons every 24 l

"'8*

B. With one SLC subsystem inoperable for reasons other 5. Verify temperature of sodium than Condition A, restore SLC l

pentaborate solution is i subsystem to OPERABLE status > 48 F every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

within 7 days AND 10 days from discovery of failure to meet 6. Ve@ de mehh of the LCO.

boron in solution is 5 9.22 %

weight and within the limits of C. With two SLC subsystems Figure 3.4-1 every 31 days; i inoperable for reasons other g than Condition A, restore one SLC subsystem to OPERABLE h M h a af W m a i or boron is added to solution; l status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

E l D. Required Action and associated g , ,f Completion Time not met, be in Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , solution temperature is restored o

to > 4 8 F. ,

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7. Verify sodium pentaborate l enrichment is 2 54.5 atom percent B-10 prior to addition i to SLC tank. I 8 verify all heat traced piping l between storage tank and pump ,

suction is unblocked every 24 l months. I AND i Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after I solution temperature is restored to > 4 8 F.

9. Verify temperature of gump suction piping is > 48 F eve n 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Revielen 1

Amendment No. 100, 140 3/4.4-1 l

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PNPS FIGURE 3.4-1 Sodiusi Pentaborate Solution Volume and Concentration Reauirements Tank overnow 10 ..

Lineof henimumSedum 9.5 -- o weight 9.22 9 --

Region of Required Volume -

s.82 s.5 -- s.42

( concentration (Enttro Zone)

% Sedum Pentaboroes g-- l

=*,- m,*,- no,on

_ , , , , , concentration B10 seasope weight 7.5 -- Lla* Enttchment

> 54.5 Atom Percent 7--

6.5 - 2068 4696 6 : ; ; ;l ; ; ; ; ; I ; i 0 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 V = Not Tank Volume (Gallons)

Amendment 102 3/4.4 -2

BASES:

3/4.4 STANDBY LIQUID CONTROL SYSTEM Backaround The design objective of the standby liquid control system is to provide the capability of bringing the reactor from full power to a ccid, xenon-free shutdown condition assuming that none of the withdrawn control rods can be inserted. The Standby Liquid Control system satisfies 10 CFR 50.62, " Anticipated Transients Without Scram (ATWS)".

The SLC System consists of a boron solution storage tank, two positive displacement pumps, two explosive valves that are provided in parallel for redundancy, and associated piping and valves used to transfer borated water from the storage tank to the reactor pressure vessel (RPV). The borated solution is discharged near the bottom of the core shroud, where it then mixes with the cooling water rising through the core. A smaller tank containing demineralized water is provided for testing purposes.

Acolicable Safety Analysis The requirements for SLC capability to shutdown the reactor are identified via the station Nuclear Safety Operational Analysis (Appendix G to the FSAR, Special Event 45 - Shutdown Without Control Rods) If no more than one operable control rod is withdrawn, the basic shutdown reactivity requirement for the core is satisfied and !

the Standby Liquid Control system is not required, t

The SLC System is used in the event that enough control rods cannot be inserted to accomplish shutdown and cooldown in the normal manner. To meet this objective, the SLC system is designed to inject a quantity of boron that produces a minimum concentration equivalent to 675 ppm of natural boron in the reactor core. The 675 ppm equivalent concentration in the reactor core is required to bring the reactor from full power to at least a three percent Ak suberitical condition, considering i the hot to cold reactivity difference, xenon poisoning, etc. The system will inject I this boron solution in less than 125 minutes. The maximum time requirement for '

inserting the boron solution was selected to override the rate of reactivity i insertion caused by cooldown of the reactor following the xenon poison peak. l 1

The Standby Liquid Control system must have the equivalent control capacity I (injection rate) of 86 gpm at 13 percent by wt. natural sodium pentaborate for a I 251" diameter reactor pressure vessel in order to satisfy 10 CFR 50.62 requirements. l This equivalency requirement is fulfilled by a combination of concentration, B-10 l enrichment and flow rate of sodium pentaborate solution. A minimum 8.42%

concentration and 54.5% enrichment of B-10 isotope at a 39 GPM pump flow rate satisfies the ATWS Rule (10 CFR 50.62) equivalency requirement. l The quantity of B-10 stored in the Standby Liquid Control System Storage Tank is sufficient to bring the concentration of B-10 in the teactor to the point where the reactor will be shutdown and to provide a minimum 25 percent margin beyond the amount needed to shutdown the reactor to allow for possible imperfect mixing of the chemical solution in the reactor water. The volume versus concentration limits in Figure 3.4-1 are calculated such that the required concentration is achieved accounting for dilution in the RPV with normal water level and including the water l volume in the residual heat removal (RHR) shutdown cooling piping and in the recirculation loop piping. This quantity of borated solution is the amount that is above the pump suction shutoff level in the borated solution storage tank. No credit is taken for the portion of the tank volume that cannot be injected.

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Revision I Amendment No. B3/4.4-1 l

BASES:

3/4.4 STANDBY LIQUID COICROL SYSTEM i Soecification j The OPERABILITY of the SLC System provides backup capability for reactivity control independent of normal reactivity control provisions provided by the control rods.

The OPERABILITY of the SLC System is based on the conditions of the borated solution in the storage tank and the availability of a flow path to the RPV, including the !

OPERABILITY of the pumps and valves. Two SLC subsystems are required to be OPERABLE; each contains an OPERABLE pump, an explosive valve, and associated piping, !

valves, and instruments and controls to ensure an OPERABLE flow pa*.h.

Acolicability:

In the Run and Startup MODES, shutdown capability is required. In the Hot Shutdown 1

and Cold Shutdown MODES, control rods are not able to be withdrawn since the reactor {

l mode switch is in shutdown and a control rod block is applied. This provides '

adequate controls to ensure that the reactor remains subcritical. In the Refuel j Mode, only a single control rod can be withdrawn from a core cell containing fuel l assemblies. Demonstration of adequate SDM (LCO 3.3.A.1, " Reactivity Margin - core

! loading") ensures that the reactor will not become critical. Therefore, the SLC j System is not required to be OPERABLE when only a single control rod can be l withdrawn.

l Ooeration with Inocerable Eculoment l 3.4.A.

If the boron solution concentration is less than the required limits for mitigation but greater than the concentration required for cold shutdown (original licensing basis), the concentration must be restored to within limits in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . It is not I necessary under these conditions to declare both SLC subsystems inoperable since they are capable of performing their original design basis function. Because of the low probability of an event and the fact that the SLC System capability still l exists for vessel injection under these conditions, the allowed Completion Time of l 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is acceptable and provides adequate time to restore concentration to within j l limits. i l

The original shutdown criteria (licensing basis) required a quantity of boron be injected into the vessel to produce a concentration equivalent to 700 ppm of natural boron in the reactor core in less than 125 minutes. To meet this criteria, at least 4770 gallons of 9.4% sodium pentaborate or equivalent was required to be available for delivery to the reactor. Since the SLC pump flowrate is unchanged and the quantity of boron in the SLC storage tank is a function of volume, concentration, and enrichment, the following formula describes the relationships necessary to ensure that sufficient B-10 is available:(BECo Calculation - N82) l C_ x 2 1.0

_E_ x V 19.8 9.4 4770 Minimum Concentration (C) to achieve original shutdown criteria assuming a SLC tank l usable volume (V) of 3650 gallons (4050 gallons (low level alarm) - 400 gallons (volume below suction path)], and a 54.5% enriched boron solution is:

C= 19.8 x 4770 x 9.4 E V C= M x 127.Q x 9.4 = 4.46%

54.5 3650 Revision Amendment No. B3/4.4-2 I

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l BASES 3/4.4 STANDBY LIQUID CONTROL SYSTEM Ooeration with Inocerable Eculoment (continued) 3.4.A (continued)

Therefore, maintaining the solution concentration > 8% will-ensure original shutdown criteria is satisfied.

The second completion time establishes a limit on the maximum time allowed for any combination of concentration out of limits or inoperable SLC subsystems during any single contiguous occurrence of failing to meet the LCO. If condition 3.4.A is entered while, for instance, a SLC subsystem is inoperable (condition 3.4.B) and that subsystem is subsequently returned to OPERABLE, the LCO may already have been not met for up to 7 days. This situation could lead to a total duration of 10 days 3 (7 days in condition 3.4.B, followed by 3 days in condition 3.4.A), since initial failure of the LCO, to restore the SLC System. Then a SLC subsystem could be found inoperable again, and concentration could be restored to within limits. This could continue indefinitely.

This completion time allows for an exception to the normal " time zero" for beginning i the allowed outage time " clock," resulting in establishing the " time zero" at the I time the LCO was initially not met instead of at the time condition 3.4.A was entered. The 10 day Completion Time is an' acceptable limitation on this potential to fail to meet the LCO indefinitely.

3.4.B Only one of the two standby liquid control pumping loops is needed for operating the system. If one SLC subsystem is inoperable for reasons other than condition 3.4.A, the inoperable subsystem must be restored to OPERABLE status within 7 days. One inoperable pumping circuit does not immediately threaten the shutdown capability, and reactor operation can continue while the circuit is being repaired. Assurance that the remaining system will perform its intended function and that the long term average availability of the system is not reduced is obtained for a one out of two system by an allowable equipment out of service time of one third of the normal surveillance frequency. This method determines an equipment out of service time of ten days. Additional conservatism is introduced by reducing the allowable out of l service time to seven days. l The second completion time establishes a limit on the maximum time allowed for any combination of concentration out of limits or inoperable SLC subsystems during any single contiguous occurrence of failing to meet the LCO. If condition 3.4.B is entered while, for instance, concentration is out of limits (condition 3.4.A), and I is subsequently returned to within limits, the LCO may already have been not met for up to 3 days. This situation could lead to a total duration of 10 days (3 days in condition 3.4.A, followed by 7 days in condition 3.4.B), since initial failure of the LCO, to restore the SLC System. Then concentration could be found out of limits again, and the SLC subsystem could be restored to OPERABLE. This could continue indefinitely.

This completion time allows for an exception to the normal " time zero" for beginning the allowed outage time " clock," resulting in establishing the " time zero" at the time the LCO was initially not met instead of at the time condition 3.4.B was entered. The 10 day Completion Time is an acceptable limitation on tnis potential to fail to meet the LCO indefinitely.

3.4.C If both SLC subsystems are inoperable for reasons other than condition 3.4.A, at least one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The allowed completion time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is considered acceptable given the low probability of a Revision Amendment No. B3/4.4-3

r BASES l 3/4.4 STANDBY LIQUID CONTROL SYSTEM l Ooeration with Incoerable Eauioment (continued) 3.4.C (continued) l DBA or transient occurring concurrent with the failure of the control rods to shut down the reactor.

3.4.D If any action and associated completion time is not met, the plant must be brought l to a MODE in which the LCO does not apply. To achieve this status, the plant must I be brought to Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed completion time of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

, is reasonable, cased on operating experience, to reach Hot Shutdown from full power I

conditions in an orderly manner and without challenging plant systems, i i i Surveillance Recuirements i 4.4.1 Demonstrating that each SLC System pump develops a flow rate of 39 gpm at a minimum system head ct 1275 psig ensures that pump performance is acceptable during the fuel l cycle. This minimum pump flow rate requirement ensures that, when combined with the sodium pentaborate solution concentration requirements, the rate of negative l reactivity insertion from the SLC System will adequately compensate for the positive reactivity effects encountered during power reduction, cooldown of the moderator, and xenon decay. This test confirms one point on the pump design curve and is indicative of overall performance. Such inservice inspections confirm component

, OPERABILITY, trend performance, and detect incipient failures by indicating abnormal l performance. Testing the pumps and valves in accordance with the Inservice Testing i j Program [ASME B&PV Code Section XI (Articles IWP and IWV, except where specific l l relief is granted)) adequately assesses component operational readiness.

4.4.2; This Surveillance ensures that there is a functioning flow path from the boron solution storage tank to the RPV, including the firing of an explosive valve. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch that has been certified by having one of that batch successfully fired. The pump and explosive valve tested should be alternated

such that both complete flow paths are tested every 48 months at alternating 24 l month intervals. The Surveillance may be performed in separate steps to prevent i

injecting boron into the RPV. An acceptable method for verifying flow from the pump to the RPV is to pump demineralized water from a test tank through one SLC subsystem and into the RPV. The 24 month frequency 10 based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the surveillance were performed at power. Various

components of the system are individually tested periodically, thus making more l frequent testing of the entire system unnecessary.

l l 4.4.3 This Surveillance verifies the continuity of the explosive charges in the injection valves to ensure that proper operation will occur if required. Other administrative i controls, such as those that limit the shelf life of the explosive charges, must be followed. The 31 day frequency is based on operating experience and has demonstrated the reliability of the explosive charge continuity.

Revision Amendment No. B3/4.4-4

BASES 3/4.4 STANDBY LIQUID CONTROL SYSTEM Surveillance Reauirements (continued) 4.4.4. 4.4.5 and 4.4.9 These 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Surveillances verify certain characteristics of the SLC System (e.g.,

the volume and temperature of the borated solution in the storage tank) , thereby ensuring SLC System OPERABILITY without disturbing normal plant operation. These Surveillances ensure that the proper borated solution volume and temperature, including the temperature of the pump suction piping, are maintained. Maintaining a minimum specified borated solution temperature is important in ensuring that the boron remains in solution and does not precipitate out in ene storage tank or in the pump suction piping. The solution shall be kept at least 10*F above saturation temperature to guard against boron precipitation. Minimum solution temperature is 48'F. This is 10*F above the saturation temperature for the maximum allowed sodium pentaborate concentration of 9.22 Wt. Percent.

Maintaining 2 4000 gallons of 2 8% concentration of 54.5 atom percent B-10 solution provides assurance that the original design criteria will be met which is consistent with the current license bases as revised by Amendment No. 102.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency is based on operating experience and has shown there are relatively slow variations in the measured parameters of volume and temperature.

4.4.6 This Surveillance requires an examination of the sodium pentaborate solution by using chemical analysis to ensure that the proper concentration of boron exists in the storage tank. This Surveillance must be performed anytime boron or water is added to the storage tank solution to determine that the boron solution concentration is within the specified limits. This surveillance must also be performed anytime the temperature is restored to > 48 F, to ensure that no significant boron precipitation occurred. The 31 day fequency of this Surveillance is appropriate because of the relatively slow variation of boron concentration between surveillances.

4,4,7 Enriched sodium pentaborate solution is made by mixing granular, enriched sodium pentaborate with water. The boron enrichment (B-10 atom percent) of the solution in the tank does not vary with the addition of enriched sodium pentaborate or water provided 54.5% enriched (B-10 atom percent) material is added. The procurement process ensures that material is only purchased from a Quality Assurance approved vendor. The Quality Assurance requirements for storage of "Q" material ensures against onsite contamination / degradation of the material. Receipt inspection, isotopic tests, to verify the actual B-10 enrichment, must be performed prior to use.

Since a change in enrichment cannot occur by any process other than the addition of new chemicals to the Standby Liquid Control solution tank, verification of Boron-10 enrichment as a function of the receipt inspection of new chemicals in conjunction with the quality controls in place for onsite storage _is sufficient to satisfy the prior to addition completion Time.

4.4.8 Demonstrating that all heat traced piping between the boron solution storage tank and the suction inlet to the injection pumps is unblocked ensures that there is a functioning flow path for injecting the sodium pentaborate solution. An acceptable method for verifying that the suction piping is unblocked is to pump from the storage tank to the test tank.

Revision Amendment No. B3/4.4-5 ,

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TABLE 6.9-1 l l

REPORTS j Area Reference Submittal Date l 1

f a. Secondary Containment 4.7.C.1.c Upon completion of Leak Rate Testing (1) each test (2) i

b. (Deleted)

c. (Deleted)

d. (Deleted) )

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e. (Deleted) 3 NOTES: 1. Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report. This report shall include data on the wind speed, wind direction, outside and inside i temperatures during the test, concurrent reactor building pressure, j and emergency ventilation flow rate. The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate limits.

2. The report shall be submitted approximately 90 days after completion of each test. Test periods shall be based on the commercial service date as the starting point.

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Revision Amendment No. 30, 00, 102, 112, 132 6-17

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PNPS Table 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTPNNTATION REuuw-=mwr Operable Inst. Modes in which Function Channels per Trip Function Trip Level Setting Must Be Operable Action (1)

Trio System (1) Refuel Startup/ Hot Run Standby Minimum) Avail.

1 Mode Switch in Shutdown X (7) X A 1

1 Manual Scram X 7) X X A 1

IRM

7) X (5) A 3 4 High Flux 5120/125 of full scal X X (5) A 3 4 Inoperative I t e APRM L1 2 's High Flux (15) (17 (17) X A or B 2 3 Inoperative (13) X (7 X(9) X A or B 2 3 High Flux (15%) 515% of Design Power X X (16) A or B 2 2 High Reactor Pressure 51063.5 peig X (10) X X A 2 2 High Drywell Pressure 1 2 22 psig X(8) X(8) X A 2 2 Reactor Low Water Level 211.6 In. Indicated Level X (10) X X A SDIV High Water Level: 538 Gallons X(2 (7) X A

[ X 2 2 East 2 2 West 4 4 Main Steam Line ,

Isolation Valve Closure $10% Valve Closure X(3) (6) X(3) (6) X(6) A or C 2 2 Turbine Control Valve 2 1 50 psig Control Oil Fast Closure Pressure at Acceleration kelay X(4) X (4) X(4) A or D 4 4 Turbine Stop Valve 510% Valve Closure X (4 ) X (4) X(4) A or D Closure nceicien 10t Amendmerit No. 15, 12, OC, 02, 117, 123, 107, 151, 152, 15 0 ,-14+ 3/4.1-2

NOTES FOR TABLE 3.1.1 (Cont)

2. Per1nissible to bypass, with control rod block, for reactor protection

, system reset in refuel and shutdown positions of the reactor mode switch.

3. Permissible to bypass when reactor pressure is <576 psig.

4. Permissible to bypass when turbine first stage pressure is less than s 112 psig.

5. IRM's are bypassed when APRM's are onscale and the reactor mode switch is in the run position.

6. The design permits closure of any two lines without a scram being initiated. -

g, . -- u- -----..u-22., ..., :- - .u. -- -- ... - ,

->y

, r;;;ter ;;t;r t .;p;ratur; i; 1;;; th:2 214D, only th; f;11;;ing trip -

f;;;tica: z;;i t; b; ap;r:bi;.

l A. "=d; ;=Lt;b in ;huti;=.

. o._._.._..,. . _ - _ ..

O. "igh f1 = I"2:

O. 0;r = di;;harg; colu=; high 1; :1

, ". A""l' '15t) Sigh fl= ;; rem l

8. Not required to be operable when primary containment integrity is not required.

9. Not required while performing low power physics tests at atmospheric pressure during or af ter refueling at power levels not to exceed 5 MW(t) ..

10. Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.

11. Deleted

12. Deleted

13. An APRM will be considered inoperable if there are less than 2 LPRM inputs per level or there is less than 50% of the normal complement of LPRM's to an APRM.

14. Deleted

15. The APRM high flux trip level setting shall be as specified in the CORE OPERATING LIMITS REPORT, but shall in no case exceed 120% of rated thermal power.

16. The APRM (15%) high flux scram is bypassed when in the run mode.

17. The APRM flow biased high flux scram is bypassed when in the refuel or startup/ hot standby modes.

18. Deleted.

bl W.

7. When the reactor mode switch is in the Refuel position, the reactor vessel head is removed, and control rods are inserted in all core cells containing one or more fuel assemblies, these scram functions are not required.

Revision 177 Amendment No. O, 15, 27, 12, 00, 117, 110, 130, 117, 151, 150, 15? 3/4.1-4

PNPS TABLE 3.2.C.1 INSTRN "TATION THAT INITIATES ROD BLOCKS Operable Channels per Trio Function Required Minimum l Available Operational Conditions Notes Trio Function APRM Upscale (Flow Biased) 4 6 Run (1)

APRM Upscale 4 6 Startup/ Refuel (1) (6)

APRM Inoperative 4 6 Run/Startup/ Refuel (1) 6)

APRM Downscale 4 6 Run (1)

Rod Block Monitor 2 2 Run, with limiting control rod (2) (5)

(Power Dependent) pattern, and reactor power > LPSP Al Rod Block Mcnitor 2 2 Run, with limiting control rod (2) (5)

Inoperative pattern, and reactor power > LPSP Rod Block Monitter 2 2 Run, with 1Amiting control rod (2) (5)

Downscale pattern, and reactor power > LPSP IRM Downscals 6 8 Startup/ Refuel, except trip is (1 (6) bypassed when IRM is on its lowest range L1 IRM Detector not in 6 8 Startup/ Refuel, trip is bypassec} (1) (6)

Startup Position when mode switch is placed in run IRM Upscale 6 8 Startup/ Refuel (1) (6)

IRM Inoperative 6 8 Startup/ Refuel (1) 6)

Ravision 177 Amendment No. 15, 27, 02, C5, 72, 70, 110, 100, 120, 107 3/4.2 13

PNPS TABLE 3.2.C.1 (Cont)

INSTAIBMNTATION THAT INITIATES ROD BLOCKS Operable Instrument Channels ner Trio Function Required Trio Function Minimum l Available Operational Conditions Potes SRM Detector not in 3 4 Startup/ Refuel, except trip is bypassed (1) (4) 6) .

Startup Position when SRM count rate is 2 100 counts /second or IRMs on Range 3 or above Al SRM Downscale 3 4 Startup/ Refuel, except trip is bypassed (1) (4 (6) when IRMs on Range 3 or above SRM Upscale 3 4 Startup/ Refuel, except trip is by- (1) 6) l passed when the IRM range switches are on Range 8 or above (4)

IL) 1 SRM Inope.rative 3 4 Startup/ Refuel, except trip is by- (1) (6) passed when the IRM range switches are on Range 8 or above (4)

Scram Discharge 2 2 Run/Startup/ Refuel (3) 6)

Instrument Volume Water Level - High Scram Discharge 1 1 Refuel / Shutdown (3 (6)

Instrument Volume-Scram Trip Bypassed Rsvision 178 Amendment No. 4-34, 44-7, 159 3/4.2-20

e

" s.

l NCTTES FOR TABIE 3.2.C-1

1. With the number of operable channels:

a. One less than required by the minimum operable channels per l trip function requirement, restore an inoperable channel to l' operable status within 7 days or place an inoperable channel i in the tripped condition within the next hour.

l b. Two or more less than required by the minimum operable channels per trip function requirement, place at least one inoperable channel in the tripped condition within one hour.

2. a. With one RBM Channel inoperable:

(1) restore the inoperable RBM channel to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; otherwise place one rod block monitor-channel in the tripped condition within the next hour, and; (2) prior to cor. trol rod withdrawal, perform an instrument i

fur.ction test of the operable RBM channel.

b. With both RBM channels inoperable, place at least one inoperable rod block monitor channel in the tripped condition within one hour.

3. If the number of operable channels is less than required by the minimum operable channels per trip function requirement, place the iurgerable channel in the tripped condition within one hour.

4. SRM operability requirements during core alterations are given in Technical Specification 3.10.

5. RBM operability is required in the run mode in the presence of a limiting rod pattern with reactor power greater than the RBM low power setpoint (LPSP). -A limiting rod pattern exists when:

MCPR < 1.40 for reactor power 2 90%

MCPR < 1.70 for reactor power < 90%

The allowable value for the LPSP is 5 29% of rated ' core thermal power.

L1

6. When the reactor mode switch is in the Refuel position, the reactor vessel head is removed, and control rods are inserted in all core cells containing one or more fuel assemblies, these Rod Block functions are not required.

! Revision 177

' Amendment No. 15, 27, 02, 05, "?, 110, 130 3/4.2-22

l l

a >

LIMITING CONDITIONS FOR OPERATION SURVIILLMCE REQUIREMENTS

)

3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM l AmeMeeM-hh- -,.2.___ui,..

.... i t

.yr__, . ._. . .,, _. .u..._ ___7,, . _. .: ._ .__ . ,. .. .. . _

.u_

_, __,2__

gi l

. 2 ._ _ . . . _ .- -- g%

vr-- - - -- -

i

, g .e, . .___ J u.,- .

r__._,

e.. :, _2 .,J. . . . . . . . ..e.,__ __.

..s.......

_E

____ _ , , . u.. u.. . .e.__J.L,,. . . . .

e :. 3, :..J. -l i

o____,. . . , . . .e..,.___ . . . .

mu.,2 v n

._ ._ m. . . .2..

mu.,, a ,_ _ s ._ .

v 1 .......

. . . . .._ ... _ a... .. . _ : , _ u :. . . - . . . . , . _ _

. . . . - . . . .. : . u. L.._ ._u....,.

r-

. . , . , , _u....

,ri._.,

. : s .,. .. t.._, __r,_u.....,.

. .m. .. . u. .

2_._.

.. u. s.. ,... _ _ _

. . . . . . a...._ .e . ._, ._ n.u,.,. ,2, .

e_,_, . . . . , . .e.,.___

i

_u.... . .J.,_... ,, , . .J. .:

. . __ ..:t..,...

, . . -.. .. .. u. - . . , , _

i

. , . . ,.. . , . ,.,,2.._..

t ,,

i Soecification: "rccificctic.- i I

..,.....e,..___ . . . . . _..._2.,._u2.,.s..

. . , . , . . . . .e...___ _..._2.,._u2.,.2..

r.-.','... - ' . - . * '. . ' . . .' .

l l

A, '

.. . ~..-. .. .,- -

" . ' . " . , , ..,r.-..',-

, a __ . a n.,_.,._..__, _s._,,

e

a. . . . _ _ _ _ , _ _ __.,. r :__ .,, _...y 3, . . .. . .e..,.___. . . . . . ..

u.,,_

. r ,, . ,a. n. _ _..a. .s: _ _ the

. ... . .: ._ ,a u,.,. a..._ y......

. a.. _

Two SLC

. . " _. _ ,.' .a.,....-. .'.,.'..,.......-

v" _-. . .

subsystems afiall. .be O_PERABLE.[y cxcc vt --

f

^

~" d cc:.-icd in .: . : . ; ccic;;,[Th*e 7 _____u,_

1. When tested as specified in 3.13

_ _ . . , . ,.,y,.-.. ..i.._. . . verify that each pump delivers

the rccetcr ic in the Ocid at least 39 GPM against a system

.e,u...2.._._...

.. .. ,.__.2.22,__

_,, _____u,

,r. . - . c head of 1275 psig.

l

. _ _. , __2.._. ... ___ . .. ,. . , , , - . .' . . . . - . . '

. A5 _

._..__ _ . _ q.

e. ..s. ..,..y . ,,.....

, . e Li APPLICABILITY.- Run and Startup MODES Ri ^ . . . - . . . , . , - . ..' ..'..'

- ,-. _ .- . .u. . .s.., _. .._ :__ __ _ __ ..

. . . . , y.. .

..., ..,_2,.,.

i 1

7

.e .. .y..

__ __2_.

y s sa .

. 2 en , y .y

\

= -, _ ._ ,.

r _.

t l

l

(

l i

i l

Revision 177 Amendment No. 102, 149 3/4.4-1

LIMITING C0 EDITIONS FOR OPERATION SURVEZLLANCE REQUIREMEETS 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID COFFROL SYSTEM (Cont) (Cont)

'";_1.1 O=t;= ".=ildilit ; (C;; )

_ _ _u u.

_,_______m.._2__ ._.u._,_,_.

_____2__

_, . . _2_

I ;; tin ;; :;;;i'i;d in ~

2.1 ually initlate dii' o the Standby Liquid I /'ControlSystemloopsand pump domineralised water into the reactor vessel

/

Ai my24 enonen on a sTAooemen Test eAyss

= __ _ - -- -

"This test checks explosion '

of the charge associated R2 1 withthetestedloop,. proper (

operation of the valves, and) j buse operability.fjTheN freplacement enarges to be 1

+

R3 installed will be selected from the same manufactured batch as the tested charge.

. 1".;; 00; ting t: 0;ti;f,-

..,_2___._.,._ a..... ....u,

<_._u.

_ . . _ , _ _ _ _ 2__,.22__ u_u Br Ooeration with Inocerable ~','

..,._.Z.._'._._-"..~.,.'._..-","._."".,_,_',__

Components: Ai .,__ _,......,_..., .

n .._,2__ _ . - , _

. -___ - > _- _- u_ n_ _ . Du_._

w---------

)

l t

d='=0; ,;=;;;i; =t ;;\ Y f;=d

b; in;;;;;.ti;,

Op;;i'i;;tica 2.0."..; ;h:11 50

h. 0;_ . i11=0; ;it'. I;;;::d

( GemeenenteK- .-

MM

.m......._

r,.-._a_-.v..--....

-____s- > ,

1. . ---. _---r-----

^ -

Q

.n_,

...,.r,.----, -__----_----

_m_>

1 7,.,.___ .. ... , . . . . . __ _ __ _,._m_,, u_ ,_____ __ _2

--r.-.---.---

. ,,. ____.. >____ L3

r-----

_____u,_ . 2.__,._

z

..n. .a.. .__..s.u.....

__. ..._a..,

_2_,,..__, ..u. .. . ... . . ....

y' 4

i;;r;;;ti; ; .;;;;; i; j t_,7,.... .

i. 3.4.8 With one SLC subsystem inoperable for ressens 1

other then 3.4.A restore SLC subsystem to i OPERABLE status within 7 days AND 10 days

, from discovery of failure to meet the LCO a

{ L2 1

j ..

} L 3.4.C With two SLC subsystems inoperable for reasons other j then 3.4.A, restore one SLC subsystem to OPERABLE J status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4

j Revision 177

Amendment No. 10 ': , l'0 3/4.4 2 a

l 1

a

. o.

LIMITING CONDITIONS FOR OPERATICE SURVIILLANCE REOUIREMENTS 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM (Cont) (Cont)

M i= r;;t :;t; 201; tic; '

O.

_,, _ mu_ _

a

.m . _.- . - _ 2___ _ _ . . _ . . . u. _

. _n. -._ - _ , __ ,_,,__,__ __ _

_u_,, u_

.2,_.,

,_,,-_a__ -.,2,.

Ai ._

____u,_

u__ . , . - - .m._.

_ - - ,_u,u__ ,------ .----

_, .m_

.2_a n,__

-.. . ___,,. . _ -u.. - -. .

c._. ,. ..-..

..-,m.-.. _

. . . ,_. __. . . ._ . ..., . . _ _ _ _ _ -,... ...eeeeen-verWy

_,u.._ , 2 ,_ . 2 2, . - - ,__

_,..a.--.

2_ .u_ ,2 2 _ _ _ _ , ._u ) 4 . Md W ".' . - '- " '- - . - - .

)

I :: '-- , Coodium per taterate'solubon le 4, IE _ ,",~ u 7_ I _'. !'~ _~ ~.".__ ' - ._~,'

I w __

g24 houyrs igure 3.4-A2 erWy g

2. The temperature of the liqui G. esperature "'.;;h ;__1_: ;;

control solution shall be ; ;; - of eodium periatxiste L ecluten is > 48* F every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

_ maintained above 48*F.hffthe}

fsolucion tenperature falls to for "baron in solution is s; 9.22 % '

_ thy -

and or below 48'F, the system will 3 (Concentration d , u..;;u ;t-- ?. :=::: .

r_- -

be flow tested to verify a __ ___ _

, . , . . r,. . _ . . . .

u _ ..-, _ _ _u _ _ u. . . . at fl9w Path, g_ _

_ _ _ _; _ gg , ,

,i M8 -@y 24a months wnhin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (boron is added to the solution 341 ,l

3. The enrichment of the liquid ener ,or the solution is at or bele j control solution shall be 4 8 ' F. _f 31 days maintained at a B10 isotope M3 !

"'.;;h SN enrichment exceeding 54.5 atom b . :::id-_.;;t.

__2 _ . _ __ , _ _ _ _ ,

u._,_ ,__.

percent. . . . - - . - . . . -. -- . . . _ .

--,.1._._. u____.

_ _ _ _ 2_,

--- 2 ._ . - , . ....

___2-_...,_i_.

__, ._.2__

.u.._.._._.

.. . , , .r,..._2,__,

...,2._.. .-

_______,,,.3_,_,. . . _

u. L4

...._,2.,_,

_ .._._.2..w.,_._... _

2. .

-_..2_._.

. u.

___.u__

. . - - - , , 2. ,,_. ...2, ,__ . ._. _ . ,

__ 21.__

}

.m_,,

u_ ____2____.

____u-..,_. __,..2,__ ____.1 ____.- -_

__2

- . . . . u. . _. n. a. -,.

>____ _,m. .__.

_ , _ _ _ _ -__ _____ ,a __. ___ __2___ .

m2 >

__ ... __......2_._: __ . . . . . . ,

... -. . . , . r,..... ...

___.2.._

- - - - r,..m_u___

_ ______m__

u, 2 _ i

_2

--. u. . . _...e-m. ,

2____

_ , _,,,._u,_

. - . . /

.---.,,2._.__.._.._._.._..

u..,_. ______

..r-.u.-..,__

-.. 2.

____ ___ 2 _

- . . . . . . 2._.__,..,__

H _ _.2---

- - - . - - - ~ .....

i;;;Opi; ;;;ic'_..;;t . ".; ::1;t;".' 7. , VerW Wypentaborate enrichment is 2 54.5 atom I.i;iting 0;;'iti;;; f;; ;;;;;ti;. percent B.10 prior to addihon to SLC tank.

-__ - _V

/

_,2___ u_,__.

--...,.._m. ., - - . .

Y M 3. VerWy conimuity of explomv. chernevery ___ 31 - days ;

8. Verify all host traced piping between storage tank and pump suchon is unblocked every 24 months blKl Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solubon temperature is restored to > 48' F. m

_-_- 1

__ __n -

N_ _

M3 9. Vertfy temperature of pump sucten piping is > 48'F every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , w _

Revision 177 Amendment No. MG 3/4.4-3

- . - . . . - - - _ - . . --- - . - - . . ~ - - - - ---- - ._ --

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 2 3.4 STANDBY LIOUID CONTROL' SL17.EH 4.4 STANDBY LIOUID COffrROL SYSTEM (Cont) 1 (Cont)

,,__u.,

r. ,, _ _ _ , ,

.. .. ,,... 2._.._.a..._.

. , . , . - , _ , ,, .-l 3.4.A With concentration of boron in solution not within t i

a.a...- ..'. '_- .. '., " . . . . .

. . I mits but > 8%. restore concentration of boron in '

I t 3.4.D . , . . . . . . .. .. - . ' . . ' . ' . _' , . y'.......'. -

. solution to within limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND.10

,_.,,.2 . .

o.u....m._m,... , , - . . , ' . ' " . . , , . .

, , . days from discovery of failure to meet the LCO Li ._ 2_ a. . .

___ ,,,._u,_ _ , .

......__m_ __, _ _ -- -

t . . .. ,__ , . , . 2____,_ . . . . , _ . , , . .. ._2 a. . . 2 _.. u.

_ u.._._.____

2. '.'."...,. . . . .. ' . . ' -.-- . - . " . - ., . , - ' , . ^ ' . . . . . ~ . . ' . . -

g _- __ , _.. _2 .21 . a _1,_. ,..s..n...,, _ _

t

_u. .,

u..u... . u__ __2_.

l w ___

._.. . . . . . . _ .. _ a.._.,..

m l l

_u___ _,...a....

l __.

y... - . .. _ __ _ _ _ . _

. . ~ , . . .

g,

__ _..i._..__,_ >__: ___._2.,__s__ u.,

t

a. . . _ , . _ _ , . . . . . . _

y l

a...,_ ___. . . w____. ......,

_..,...__a..,.

___2 _. .,_, ._ ., ,. ., _ . _ _ . , _.,

l _ _ _~-

i L,_. ._ .__ u , 2 .. ._ u. .._. _2 ,.,.2a,.,__2

. , > _ . __ m...._. .

3.4.D. R utred Action and associated Com letion Time l

, p.,_ - .,_.,r.... - . .. _ ., .,. .. .. _ _

not met., be in Hot Shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

, .n,,.. ___ __. ___.

. . , . . .. . .u..,_ . . . . . . . . _ __

a...,_. ____.,__

.u.___. _ , _ _ _ , 2_.. . .

.u....a_._

. . , . , . . e__ ._. u, ..l. m , ,1 . ,_

. . . 1 u. ..

.,,.__u,__ , . _.. __,..

1 . 1a L..2.. *m a. u..,_._

e.. . s _ .a.

3.

__ a...._. ,.,_s._._

,,.._u_..,.

_,....a 1.__.

. . ..a_

. u.u..._. .__1_2

_ _ , . . , . . .. .. .. . . , u_... a. .._

____._u___ _ _,

. . . . . . . . . .. ___.2_____

. , , , . . . _ . . . . . . .. 1 3.4A . , , . . '. ' . ' _ . ' . _ ' - . . ' . ' . . ." . ' . . - . . . . . . ' .

__a, u_. _. .* . , m u. .._. en N 1. ..,_.,a . ,, .1 .

i

___....!.L. ____

.. .....__ ..u..._._. e. ,. . m. 1 l

Me . . . _ ,

y.-.....'. . ' " . . .. ' . . . . . - . . . . . _ ' - , . . ,

t .... a...,_. u.._,_. .

, , - ____ ___ __ a..._.

p _. __ 2_

_ , _ _ _ _ . _ -- _ . _ _ _ _ r s , _ . . ,_ _

_____ y .. . . .

ra. . . .: ._

.. ,,. : _ a .- .

a u.._ ,......t___--. _ . . . .

..,_._2._._.~__._

, - _-_.....a....

....... .. _ a_ _, s_. _. .__.

...<_1.

a_

.u..,.. ...kee's.e ,

c l

. 1... u..1.. . __... _s_,._ --..J. __J1___

.. ,. ,I a...._. ,,_s_, _y.___ , _ _ _ ., ,__ _u_2__ _ . . , a...,. .

.,,...a.._.

m_____ .......___u,_ .... ..

_ 4

_es%-&_2_,_.,_

1 ,

.e, a , n. _a,.,_ y __...._.a

__..1._.a____...

L4 .

t a

f Revision 177 Amendment No. 403 314.4 4 l . . - . , - . _ . , -

4..e .

R&REA:

I 3/4.4 STANDBY LIOUID COFTROL SYSTEM A. bTherequirementsforSLCcapabilitytoshutdownthereactorareidentifiedvia n -- the station Nuclear Safety Operational Analysis (Appendix G to the PSAR, APPUCAsLE Special Event 45). If no more than one operable control rod is withdrawn, the SAFETY basic shutdown reactivity requirement for the core is satisfied and the ANALYSES '

Standby Liquid Control svfigyn is not requiredfp .u;, tn; ;;;;.; r;;;;;.v;ty ]

T p:.;ran; ;;r :n; ;;;; E M-- =r 5- ; r;;- sinn; cf rh;n th; st;ndhr liri_dJ centr;l ;I;t;; i: 2 ni; J h The design objective of the stanaDy 11guia Tontrol system is to profEe the capability of bringing the reactor from full power to a cold, xenon-free shutdown condition assn =4na ehme nana of cha Lwithdrawn control rods can be inserted p o meet this objective, theStandby) rLiquia control system is oesigneo to inject a quantity of boron that produces a minimum concentration equivalent to 675 ppm of natural boron in the reactor l APPUCAsLE core. The 675 ppm equivalent concentration in the reactor core is required to SAFETY bring the reactor from full power to at least a three percent Ak suberitical f ANALYSES condition, considering the hot to cold reactivity difference, xenon poisoning etc. The system will inject this boron solution in less than 125 minutes.

The maximum time requirement for inserting the boron solution was selected to 1

override the rate of reactivity insertion caused by cooldown of__the reactor y Qollowing the xenon poison peaLI gseossiFh X _

The Standby Liquid Control system E: 21;; r; ;ir;d : :::j 10CFR50.62 (Requirements for Reduction of Risk from Anticipated Transients Without Scram 1 JATWS) Events __ for Licht-Water-Cooled Nuclear Power Plants) IfThe Standby I

& (Liquid Control system must. have the equivalent control capacity (injection APPUCAsl rate) of 86 gpni at 13 percent by wt. natural sodium pentaborate for a 251" SAFETY 5 diameter reactor pressure vessel in order to satisfy 10CFR50.62 requirements.

ANALYSES This equivalency requirement is fulfilled by a combination of concentration, B10 enrichment and flow rate of sodium pentaborate solution. A minimum 8.42% I ;

concentration and 54.5% enrichment of B 10 isotopeata39GPMpumpflowratej katisfiestheATWSRule (10CFR50.62) equivalency requirement.f

th; ;;;;;nt ;ti;nlv;1=.; ;;.v; h;; h;;; ;;;i;;i t; r;fl;;t th; Me inc;;;;;d

M i;;t;pi;

nrich;;nt, ;n ;dditi=;l ;;;;ir=;;t h;; b;;; cef

2

velu;t; th; ;;1ution'; ;;;;hility: : :: th; Origin;l d;;i p. :hutdeun Lcrit:ri; ch;n:v;r th; SM :nrich;;nt r;;;ir;;;nt i; ;;t ;&

f

.4.1 ITesting the pumps ;nd 7:17;; inaccordancewithASMEB&PVCodeSectionXI]

(Articles IWP and IWV, except where specific relief is oranted) adequately hosessesen=nnnant ooerational readinessy "'t; nly pr;cti;;l ti;; :: ful!D

-- 'G;;t On: liqui ;= ::: ;y;;;; :: cur:n ; r;fu;1Er rut;;;[fVarious 4.4.2 recmponents or tne system are individually testeo periodically, thus making !

more frequent testing of the entire system unnecessary f l i

l Revision 177 Amendment No. 15, 100, 105, 109 B3/4.4-1

a .. .,

EABxBs 3/4.4 STANDBY LIOUID COFTROL SYSTEM (Cont) 3.4.B. Fonly one of the two standby liquid control pumping loops is needed for 1 l operating the system. One inoperable pumping circuit does not inunediately i threaten the shutdown capability, and reactor operation can continue while the I circuit is being repaired. Assurance that the remaining system will perform j its intended function and that the long term average availability of the

~

system is not reduced is obtained for a one out of two system by an allowable equipment out of service time of one third of the normal surveillance i frequency. This method determines an equipment out of service time of ten l days. Additional conservatism is introduced by reducina the allowable out of

!.3 . service time to seven davap.0 by ;;;;;;;r; ;;; ting: : On; ;;;;;;;; r;- ]

I cm.y;n;nt. -

1 C. IThe quantity of B10 storedintheStandbyLiquidControlSystemStorageTank]

is sufficient to bring the concentration of.B10 in the reactor to the point APPUCAsLE where the reactor will be shutdown and to provide a minimum 25 percent margin SAFETY beyond the amount needed to shutdown the reactor to allow for possible j ANALYSES dmperfect mixing of the chemical solution in the reactor waterj I.;v;1 indic;ti;n and si;= indi;;t; rh;;h;r th; :=luti;n v;1rc h;; ch;;;;d, which night indic;t; ; p;;;ibi; ;inti;n ;;n;;ntr;tien ch=g; . T;;t int;; cal:

As f;r 1;;;1 ; =itaring h;;; h;;n ::tchlish;d in ;;n;id::sti = cf th;;; f;;;;rs.

]

T;.- verstur; nd liquid 1;;;l si;;;; f;r th; ystr :r: :nnunci;t;d in th; e ;;nt: 1 r;=. 3--

l "The solution shall be kept at least 10*F above the maximum saturation temperature to guard aca:.nst boron preciolemeinn - Min 4 == soluti 4.4. tamnerature is 48*@:.s is 10*F above the saturation temperature for the

(_ maximum allowed sodium pentaborate concentration of 9.22 Wt. Percent.

4.4.6 i

l

ch p;ruct;r (;;;;;ntr;;i;n, p;;p f1;; r;t;, and ;nri;;- r0) i; t;;t;d :: n]

A interv;1 ;;;;i ;nt with th; p;;;ntici f;r th;; pern;tcr :: very ;;d ci:; 0;)

pr;;;r ;;u!= nt ;;rf;=cn;;)J Enricnment testing is g required when'

' material is receivea =; une; ;;;; ;;1 ;dditi=-eeewee since change cannot 4.4.7 occur by any process other than the addition of new chemicals to the Standby Liquid Control solution tan gk l

Additional information has also been added to more fully describe each subsection.

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1 Revision 177-Amendment No. 1 ^ ': , ita B3/4.4-2

e , * ~*

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PNPS i

l

j. TABLE 6.9-1 t

REPORTS l

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AERA Reference Sn hittal Dat,g

a. Secondary Containment 4.7.C.1.c Upon completion of Leak Rate Testing (1) each test (2)

b. (Deleted) i

c. (Deleted)

d. (Deleted)

: . et= cy 1.iquie c;;t ;l :.:.c.: reurt== cy; ;f :: = = ipt l l

celuti;n :n;id.-ant cut Of ; ;;; ;_ ,1ying nrid -- t l

=f ;;;;ific;ti;; :;;;;t ;: 1;;h ;f :;;;ipt ;f

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l

u;h ; .;p; t within th; L4: :q;ir:d thirty d;y;, if nri.:_;;t ;_ ,li= =; ;ennee b; ;;hi;n d within ;;n ;

J NOTES: 1. Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report. This report shall include data on the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate. The report shall also include analyses and interpretations of those data which demonstrate j

! compliance with the specified leak rate limits.

2. The report shall be submitted approximately 90 days after completion of each test. Test periods shall be based on the cceanercial service date as the starting point.

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i Revision 177

Amendment No. 30, 00, 102, 113, 130 6-17 i

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ML20111C276

Text

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