Text

Proposed Tech Specs Re line-item Improvements,Per GL 93-05
	ML20077R413
Person / Time
Site:	Farley
Issue date:	01/09/1995
From:	; SOUTHERN NUCLEAR OPERATING CO.
To:	;
Shared Package
ML20077R410	List: ML20077R407; ML20077R413;
References
	GL-93-05, GL-93-5, NUDOCS 9501200239
	Download: ML20077R413 (39)
	v • d • e

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Enclosure 1 3 i

Joseph M. Farley Nuclear Plant Request to Incorporate Line-Item Improvements - :

Technical Snecification Channes t

i Basis for Change Reauest Below are the proposed Technical Specification changes for Farley Nuclear Plant Unit I and Unit 2 that have been selected for implementation from Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing ,

During Power Operation": -;

i Proposed Channe 1 i i

g Revise proposed Farley Unit I and Unit 2 Technical Specification 4.1.3.1.2 in accordance with ,

Generic Letter 93-05, in order to change the frequency of the full length control rod operability :

test from every 31 days to quarterly. (

Reference:

GL 93-05 #4.2.1.)

Basis for Proposed Channe ! ,

The Technical Specifications require the control rod movement test to be performed to determine if the control rods are movable at least once per 31 days. Industry experience has [

shown that this test can cause reactor trips, dropped rods, and unnecessary challenges to the !

safety systems. The proposed change to the surveillance interval will reduce the likelihood of l these occurrences. In view of successful operational record demonstrated by the control rod !

movement tests during power operation, it is requested that the surveillance interval for control i rod testing be changed from every 31 days to quarterly.

This proposed Technical Specification change is consistent with Farley Nuclear Fiant's design i and operating experience and the guidance provided in NUREG-1366. l l

Proposed Channe 2 Revise proposed Farley Unit I and Unit 2 Technical Specification Table 4.3.3 in accordance with Generic Letter 93-05, in order to change the monthly channel functional test of the ;

radiation monitors to quarterly. (

Reference:

GL 93-05 #5.14) j i

'8 asis for Proposed Channe 2 !

The Technical Specifications require channel functional testing of the radiation monitoring l instruments on a monthly basis. These instruments perform a monitoring function for reactor i coolant leakage, accident conditions in containment, and the release ofgaseous and liquid L El-1 l

9501200239 950109 PDR '

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' Enclosure 1 Basis for Change Request ellluents. Industry experience has shown that testing of radiation monitor instruments can produce a significant number ofisolations of the control room, fuel handling building, auxiliary buildings, and various process lines. In addition, the testing requires significant personnel resources and the frequent testing tends to degrade the equipment. A majority of the instrumentation is self-checkirig so that most failures will be found in this way or by channel checks. In order to decrease the plant staff burden and increase the availability of the radiation monitoring systems, it is requested that channel functional tests on radiation monitoring equipment be performed quarterly instead of monthly.

This proposed Technical Specification change is consistent with Farley Nuclear Plant's design and operating experience and the guidance provided in NUREG-1366.

Proposed Change 3 Revise Farley Unit I and Unit 2 Technical Specifications 4.5.1.1.b in accordance with Generic Letter 93-05, in order to remove the surveillance requirement for verification of the boron concentration in the accumulator under certain conditions. (

Reference:

GL 93-05 # 7.1)

Hasis for Proposed Change 3 The Technical Specifications require the boron concentration in the accumulators to be sampled at least once per 31 days to verify that it is within its limits and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months aller an increase in volume of 1% or more from makeup. Verification of the boron concentration in the accumulator afler a volume increase of 1% is not required if makeup is from the Refueling Water Storage Tank (RWST) and the concentration of boron in the RWST is within the accumulator baron concentration limit and the RWST has not been diluted since the last RWST !

sample was verified to be within specification. In addition, the present surveillance requirement l is burdensome and can result in occupational exposure. It is requested to add clarification that :

this surveillance is not required under the above special conditions.

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This proposed Technical Specification change is consistent with Farley Nuclear Plant's design and operating experience the guidance provided in NUREG-1366. ;

l Proposed Change 4 Revise Farley Unit I and Unit 2 Technical Specification 4.6.2.1.d in accordance with Generic Letter 93-05 in order to extend the surveillance interval of the containment spray nozzles from 5 years to 10 years. (

Reference:

GL 93-05 #8.1) l El-2 l

' Enclssure !

Basis for Change Request i

Basis for Proposed Channe 4 The Technical Specifications currently require that each containment spray system be ,

demonstrated operable at least once every five years by performing an air or smoke flow test through each spray header and verifying that each spray nozzle is unobstructed. The testing gives no quantitative data on flowrates exiting the nozzles. The test only verifies the flow path is unobstructed. Industry experience has shown that testing problems encountered have been constmetion related and supports a test frequency extension. Therefore, it is requested that this test interval be extended to every ten years.

This proposed Technical Specification change is consistent with Farley Nuclear Plant's design and operating experience and the guidance provided in NUREG-1366.

Proposed Channe 5 Revise Farley Unit I and Unit 2 Technical Specification 4.6.4.2 in accordance with Generic Letter 93-05 in order to change the surveillance test interval for the hydrogen recombiner functional test from once every 6 months to once each refueling cycle. (

Reference:

GL 93-05

8.5)

Basis for Proposed Channe 5 The Technical Specifications require an operability test of the hydrogen recombiner system at least once per 6 months. The hydrogen recombiner removes the hydrogen and oxygen gases that accumulate in the containment atmosphere following a design-basis loss-of-coolant accident. Industry experience has shown that only a limited number of hydrogen recombiners have failed. In most cases, only one train was found to be inoperable and in the case where both trains were found to be inoperable, a backup hydrogen purge system was available. Even the recombiners that were found to be inoperable were fixed within two hours of the failure.

Since the hydrogen recombiner is not necessaiy until many hours after a LOCA, it could be demonstrated operable well before it was needed. Therefore, it is requested that the functional test be changed to once each refueling interval instead of once per six months.

This proposed Technical Specification change is consistent with Farley Nuclear Plant's design ,

and operating experience and the guidance provided in NUREG-1366.

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' Enclosure 1 t Basis for Change Request Proposed Channe 6 Revise Farley Unit I and Unit 2 Technical Specification 4.10.1.2 in accordance with Generic Letter 93-05 in order to eliminate one rod drop test if the condition of performing a rod drop test no more than 7 days (rather than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) before reducing shutdown margin has been satisfied. (

Reference:

GL 93-05 #12)

Basis for Proposed Chvisti The Technical Specifications require the control rods not fully inserted to be tripped within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the shutdown margin to less than the specified limits. These tests are .

performed in order to verify that control rod drop times are less than the value(s) assumed in the safety analyses. This may result in testing of the control rods at least twice following a .

refueling outage: once for the drop time measurements and once prior to the time that the shutdown margin limit is suspended. Since no changes will have been made to the core geometry between the time tnat the control rods are tripped for the drop time measurements i-and the time that the shutdown margin limit would be suspended, only one test is needed to

satisfy the testing requirement if the rod drop test has been performed no more than 7 days ;

before reducing shutdown margin. It is requested that the surveillance interval associated with this condition be extended from 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to 7 days.

This proposed Technical Specification change is consistent with Farley Nuclear Plant's design and operating experience and the guidance provided in NUREG-1366.

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Enclosure 2 Joseph M. Farley Nuclear Plant Request to Incorporate Line-Item Improvements Technical Specification Channes 10 CFR 50.92 Evaluation .

Proposed Channes l

Below are the proposed technical specification changes that are specific to Farley Nuclear Plant units 1 and 2 per Generic Letter 93-05: '

l. Revise proposed Farley Unit I and Unit 2 Technical Specification 4.1.1.3 in accordance with Generic Letter 93-05, in order to change the frequency of the control rod movement test from every 31 days to quarterly. (

Reference:

GL 93-05 #4.2.1.)

2. Revise proposed Farley Unit I and Unit 2 Technical Specification Table 4.3.3 in accordance with Generic Letter 93-05, in order to change the monthly channel functional test of the radiation monitors to quarterly. (

Reference:

GL 93-05 #5.14)

3. Revise Farley Unit I and Unit 2 Technical Specification 4.5.1.1.b in accordance with Generic Letter 93-05, in order to remove the surveillance requirement for verification of the boron concentmien in the accumulator under certain conditions. (

Reference:

GL 93-05 # 7.1)

4. Revise Farley Unit I and Unit 2 Technical Specification 4.6.2.1 in accordance with Generic Letter 93-05 in order to extend the surveillance interval of the containment spray nozzles from 5 years to 10 years. (

Reference:

GL 93-05 #8.1)

5. Revise Farley Unit I and Unit 2 Technical Specification 4.6.4.2 in accordance with Generic Letter 93-05 in order to change the surveillance test interval for the hydrogen recombiner functional test from once every 6 months to once each refueling cycle.

(

Reference:

GL 93-05 #8.5)

6. Revise Farley Unit I and Unit 2 Technical Specification 4.10.1.2 in accordance with Generic Letter 9'l-05 in order to eliminate one rod drop test if the condition of performing a rod drop test no more than 7 days (rather than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) before reducing shutdown margin has been satisfied. (

Reference:

GL 93-05 #12)

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"l 8-7' Enclosure 1: i 10 CFR 50.92 Evaluation !

Backaround !

A study was conducted by the NRC to analyze industry problems associated with surveillance ;

testing required by Technical Specifications (TS). This study involved the following six criteria to make a qualitative assessment of the impact of proposed line item improvement: 1) direct !

safety impact; 2) indirect safety impact; 3) reliability; 4) occupational exposure; 5) operator

-l burden; and 6) NRC burden. The study found that while some testing at power is essential to - ,

verify equipment and system operability, safety can be improved, equipment degradation i decreased, unnecessary personnel radiation exposure reduced, availability of safety related l equipment increased, and unnecessary personnel burden relaxed by reducing the amount of i

~ testing at power. In December 1992, recommendations from the study for line item Technical Specification improvements were proposed by the NRC and documented in NUREG-1366,

" Improvements to Technical Specifications Surveillance Requirements." Generic Letter 93-05 l dated September 27,1993 was issued by the NRC to encourage licensees to propose Technical ;

Specification changes that are consistent with NUREG-1366. NUREG-1366 was used as the l basis for the proposed Farley Nuclear Plant Unit I and Unit 2 Technical Specification changes. !

Analysis l The proposed changes to the Farley Unit I and Unit 2 Technical Specifications allow for improvements to the Technical Specifications surveillance requirements. The proposed changes i will relax unnecessary personnel burden, decrease equipment degradation, reduce unnecessary personnel radiation exposure, and assure the availability of safety related equipment without compromising the protection of the public health and safety. ,

SNC has reviewed the requirements of 10 CFR 50.92 as they relate to the proposed changes !

and has made the following determination:

1. The ; roposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed changes do not involve any change to the configuration or method of operation of any plant equipment used to mitigate the l consequences of an accident. The changes to the surveillance requirements will result in an )

overall improvement in plant safety by reducing the likelihood of plant trips and subsequent i challenges to safety systems, decreasing equipment degradation due to excessive testing, l reducing radiation exposure to plant personnel, increasing the availability of safety related equipment, and eliminating an unnecessary burden on plant personnel. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident

previously evaluated.

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"' 2 Enclosure 2 10 CFR 50.92 Evaluation

2. The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes do not involve any change to ;

the configuration or method of operation of any plant equipment used to mitigate the ;

consequences of an accident. The relaxation of surveillance tests curtails the excessive amount !

of testing that increases wear on the equipment and reduces the likelihood of plant trips and l subsequent challenges to safety systems. The relaxation also increases the availability of safety {

related equipment. Accordingly, no new failure modes have been defined for any plant syrtem !

or component important to safety nor has any new limiting failure been identified as a result of i the proposed changes. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. l

3. The proposed changes do not involve a significant reduction in a margin of safety. The proposed changes eliminate an unnecessary burden without compromising protection for public f health and safety. The proposed changes were generically analyzed by the NRC as part of a !

comprehensive study and presented in NUREG-1366 " Improvements to Technical specifications Surveillance Requirements." The NRC concluded that while some testing at i

< power is essential to verify equipment and system operability, safety can be improved, .

equipment degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at power. SNC has analyzed plant operations and made a comparison with l the criteria stated in NUREG-1366 for the line-item improvements contained in this request and has found the NUREG-1366 basis to be consistent with the Farley design and operation ;

experience. Therefore, the proposed changes do not involve a significant reduction in a margin ofsafety.

Conclusion Based on the preceding analysis, SNC has determined the proposed changes to the technical ,

specifications will not significantly increase the probability or consequences of an accident !

previously evaluated, create the possibility of a new or different kind of accident from any .

accident previously evaluated, or involve a significant reduction in a margin of safety. l Therefore, SNC has determined the proposed changes meet the requirements of 10 CFR ;

50.92(c) and do not involve a significant hazards consideration. !

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i Enclosure 3 Joseph M. Farley Nuclear Plant Request To Incorporate Line-Item Improvements Technical Specification Channes Pane Change Instructions Unit 1 ,

Remove Pane Insert Pane 3/4 1-15 3/4 1-15 3/4 3-41 3/4 3-41 3/45-2 3/45-2 3/4 6-11 3/4 6-11 ,

3/4 6-20 3/4 6-20 .

3/4 10-1 3/4 10-1 Unit 2 j Remove Pane Insert Pane 3/4 1-15 3/4 1-15 3/4 3-41 3/4 3-41 3/45-2 3/4 5-2 3/4 6-11 3/4 6-11 .

3/4 6-20 3/4 6-20 3/4 10-1 3/4 10-1 l

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~; - REACTIVITY CONTROL SYSTEMS

- LIMITING CONDITION FOR OPERATION (Continued) b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c) . A power distribution map is obtained from the movable incore detectors and '

FQ(Z) and Fh are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and d) The THERMAL POWER level is reduced to less than or equal to 75% of ,

RATED TliERMAL POWER within one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

SURVEILLANCE REOUIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intenals when the Rod Position Deviation Monitor is inoperable, then verifying the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 92 days. l FARLEY - UNIT 1 3/4 1-15 AMENDMENT NO.M 1

m p TABLE 4.3-3 -

m p RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUTREMENTS h CHANNEL MODES IN WHICH q CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

- INSTRUMENT CHECK CALIBRATION TEST REOUTRED l

1. AREA MONITORS

a. Fuel Storage Pool Area (R-5) S R Q

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b. Containment Area (R-27A&B) S 'R N/A 1, 2, 3, 4

2. PROCESS MONITORS

a. Fuel Storage Pool Area E

y Gascous Actisity-3 Ventilation System R "

isolation (R-25 A&B) S Q l

b. Containment

i. Gaseous Actisity a) Purge and Exhaust Isolation (R-24 A&B) S R Q ALL MODES l b) RCS Leakage Detection (R-12) S R Q 1, 2, 3 & 4 l ii. Particulate Actisity K RCS Leakage Detection (R-1I) S R Q 1,2,3 & 4 l C i K c. Control Room Isolation S R Q 1,2,3. 4 and during l m movement of k irradiated fuel or Z mowment ofloads

.O over irradiated fuel k

With fuel in the storage pool or building.

" With irradiated fucI in the storage pool.

.1 EMERGENCY CORE COOLING SYSTEMS SURVFII.T ANCE REOIHREMENTS (CnntinneA) ,

b. At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the accumulator solution. His surveillance is not required when the volume increase makeup source is the RWST and the RWST has not been diluted since verifying that the RWST boron concentration is within the accumulator boron concentration limit.

c. At least once per 31 days when the RCS pressure is above the P-1I setpoint by verifying that power to each isolation valve operator is disconnected by a locked open disconnect device.

d. At least once per 18 months by verifying that each accumulator isolation valve opens automatically under each of the following conditions: ,

1. When the RCS pressure (actual or simulated) exceeds the P-11 (Pressurizer i Pressure Block of Safety Injection) setpoint,

2. Upon receipt of a safety injection test signal.

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FARLEY - UNIT 1 3/45-2 AMENDMiiNT NO.93 l

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CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLINO SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITINO CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY: MODES 1,2,3 and 4.

t ACTION:

l With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SilUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

jpRVEILLANCE REOUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, scaled, or otherwise secured in position, is in its correct position.

b. By verifying, that on recirculation flow, each pump develops a discharge pressure ofgreater than or equal to 210 psig when tested pursuant to Specification 4.0.5.

c. At least once per 18 months during shutdown, by:

1. Verifying that each automatic valve in the flow path actuates to its correct position on a Phase B test signal.

2. Verifying that each spray pump starts automatically on a Phase B test signal.

d. At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozz!c is unobstructed.

FARLEY - UNIT 1 3/4 6-11 AMENDMENT NO. 26

n CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS -W LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILI ANCE REOUIREMENTS 4.6.4.2 Each hydrogen secombiner system shall be demonstrated OPERABLE:

a. At least once each refueling interval by verifying during a recombiner system ,

functional test that the minimum heater sheath temperature increases to greater than or equal to 700 F within 90 minutes. Upon reaching 700 F, increase the power sctting to maximum power for two minutes and verify that the power meter reads ,

greater than or equal to 60 KW.

b. At least once each refueling interval by: l

1. Performing a CHANNEL CALIBRATION of all recombiner instmmentation (

and control circuits.

2. Verifying through a visual examination that there is no evidence of abnormal !

conditions within the recombiners (i.e., loose wiring or structural connections, deposits of foreign materials, etc.)

3. Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

1 FARLEY - UNIT 1 3/4 6-20 AMENDMENT NO.M

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' 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHITI'DOWN MARGIN.

LIMITING CONDITION FOR Q_PERATION 3.10.1 'Ihe SilUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod wonh and chutdown margin provided the reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod (s).

APPLICABILITY: MODE 2.

ACTION:

a. With any full length control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at greater thr.n or equal to 7006 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored,

b. With all full length control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REOUIREMENTS 4,10.1.1 The position of each full length rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full length rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

FARLEY - UNIT 1 3/4 10-1 AMENDMENT NO. 26-

'- REACTIVITY CONTROL SYSTEMS

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LIMITINO CONDITION FOR OPERATION (Continued) b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c) A power distribution map is obtained from the movable incore detectors and F (Z) and F%; are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and Q

d) 'Ihe TIIERMAL POWER level is reduced to less than or equal to 75% of RATED TliERMAL POWER within one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED TIIERMAL POWER.

SURVEILLAN_CE REOUIREMENTS ,

4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Position Deviation Monitor is inoperable, then verifying the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 92 days. l .

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AMENDMENT NO.

FARLEY - UNIT 2 3/4 1-15 i

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. TABLE 4.3-3 , . ,

l RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS C CHANNEL MODES IN WHICH l h INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION FUNCTIONAL TEST SURVEILLANCE d REQUIRED

1. AREA MONITORS

a. Fuel Storage Pool Area I (R-5) S 'R Q

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! b. Containment Area (R-27A&B) S R N/A 1, 2,3, 4

2. PROCESS MONITGRS i a. Fuel Storage Pool Area w

k w Gaseous Actisity-i

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Ventilation System l R **

Isolation (R-25 A&B) S Q 8

b. Containment

i. Gaseous Actisity a) Purge and Exhaust isolation (R-24 A&B) S R Q ALL MODES l

b) RCS Leakage Detection g (R-12) S R Q 1, 2,3 & 4 l ii. Pasticulate Acthity k RCS Leakage Detection (R-1l) S R Q 1,2,3 & 4 l

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C jf c. Control Room isolation S 'R Q 1,2,3. 4 and during l mmunent of H irradiated fuel or Z movement ofloads -

9 over irradiatcd fuel

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With fuel in the storage pool or building.

- With irradiated fuel in the storage pool.

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EMERGENCY CORE COOLING SYSTEMS SIIRVFli.T ANCE REQUIREMENTS (Cnntinnad) -

b. At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months aAer each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the (

accumulator solution. This surveillance is not required when the volume increase makeup - .

source is the RWST and the RWST has not been diluted since verifying that the RWST horon concentration is within the accumulator boron concentration limit. :

c. I At least once per 31 days when the RCS pressure is above the P-1I setpoint by verifying that power to each isolation valve operator is disconnected by a locked open disconnect -

device.

d. At least once per 18 months by verifying that each accumulator isolation valve opens automatically under each of the following conditions:

1. When the RCS pressure (actual or simulated) exceeds the P-11 (Pressurizer Pressure Block of Safety Injection) setpoint,

2. ' Upon receipt of a safety injection test signal.

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FARLEY - UNIT 2 3/45-2 AMENDMENT NO.M

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CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system j.I capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY: MODES 1,2,3 and 4.

ACTION: I With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least ilOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable spray i system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SilUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or ,

automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 210 psig when tested pursuant to Specification 4.0.5. ,

c. At least once per 18 months dnring shutdown, by:

1. Verifying that cach automatic valve in the flow path actuates to its correct position on a Phase B test signal.

2. Verifying that each spray pump starts automatically on a Phase B test signal.

d. At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

FARLEY - UNIT 2 3/46-11 AMENDMENT NO.

CONTAINMENT SYSTEMS ELECTRIC IWDROGEN RECOMBINERS -W LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

a. At least once each refueling interval by verifying during a recombiner system functional test that the minimum heater sheath temperature increases to greater than or equal to 700'F within 90 minutes. Upon reaching 700 F, increase the power setting to maximum power for two minutes and verify that the power meter reads greater than or equal to 60 KW.

b. At least once each refueling interval by: l

1. Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.

2. Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiners (i.e., loose wiring or structural connections, deposits of foreign materials, etc.)

3. Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test. "Ile resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

FARLEY - UNIT 2 3/4 6-20 AMENDMENT NO.

. -~ ..

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN t

LIMITING CONDITION FOR OPERATION 3.10.1 'The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided the reae u - equivalent to at least the highest estimated control rod worth is available for trip insertion from OP4 sJLE control rod (s).

\

APPLICABILITY: MODE 2.

ACTION:

a. With any full length control rod not fully inserted and with less than the above reactisity equivalent available for trip insertion, immediately initiate and continue boration at greater than or equal to 7000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

b. With all full length control rods fully inserted and the reactor suberitical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REOUIREMENTJ _

4.10.I'.1 The position of each full length rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full length rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdraws )sition within 7 days prior to reducing the SHUTDOWN MARGIN to less than the hmits of Specification 3.1.1.1.

FARLEY - UNIT 2 3/4 10-1 AMENDMENT NO.

s

Enclosure 4 Joseph M. FarleyNuclearPlant ,

Request To Incorporate Line-Item Improvements i Technical Specification Changes Hand-Marked Pares P

o p

i

1

, . i 1

I

1. (GL #4.2.1) Control Rod Movement Test !

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) b) The SHUTDOWN MARGIN . requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c) Apowerdistributionmapisobtajnedfromthemovable incore detectors and Fo(Z) and F are verified to be within their limits within 72 ho8yrs and d) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS , 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per JT a s. .

FARLEY-UNIT 1 3/4 1-15 AMEN 0 MENT NO. Efr ,

7 1

9e REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 4 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c) Apowerdistributionmapisobtajnedfromthemovable incore detectors and F (Z) and F are verified to be within their limits wiEhin 72 hobYs and d) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS

(

4.1.3.1.1 The position of each full length rod .shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Position Deviati)n Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 4.1.3.1.2 Each full length rod not fully inserted in the core shall be deter-mined to be OPE LE by movement of at least 10 steps in any one direction at least once per ays.

92 I

FARLEY-UNIT 2 3/4 1-15 f %e u ,3 % g,y7 gio,,

l l

2. (GL #5,14) Radiation Monitors

TA8LE 4.3-3 5

RADIATION MONITORING INSTRUNENTATION SURVEILLANCE REQUIREMENTS C! CHANNEL M00ES IN-WICH CHANNEL FUNCTIONAL SURVEILLANCE CHANNEL b' CHECK CALIBRATION TEST REQUIRED g INSTRUNENT

1. AREA MONITORS

Fuel Storage Pool Area S E d.

a.

(R-5)

S R N/A 1,2,3,4

b. Containment Area (R-27A&B)

2. PROCESS W ITORS

a. Fuel Storage Pool Area Gaseous Activity -

Ventilation Syst. eat a **

t' Isolation (R-25 A88) S R YQ .

Y b. Containment

=

" i. Gaseous Activity a) Purge & Exhaust All MODES R

Isolation (R-24 A48) S R 1,2,3 & 4 b) RCS Leakage Detection S (R-12)

11. Particulate Activity V

5 R YQ 1,2,3 & 4 g RCS Leakage Detection S (R-11)

S R 1,2,3,4 and during

-* c. Control Room Isolation movement of irradiated g fuel or movement of loads over irradiated fuel "With fuel in the storage pool or building.

With irradiated fuel in the storage pool.

m TABLE 4.3-3 5

l!! RADIATICII MONITORING INSTRUENTATION SURVEILLANCE REQUIREENTS Q

CHANNEL PRIDES IN WHICH

!' CHANNEL CHAISIEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATION TEST I NT ItEQUIRED

1. AREA IRINITORS

a. Fuel Storage Pool Area (R-5)

S R fG. *

b. Containment Area (R-27A88) S R N/A 1,2,3,4

2. PeoCESS 90lITORS

a. Fuel Storage Pool Area Gaseous Activity -

Ventilation Systen y g Isolation (R-25 A48) S R YG **

b. Containment

]" 1. Gaseous Activity a) Purge & Exhaust Isolation (R-24 A88) S R All MODES g

b) RCS Leekage Detection (R-12)

S R [Q 1,2,3 & 4 k 11. Particulate Activity 2

Jrb, g aCS Leakage setection 5 R 1,2,3 & 4 (R-11)

E

' .)

c. Control Room Isolation 5 R fG 1,2,3,4 and duri h movement of irred ated l fuel or movement of loads over irradiated fuel ith fuel in the storage pool or building.

_ With irradiated fuel in the storage pool, m

ss . i r

3. (GL #7.1) Surveillance of Baron Coacentration in the Accumulator / Safety Iniection/ Core Flood Tank h

I I

i

)

I f

I i

i

, - - , , , .- I m

SURVEILLANCE REQUIREMENTS (Continued) i

b. At least once per 31 days and within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after each solution !

volume increase of greater than or equal to 15 of tank volume by vertfying the boron concentration of the accumulator solution. ,

c. At least once per 31 days when the RCS pressure is above the P-11 setpoint by verifying that power to each isolation valve operator is disconnected by a locked open disconnect device.

l

d. At least once per la months by verifying that each accumulator isolation valve opens automatically under each of the following conditions:

1. tihen the RCS pressure (actual or simulated) escoeds the P-11 (Pressurizer Pressure Block of Safety Injection) setpoint, i

3. Upon receipt of a safety injection test signal. ,

Thi6 Surveil \.ance 1S not nequiM w ,en 4he

/

volume increase makev.o coune rs -he RwsT and N RWGT ha.9 not wn & lum 5Me .

ver inA-that 1he RW9r boron aWentration {:

is wi hiX the occamalAtor borm concehkd,M I

Limi4.

i I

l O

L FARLEY-UNIT 1 3/4 5-2 AMENOMENT NO. &

l

$MERGENCYCORECOOLINGSYSTEMS .

~.

SURVEILt.ANCE REQUIREMDf75 (Continued) b

b. At least .ence per 31 days and within g hours after each eelutten volume increase of greater than er equal to 15 of tank volume by verifying the beren concentration of the accueulater solution.

c. k At least once per 31 days when the RCS pressure is above the P-Il setpoint by verifying that power to each isolatir valve opera %r is disconnected by a locked open disconnect device.

l

d. At least once per 18 months by verifying that each occueulater isolation valve opens automatically under each of the fe11 ewing conditions:

1. idhen the RCS pressure (actual er simulated) eaceeds the P-11 (Pressurizer Pressure Block of Safety Injection) setpoint.

2. 44mn receipt of a safety injection test signal.

uhed when the vctam/e, Th6 surveittans increa50 makeup 16 not req (G The Rur7T ah4 the RW9 Source ha6 Md ben chlafed since VenfyinA that 4h6 RN97 b0fon COnCenWO.Y10Y115 Wlhhin ih&'GCCUMlU.lG$W' baron concentrakion Lim &.

Q l

l l

~'

FARLEY-UNIT 2 . 3/4 5-2 AMENOMENT 10. @

)

4. (GL #8.1) Containment Sorav System i

l

, . . i <

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS l l

CONTAINMENT SPRAY SYSTEM 1

LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERA 8LE with each '

spray system capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION: .

1 With one conthinment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable ' spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l SURVEILLANCE REQUIREMENTS i

4.6.2.1 Fach containment spray system shall be demonstrated OPERABLE:

1

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 210 psig when tested pursuant to Specification 4.0.5.

tc. At least once per 18 months during shutdown, by: ,

1. Verifying that each automatic valve in the flow path actuates to its correct position on a Phase B test signal.

2. Verifying that each spray pump starts automatically on a Phase 8 test signal.

d. At least once perht' years by performing an air or smoke flow test ,

through each spray header and verifying each spray nozzle is unobstructed.

FARLEY-UNIT 1 3/4 6-11 '

0. __ :

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump.

APPLICABILITY: MODES 1, 2, 3 and 4.

- ACTION:

With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 heurs; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

S_URVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall b' demonstrated e OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position. l

b. By verifying, that on recirculation flow, each pump develops a '

discharge pressure of greater than or equal to 210 psig when tested pursuant to Specification 4.0.5.

c. At least once per 18 months during shutdown, by:

1. Verifying that each automatic valve in the flow path actuates to its correct position on a Phase B test signal.

l

2. Verifying that each spray pump starts automatically on a Phase B test signal.

d. At least once,perV ars by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

FARLEY-UNIT 2 3/4 6-11 A mengsem go, .

5. (GL #8.5) Hydrogen Recombiner t

l

CONTAINMENT SYSTEMS ELECTRIC NYDROGEN RECOMBINERS - W LIMITING CONDITION FOR OPERATION-3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.2 Each hydrogen combiner system shall be demonstrated OPERABLE:

each re o mTeM

a. At least once ,_rg eentke y verifying during a recombiner system functional test that the minimum heater sheath temperature increases togreaterthanorequalto700*Fwithin90 minutes. Upon reaching 700 F, increase the power setting to maximum power for two minutes and verify that the power meter reads greater than or equal to

(

60 KW~

60Chrefuel.tr13trihF l-

b. At least onceV;e- la renthe by:

1. Performing a CHANNEL CALIBRATION of all recombiner instrumenta-tion and control circuits.

2. Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiners (i.e. , loose wiring or structural connections, deposits of foreign materials, etc.)

3. Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ches.

l l

l FARLEY-UNIT 1 3/4 6-20 AMENOMENT N0. &

l l

..,..o.

9 % i 1-CONTAINMENT SYSTEMS f ELECTRIC HYOROGEN RECOMINERS - W l

LIMITING CONDITION FOR OPERATION ;

9 l

r 3.6.4.2 Two independent containment hydrogen recombiner systems shall be !

OPERABLE. j APPLICABILITY: MODES 1 and 2.

-1' ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system !

to OPERABLE status within 30 days or be in at least HOT SiAND8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS ;

- 4.6.4.2 Each hydrogen recom)iner s stem hall be demonstrated 0PERA8LE: !

each fr ue.irg i ;

a. At least once ;: 6 r :th: y verifying during a recombiner systes ;

functional test that the minimum heater sheath temperature increases to greater than or equal to 700*F within 90 minutes. Upon reaching ( :

700 F, increase the power setting to maximum power for two minutes ;

and verify that the power meter reads greater than or equal to i 60 W. frtferv4L earJ., refuep

b. At least onceV;;r L* n thdy. i

1. Performing a CHANNEL CALIBRATION of all recombiner instrumenta- 1 tion and control circuits. i

2. Verifying through a visual examination that there is no evidence ;

of abnormal conditions within the recombiners (i.e., loose i' wiring or structural connections, deposits of foreign materials, ,

etc.) !

3. Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ches. ,

i 5

j FARLEY-UNIT 2 3/4 6-20 A m su oscu.c g o, l

6. (GL #12) Special Test Exceptions l

l l

I i

l u j

e

.. . . .1 s t

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION _,

3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided the reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod (s).

APPLICABILITY: MODE 2.

ACTION:

a. With any full length control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at greater than or equal to 30 gpa of a solution containing greater than or equal to 7000 ppe boron or its equiva-1ent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored,

b. With all full length control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately I

initiate and continue boration at greater than or equal to 30 gpa of a solution containing greater than or equal to 7000 ppe boron or its .

equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length rod either partially or fully withdrawn shall. be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full length rod not fully inserted shall be demonstrated capable of full i 2' 5eu :ffertion prior towhen tripped reducing from at leastMARGIN the SHUTDOWN the 50%

to withdrawn position less than the limits ofwithin 1[Chig5 Specification 3.1.1.1.

( AMENDMENT NO.4NF FARLEY-UNIT 1 3/4 10-1 J

i 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUT 00WN MARGIN i

LIMITING CONDITION FOR OPERATION i

l 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided the reactivity c

equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod (s).

- APPLICABILITY: MODE 2. l ACTION:

a. With any full length control rod not fully inserted and with less than the above reactivity equivalent availat's for trip insertion, immediately initiate and continue boration at greati. than or equal to 30 gpm of a solution containing greater than or equai ,o 7000 ppe boron or its equiva- l 1ent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

b. With all full length control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately

( initiate and continue boration at greater than or equal to 30 gpo of a .

solution containing greater than or equal to 7000 ppe boron or its . l equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 1 4.10.1.1 The position of each full length rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full length rod not fully inserted shall be demonstrated capable -

nsertion when tripped from at least the 50% withdrawn position within of full 20 he.r; ) prior to reducing the SHUTDO)dt MARGIN to less than the limits of 7chij$ Specification 3.1.1.1.

f FARLEY-UNIT 2 3/4 10-1 A - e u o,4 u r M e.

ML20077R413

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