Text

Amends 73 & 48 to Licenses DPR-70 & DPR-75,respectively,. Revising Calibr Methods for Analog Rod Position Indication Sys
	ML20210K028
Person / Time
Site:	Salem
Issue date:	03/19/1986
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20210K035	List: ML20210K028; ML20210K037;
References
	NUDOCS 8604040522
	Download: ML20210K028 (24)
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UNITED STATES NUCLEAR REGULATORY COMMISSION 3

p WASHINGTON, D. C. 20555

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COPFANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. DPR-70 1.

The Nuclear Regulatory Comissian (the Commission) has found that:

A.

The application for amendment by Public Service Electric and Gas Comnany, Philadelphia Electric Company, Delmarva Power and Light Company and At.lantic City Electric Company (the licensees) dated October 16, 1985, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I;

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:

8604040522 860319 PDR ADOCK 05000272 P

PDR

2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 73 are hereby incorsorated in the license. The licensee shall operate the facility.in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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CLLur Steven A. Var frector W8 Project Directorate #3 Division of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of Issuance: March 19, 1986 i

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l ATTACHMENT TO LICENSE AMENDMENT N0. 73 f

FACILITY OPERATING LICENSE N0. DPR-70 l

DOCKET NO. 50-272 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 1-18 3/4 1-18 3/4 1-18a 3/4 1-18b 3/4 1-19 3/4 1-19 3/4 1-19a 3/4 1-20 3/4 1-20 3/4 1-22 3/4 1-22 4

3/4 1-23 3/4 1-23 8 3/4 1-4 8 3/4 1-4 t

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rods, shall. be OPERABLE and positioned within.+ 12 steps (indicated position) of their group step counter demand position within one hour after rod notion.

APPLICABILITY: MODES 1* and 2*

ACTION:

With one or more full length rods inoperable dub to being a.

immovable as a result o ' excessive friction or nachanical interference or known to be untrippable, determine that the SHUTDukN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

bdth mare than one full length rod inoperable or rais-aligned from the group step counter. demand position by more than j; 12 steps l

(indicated position), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

kNth one full length rod inoperable due to causes other than addressed by ACTION a, above, or mis-aligned from its group step counter demand position by porc than + 12 steps (indicated position), P0kER OPERATION may cantinue provided that within one hour either:

1.

The rod is restored to OPERABLE status within tne above alignment requirements, or 2.

The remainder of the rods in the bank with the inoperable, rod are aligned to within j; 12 steps of the inoperable rod while maintaining the rod sequerce and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL P0bER level shall be restricted pursuant to Specification 3.1,3.5 during Jubsequent operation, or 3.

The rod is declared inoperable and the SHUTD0bN MARGIN requirement of Specification 3.1.1.1 is satisfied. P0 bER OPERATION may then continue provided that:

See Special Test Exceptions 3.10.2 and 3.10.3.

SALEM - UNIT 1 3/4 1-18 Amendmnet No. 73 4

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a)

A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.

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 r.ower distribution map is obtained from the r.ovable i'ncore detectors and Fo(Z) and FRH are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d)

The THERMAL POER level is reduced to less than or equal to 75%

of RATED THERMAL POER 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 POER. THERMAL POER shall be maintained less than or equal to 75% of RATED THERMAL POER until compliance with ACTIONS 3.1.3.1.c.3.a and 3.1.3.1.c.3.c above are denonstrated.

SURVEILLANCE REQJIREMENTS 4.1.3.1.1 The position of each full. length rod shall be determined to be within + 10 steps (indicated position of the group demand position at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (allowing for one hour thermal soak after ro.d notion) except during time intervals when the Rod Ibsition Deviation Monitor is inoperable, then wrify the youp 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 novenant of at least 10 steps in any one direction at least once per 31 days.

SALEM - UNIT 1 3/4 1-18a Amendment No. 73 a

TABLE 3.1-1

'....s ACCIDENT ANALYSES RE'0VIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL LENGTH ROD Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Control Assembly Mis-alignment i

I Loss Of Reactor Coolt.it From Ruptured Pipes Or From Cracks In large Pipes hhich Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal At Full Rawer Major Rcactor Coolant System Pipe Ruptures (Loss Of Coolant Accident)

Major Secondary System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection)

Amendment No. 73 SA'.EM - UNIT 1 3/4 1-18b i

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REACTIVITY CONTROL SYSTEMS l

POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2.1 The shutdown and control rod position indication systems shall be OPERABLE and capable of determining the actual and demanded rod positions as follows:

Analog rod position indicators. Within one hour after rod notion a.

(allowance fer thermal soak);

All Shutdown Banks:

+ 12 steps of the group demand counters for withdrawal ranges of U-30 steps and 200-228 steps.

Control Bank A:

+ 12 steps of the group demano counters for withdrawal ranges of 0-30 steps and 200-228 steps.

Control Bank B:

+ 12 steps of the group demand counters for l

withdrawal ranges of 0-30 steps and 160-228 steps.

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Control Banks C and D:

+ 12 steps of the group demand counters for withdrawal range of U-228 steps.

b.

Group demand counters; + 2 steps of the pulsed output of the Slave Cycler Circuit over the withdrawal range of 0-228 steps.

APPLICABILITY: MODES 1 and 2.'

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ACTION:

a.

With a maximum of one analog rod position indicator per bank inoperable either:

1.

Determine the position of the non-indicating rod (s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and within one hour after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.

Reduce THERMAL P0hER to less than 50% of RATED THERMAL R3WER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b.

b4th a maximur. of one group demand position indicator per bank l

inoperable either:

SALEM - UNIT 1 3/4 1-19 Amendment No. 73

Verify that all analog rod position indicator's for the 1.

affected bank are OPERABLE and that the nost withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or Reduce THERMAL POER to less than 50% of RATED THERMAL POWE 2.

within 8 tours.

SURVEILLANCE REQJIREMENTS 4.1.3.2.1.1 Each analog rod position indicator shall be determined to be OPERABLE by verifying that the demand position indication system and the rod position indication system agree within 12 steps (allowing for one hour thermal soak after rod notion) 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 compare the demand position indication system and the rod position indication system at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.2.1.2 Each of the above required rod position indicator (s) shall be determined to be OPERABLE by performance of a CHANNEL calibration at least onca per 18 cenths.

i SALEM - UNIT 1 3/4 1-19a Amendment Nc, 73

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM SHUTDOW LIMITING CONDITION FOR OPERATION 3.1.3.2.2 The group demand position indicator shall be OPERABLE for each shutdown and control rod not fully inserted.

APPLICABILITY:

MODES 3*#, 4*#, and 5*#

ACTION:

With less than the above required group demand position indicator (s)

OPEP.ABLE, open the reactor trip system breakers.

SURVEILLANCE REQJIREMENTS 4.1.3.2.2 Each of the above required group demand position indicator (s) shall be determined to be OPERABLE by movement of the associated control rod at least 10 steps in any one direction at least once per 31 days.

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With the reactor trip system breakers in the closed position

See Special Test Exception 3.10.5 l

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SALEM - UNIT 1 3/4 1-20 Amendment No. 73 L

l REACTfyITY CONTROL SYSTEMS POSITION INDICATION SYSTEM SHUT 00W4 LIMITING CONDITION FOR OPERATION 3.1.3.4 All shutdown rods shall be fully withdrawn.

APPLICABILITY: MODES 1*, and 2*4 ACTION:

1 Mth a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:

a.

Fully withdraw the rod,, or b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQJIREMENTS 4.1.3.4 Each shutdown rod shall be determined to be fully withdrawn by use of the group demand counters, and verified by the analog rod position indicators within one h:ur after rod notion:

a.

Mthin 15 minutes prior to withdrawal of any rods in control banks A, B, C, 6r D during an approach to reactor critically, and b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thareafter.

See Special Test Exceptions 3.10.2 and 3.10.3 With X,ff greater than or equal to 1.0 i

4 SALEM - UNIT 1 3/4 1-22 Amendment No. 73 9

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l REACT 1VITY CONTROL SYSTEMS POSITION INDICATION SYSTEM SHUTD0bN LIMITING CONDITION FOR OPERATION 3.1.3.5 The control banks shall be limited in physical insertion as shown in Figures 3.1-1 and 3.1-2.

APPLICABILITY: H0 DES 1*, and 2 * #

ACTION:

With the control banks insarted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:

a.

Restore the control banks to within the limits within two hours, or b.

Reduce THERHAL F0kER within two hours to less than or equal to that fraction of RATED THERMAL P0bER which is allowed by the bank l

position using the above figures, or c.

Be in at least HOT STAND 8Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQJIREMENTS 4.1.3.5 Tho position of each controk bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by use of the group demand counters and verified by the analog rod position indicators within one hour f

of rud totion, except during time intervals when the Rod Insertion Limit j

Monitor is inoperable, then va.-ify the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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See Special Test Exceptions 3.10.2 and 3.10.3

91th K,7f greater than or equal to 1.0 I

I SALEM - UNIT 1 3/4 1-23 Amendment No. 73

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REACTIVITY CONTROL SYSTEMS BASES

_/4.1.3 MOVABLE CONTROL ASSEMBLIES 3

Tha specifications of this section ensure that (1) acceptable power distribution limits us maintained, (2) the minimum SHUTDOW MARGIN is ma.intained, and (3) limit the potential effects of rod mis-alignment on associated accident analyses.

OPERABILITY of the control rod position indicators is required to datermine control rod positions and thereby ensure compliance with the control rod OPERABLE condition for the analog rod position alignment and insertion limits.

indicators is defined as being capable of indicating rod position to within + 12 steps of the bank demand position for a range of positions. For the Shutdown Banks, and Control Bank A this range is defined as the youp demand c)unter indicated position between 0 and 30 steps withdrawn inclusive, and between 200 and 228 steps withdrawn inclusive. This permits the operator to verify that the 1

control rods in these banks are either fully withdrawn or fully inserted, the normal operating modes for these banks. Knowledge of these banks positions in these ranges satisfies all accident analysis assumptions concerning their The range for control Bank B is defined as the youp demand counter po sitio n.

indicated position between 0 and 30 steps withdrawn inclusive, and between 160 an 228 steps withdrawn inclusive. For Control Banks C and D the range is defined as the youp demand counter indicated position between 0 and 228 steps withdrawn.

Comparison of the group dentand counters to the bank insertion limits with verification of rod position with the analog rod position indicators (after thermal soak after rod notion) is sufficient verification that the control rods are above the insertion limits.

The ACTION statements which permit limited variation from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met. Mis-alignment of a rod requires naasurement of peaking factors or a restriction in THERMAL POER; either of these restrictions provide assurance of fuel rod integrity during continued operation. The reactivity w rth of a mis-aligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumption used in the accident analysis.

The maximum rod drop time restriction is consistent with the assumed rod drop i

time used in the accident analyses. Measurement with Tavg>541*F and with all reactor coolant. pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditio ns.

Control rod positions and OPERABILITI of the rod. position indicators are required to be verifled on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with nore frequent verifications required if an automatic nonitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

Amendment No. 73 SALEM - UNIT 1 8 3/4 1 4

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g NUCLEAR REGULATORY COMMISSION 5

E WASHINGTON, D. C. 20555

%.....o PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-75 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated Octob' 16, 1985, complies with the standards and require-ments of tb Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurarce (i) that the activities authorized by this amendment can be cor; ducted without endangering the health and safety of the public, ani (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:

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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 48 are hereby inenrporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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,even A. Va a, Director PWR Project Directorate #3 i

J Division of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of Issuance: March 19, 1986 i

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ATTACHMENT TO LICENSE AMENDMENT N0. 48 FACILITY OPERATING LICENSC NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 1-13 3/4 1-13 3/4 1-14 3/4 1-14 3/4 1-15 3/4 1-15 3/4 1-16 3/4 1-16 3/4 1-16a 3/4 1-17 3/4 1-17 3/4 1-19 3/4 1-19 3/4 1-20 3/4 1-20 B 3/4 1-4 B 3/4 1-4

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 1

3.1.3.1 All full length (shutdown and control) rods, shall be OPERABLE and positioned.within + 12 steps (indicated position) of their group step g

counter demand posTtion within one hour af ter rod notion.

APPLICABILITY: MODES 1* and 2*

ACTION:

a.

hMth one or mare full length rods in)perable due to being inmovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTD0bn MARGIN requirerent of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i b.

With more than one full length rod inoperable or mis-aligned from the group step counter demand position by more than j;12 steps l

4 (indicated position), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one full length rod inoperable due to causes other than addressed by ACTION a, above, or mis-aligned from its group step counter demand position by more than + 12 steps (indicated position), P0bER OPERATION may contin 3h provided that within one hour either:

1.

The sud is restored to OPERABLE status within the above alignrent requirements, or 2.

The remainder of the rods in the bank with the inoperable rod are aligned to within j;12 steps of the inoperable rod while naintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during tubsequent operation, or 3

The rod is declared inoperable and the SHUTD0hN MARGIN requirement of Sp?cification 3.1.1.1 is satisfied. P0bER OPERATION may then cantinue provided that:

See Special Test Exceptions 3.10.2 and 3.10.3.

SALEM - UNIT 2 3/4 1-13 Amendmen.t No. 48

a)

A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.

b)

The SHUTOOWN 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 novable incore detectors and F (Z) and F1J4 are verified to be within their 0

limits within 7'l hours.

d)

The THERMAf. POWER level is reduced to less than or equal to 7b%

of RATED THERMAL POER 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 POER. THERMAL POER shall be maintained less than or equal to 75% of RATED THERMAL POER until complianca with ACTIONS 3.1.3.1;c.3.a and 3.1.3.1.c.3.c above are demonstrated.

SURVEILLANCE REQUIREMENTS i

4.1.3.1.1 The position of each full length rod shall be determined to be l

l within 112 steps (indicated position of the group demand position at least I

once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (allowing for one hour thermal soak after rod notion) except during time intervals when the Rod Nsition 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 31 days.

I SALEM - UNIT 2 3/4 1-14 Amendment No. 48 s

TABLE 3.1-1 ACCIDENT ANALYSES REQJIR!NG REEVALUATION IN THE EVENT OF AN INOPERABLE FULL LENGTH ROD Rod Clustar Control Assembly Insartion Characteristics Rod Cluster Control Assembly Mis-alignment loss Of Reactor Coolant From Ruptured Pipes Cr From Cracks In large Pipes mich Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Mthdrawal At Full Ibwer Major Reactor Coolant System Pipe Ruptures (Loss Of Coolant Accident)

Major Sec::ndary System Pipe Rupture Rupture of a Control Rod Drive Mechanism ibusing (Rod Cluster Control Assembly Ejection)

SALEH - UNIT 2 3/4 1 15 Amendment No. 49 h

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REACTIVITY CONTROL SYSTEMS i

i POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2.1 The shutdown and control rod position indication systens shall be OPERABLE and capable of determining the actual and demanded' rod positions as follows:

a.

Analog rod position indicators, within one hour after rod motion (allowance for thermal soak);

All Shutdown Bsnks:

+ 12 steps of the group demand counters for withdrawal ranges of F-30 steps and 200-228 steps.

Control Bank A:

+ 12 steps of the group demand counters for withorawal ranges of 0-30 steps and 200-228 steps.

Control Bank B:

+ 12 steps of the group demand counters for withdrawal ranges of 0-30 steps and 160-228 steps.

Control Banks C and 0:

+ 12 steps of the group demand counters for withdrawal range of U-228 steps.

b.

Group demand countersi + 2 steps of the pulsed output of the Slave Cycler Circuit over the withdrawal range of 0-228 steps.

APPLICABILITY: MODES 1 and 2.

ACTION:

a.

bMth a maximum of one analog rod position indicator per bank l

inoperable either:

1.

Determine the position of the non-indicating rod (s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and within one hour after any motion of the "non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.

Reduce THERMAL POER to less than 50% of RATED THERMAL POER within' 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b.

h4th a weximum of one group demand positinn indicator per bank l

inoperable either:

f Amendment No. 48 l

SALEM - UNIT 2 3/4 1 16 l

9 1.

Verify that all analog rod position indicators for the l

affected bank are OPERABLE and that the most withdrawn rod 1

and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 2.

Reduce THERMAL P0hER to less than 50% of RATED THERMAL P0kER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.2.1.1 Each analog rod position indicator shall be determined to be OPERABLE by verifying that the demand position ind.ication system and the rod position indication system agree within 12 steps (allowing for one hour thermal soak after rod motion) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during tire intervals when the Rod Rosition Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indication system at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.2.1.2 Each of the above required rod position indicator (s) shall be determined to be OPERABLE by performance of a CHANNEL calibration at least.

once per 18 months.

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SALEM - UNIT 2 3/4 1-16a Amendment'No. 48

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM SHUTD0hN LIMITING CONDITION FOR OPERATION 3.1.3.2.2 The group demand position indicator shall be OPERABLE for each shutdown and control rod not fully inserted.

APPLICABILITY: MODES 3*#, 4*#, and 5*#

ACTION:

With less than the above required group demand position indicator (s)

OPERABLE, open the reactor trip system breakers.

SURVEILLA'NC'E REqu!REMENTS 4.1.3.2.2 Each of the above required group demand position indicator (s) shall be determined to be OPERABLE by movement of the associated control rod at least 10 steps in any one direction at least once per 31 days.

kHth the reactor trip system breakers in the closed position

See Special Test Exception 3.10.5 1

SALEM - UNIT 2 3/4 1-17 Amendment No. 48 l

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i REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM SHUT 00bN LIMITING CONDITION FOR OPERATION 3.1.3.4 All shutdown rods shall be ' fully withdrawn.

APPLICABILITY: MODES 1*, and 2 * #

ACTION:

With a maximum of one shut.down rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:

a.

Iully withdraw the rod,, or b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.4 Each shutdown rod shall be determined to be fully withdrawn by use of the group demand counters, and verified by the analog rod position indicators within one hour after rod notion:

a.

Mthin 15 minutes prior to withdrawal of any rods in control banks A, 8, C, or 0 during an approach to reactor c.-itically, and b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

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See Special_ Test Exceptions 3.10.2 and 3.10.3

With Keff greater than or equal to 1.0 J

Amendment No. 48 SALEM - UNIT 2 3/4 1-19

REACTIVITY CONTROL SYSTEMS

- -s POSITION INDICATION SYSTEM SHUTD0kN LIMITING CONDITION FOR OPERATION 3.1.3.5 The control banks shall be limited in physical insertion as shown in Figures 3.1-1 and'3.1-2.

APPLICABILITY: MODES 1*, and 2*#

ACTION:

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:

a.

Restore the control banks to within the limits within two hours, or b.

Reduce THERMAL P0kER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank l

position using the a,bove figures, or c.

Se in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQJIREMENTS 4.1.3.5 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by use of the group demand counters and verified by the analog rod position. indicators within one hour of rod motion, except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least' once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exceptions 3.10.2 and 3.10.3

With Keff greater than or equal to 1.0 SALEM - UNIT 2 3/4 1-20 Amendment No. 48

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0 REACTIVITY CONTROL SYSTEMS 8_ASES 3/4.1.3 HOVABLE CONTROL ASSEMBLIES The specifications of this section ansure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUT 00W MARGIN is maintained, and (3) limit the potential effects of rod mis-alignment on associated accident analyses.

OPERABILITY of the control rod position indicators is required to determine i

control rod positions and thereby ensure compliance with the control rod OPERABLE condition for the analog rod position alignment and insartion limits. indicators is defined as being capable of indicating r For the Shutdown steps of the bank demand position for a range of positions.

Banks, and Control Bank A this range is defined as the group demand counter indicated position between 0 and 30 steps withdrawn inclusive, and between 200 This permits the operator to verify that the and 228 steps withdrawn inclusive.

control rods in these banks are either fully withdrawn or fully inserted, the Knowledge of these banks positions in normal operating nodes for these banks.

these ranges satisfies all accident analysis assumptions concerning their The range for control Bank B is defined as the group demand counter position.

indicated position between 0 and 30 steps withdrawn inclusive, and between 160 an 228 steps withdrawn inclusive. For Control Banks C and D the range is defined as the youp demand counter indicated position between 0 and 228 steps withdrawn.

Comparison of the group demand counters to the bank insertion limits with verification of rod position with the analog rod position indicators (after thermal soak after rod notion) is sufficient verification that the control rods are above the insertion limits.

The ACTION statements which permit limited variation from the basic requirements 1

are accompanied by additional restrictions which ensure that the original criteria are met. Mis-alignment of a rod requires measurement of peaking factors or a ecstriction in THERMAL POER; either of these restrictions provide assurance of fuel rod integrity during continued operation. The reactivity wrth of a mis-aligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumption used in the accident analysis.

The maximum rod drop time restriction is consistent with the assumed rod drop i

time used in the accident analyses. Measurement with Tayg>541*F and with all reactor coolant. pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating i

co nditio ns.

Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with nore frequent These verifications required if an automatic nonttoring channel is inoperable.

verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

SALEM - UNIT 2 B 3/4 1-4 Amendment No.- 48 l

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