Text

Proposed Tech Specs Incorporating Generic Ltr 90-06 Requirements
	ML18096B111
Person / Time
Site:	Salem
Issue date:	11/17/1992
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18096B110	List: ML18096B109; ML18096B111;
References
	GL-90-06, GL-90-6, NUDOCS 9211240327
	Download: ML18096B111 (37)
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ATTACHMENT 1 LCR 91-06 (Rev. 1)

NLR-N92156 REQUEST FOR LICENSE AMENDMENT INCORPORATION OF GENERIC LETTER 90-06 REQUIREMENTS SALEM GENERATING STATION UNITS 1 AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311

_,---9211240327 921117 PDR ADOCK 05000272 p

PDR

l I.

Description of Change A. 91-06 (Rev. 1)

NLR-N92156 This amendment change request proposes that existing Technical Specification 3.1.2.3, "CHARGING PUMP -

SHUTDOWN", be administratively revised such that:

A surveillance is added to verify that all safety injection pumps and centrifugal charging pumps are inoperable except for the single pump required to be operable.

This guidance is currently provided in technical specification 3.5.3 but is being restated here for clarity.

A note is added to specify that a maximum of one safety injection pump or one centrifugal charging pump shall be operable in Mode 5 or Mode 6 when the head is on the reactor vessel.

This guidance is currently provided in technical specification 3.5.3 but is being restat~d here for clarity.

This amendment change request proposes that existing Technical Specification 3.1.2.4, "CHARGING PUMPS -

OPERATING", be administratively revised such that:

A surveillance is added to verify that all safety injection pumps and centrifugal charging pumps are inoperable except for the single pump required to be operable while in Mode 4 and the temperature of any cold leg is less than or equal to 312°F.

This guidance is currently provided in technical specification 3.5.3 but is being restated here for clarity.

A note is added to specify that a maximum of one safety injection pump or one centrifugal charging pump shall be operable in Mode 4 when the temperature of any cold leg is less than or equal to 312°F.

This guidance is currently provided in technical specification 3.5.3 but is being restated here for clarity.

I This amendment change request proposes that existing Technical Specification 3/4.4.3 for DPR-70 (Unit 1) and 3/4.4.5 for DPR-75 (Unit 2), "RELIEF VALVES", be revised such that:

With one or both Power Operated Relief Valves (PORVs) inoperable due to excessive leakage, continued plant operation shall be permitted only if the associated Block Valve(s) is closed with power maintained.

PAGE 1 OF 7 ATTACHMENT 1

.. 91-06 (Rev. 1)

NLR-N92156 With one PORV inoperable for reasons other than excessive leakage, continued plant operation shall be permitted only if the associated Block Valve is closed and de-energized within one hour and the affected PORV is returned to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

With both PORVs inoperable for reasons other than excessive leakage, continued plant operation shall be permitted only if at least one PORV can be restored to operable status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one or both Block Valve(s) inoperable, either the valve(s) shall be restored to operable status or the associated PORVs shall be placed in manual control within one hour.

If both Block Valves are inoperable, at least one shall be restored to operable status within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Any remaining inoperable Block Valve shall be restored to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Each PORV shall be demonstrated operable on an 18 month test interval by: 1) operating the valve through one complete cycle of. travel during Modes 3 or 4, 2) operating solenoid, control, and check valves associated with the PORV accumulators through one complete cycle of travel, and 3) performing a channel calibration of the actuation instrumentation.

Each Block Valve shall be demonstrated operable on a 92 day test interval by operating the valve through one complete cycle of travel.

This amendment change request proposes that existing Technical Specification 3.4.9.3 for DPR-70 and 3.4.10.3 for DPR-75, "OVERPRESSURE PROTECTION SYSTEMS", be revised such that:

With one PORV inoperable in Mode 4, the inoperable PORV shall be restored to operable status within 7 days or the reactor coolant system shall be vented within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

With one PORV inoperable in Modes 5 or 6 with the Reactor Vessel Head installed, the inoperable PORV shall be restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or the reactor coolant system shall be vented within a total of 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months .

The reference to the specific ASME valve category is deleted from the surveillance requirements for consistency (applicable to DPR-70 only).

PAGE 2 OF 7 ATTACHMENT 1

A. 91-06 (Rev. 1)

NLR-N92156 Finally, this amendment -change request proposes that existing Technical Specification 3.5.3, "ECCS SUBSYSTEMS -

T ave < 350°F",

be administratively revised such that:

The applicability of the note pertaining to the LCO and surveillance 4.5.3.1 is reworded for clarity.

II.

Reason for Proposed Change PSE&G is submitting this amendment request in partial fulfillment of the requirements set forth in NRC Generic Letter (GL) 90-06 dated June 25, 1990.

GL 90-06 provided the staff's positions on the resolution of Generic Issue 70 (GI-70), "Power-Operated Relief Valve and Block Valve Reliability", and Generic Issue 94 (GI-94), "Additional Low-Temperature Overpressure Protection for Light-Water Reactors".

Following the TMI-2 accident, the NRC initiated an effort to evaluate the role of PORVs in performing certain safety-related functions.

Consequently, the NRC determined that over a period of time, the role of PORVs has changed such that PORVs are now relied upon by various plants to perform one, or more, of the following safety-related functions:

1.

Mitigation of a design-basis steam generator tube rupture accident,

2.

Low-temperature overpressure protection of the reactor vessel during startup and shutdown, and/or,

3.

Plant cooldown in compliance with Branch Technical Position RSB 5-1 to SRP 5.4.7, "Residual Heat Removal (RHR) System".

Based on these findings, it was determined that the safety classification of PORVs and block valves should be reconsidered.

The NRC subsequently issued a list of actions in GL 90-06 as part of the technical resolution of GI-70 to be taken by PWR plants to increase the reliability of PORVs and block valves and provide assurance that they will function as required in response to a Steam Generator Tube Rupture event.

One of the required actions delineated in GL 90-06 is to modify the existing technical specifications for the PORVs and block valves in Modes 1, 2, and 3.

GI-94 arose as a result of continuing low-temperature overpressure events and the unavailability of Low-Temperature Overpressure Protection (LTOP) channels.

PORVs are relied upon by most Westinghouse PWRs, Salem included, to provide PAGE 3 OF 7 ATTACHMENT 1

A. 91-06 (Rev. 1)

NLR-N92156 low-temperature overpressure protection.

Based on the NRC evaluation of the LTOP system unavailability, it was concluded that additional restrictions are warranted and that existing technical specifications should be modified for the affected plants.

The technical specification changes encompassed by this amendment request are those that have resulted from the resolutions of GI-70 and GI-94 and which have been delineated and justified by the NRC in GL 90-06.

Where differences exist between the modified technical specifications provided in GL 90-06 and those contained in this amendment request, full justification has been provided.

III. Justification for the Proposed Change Specifications 3.1.2.3, "CHARGING PUMP -

SHUTDOWN". and 3.1.2.4,

_**"CHARGING PUMP -

OPERATING".

The changes that are proposed for specifications 3.1.2.3 and 3.1.2.4 are in response to the requirements delineated and justified in GL 90-06, Enclosure B, pages B-10 and B-11.

These requirements provide Low Temperature Overpressure Protection (LTOP) and apply when: 1) the plant is in Mode 4 and any RCS cold leg temperature is less than or equal to 312°F (plant specific value), 2) Mode 5, and 3) Mode 6 when the head is on the reactor vessel.

LTOP is provided by allowing a maximum of one safety injection pump or one centrifugal charging pump to be operable thereby limiting the largest potential mass addition to the RCS to within the capability of the LTOP system.

This guidance is currently contained in specification 3.5.3, "ECCS -

T ave < 350°F".

However, since specification 3.5.3-is only applicable in Mode 4, it was felt prudent to restate the guidance in specification 3.1.2.3, applicable in Modes 5 and 6, and specification 3.1.2.4, applicable in Modes 1, 2, 3, and 4, for improved clarity.

As these changes do not delineate any new or differing guidance and are proposed for clarity only, they are considered administrative in nature.

Specification 3/4.4.3 CDPR-70, Unit 1) and 3/4.4.5 CDPR-75, Unit 2), "RELIEF VALVES".

The changes that are proposed for specification 3/4.4.3 (DPR-70, Unit 1) and 3/4.4.5 (DPR-75, Unit 2) are in response to the requirements delineated in GL 90-06, Enclosure A, pages A-4, A-5, and A-7 and justified on pages A-8 through A-10.

These requirements are based on improving the reliability of PORVs and block valves.

PAGE 4 OF 7 ATTACHMENT 1

1' 91-06 (Rev. 1)

NLR-N92156 The modified A-5 and A-7 technical specifications contained on pages A-4, of Enclosure A to GL 90-06 have been fully incorporated exceptions:

into this amendment request with the following The surveillance requirement to test the emergency power supply for the PORVs and block valves has been deleted.

With poth PORVs inoperable in Modes 1, 2, or 3 for reasons other than excessive seat leakage or both Block valves are inoperable, an allowed outage time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to restore 1 block valve or PORV to operable status has been requested.

The surveillance requirement to test the emergency power supply for the PORVs and block valves has not been incorporated into this amendment request because these valves receive power from safety-related, diesel-backed busses.

The operability of these busses is verified by surveillance requirements pertaining to electrical power systems (Technical Specification 3.8.1.1).

The Generic Letter 90-06 requirement to restore a Block valve or PORV to operable status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if both PORVs are determined to be inoperable for reasons other than excessive seat leakage or both block valves are inoperable has not been incorporated.

An Allowed Outage Time (AOT) of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months has been requested for these Limiting Conditions for Operation.

The basis for the increase for these AOTs from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is to enable sufficient time for containment entry to assess and implement, if possible, minor corrective actions to return inoperable PORV(s) or block valves to operable status.

The additional time requested would allow the correction of minor deficiencies, and therefore allow the plant to continue to operate without bringing the plant through a shutdown transient.

Plant shutdown under these action statements would result in the entry to a lower mode of operation which requires the PORVs to be operable to provide a Low Temperature Overpressure Protection (LTOP) function.

Soecification 3.4.9.3 CDPR-70, Unit 1) and 3.4.10.3 CDPR-75, Unit 2), "OVERPRESSURE PROTECTION SYSTEMS".

The changes that are proposed for specifications 3.4.9.3 (DPR-70, Unit 1) and 3.4.10.3 (DPR-75, Unit 2) are in response to the requirements delineated in GL 90-06, Enclosure B, pages B-6 and B-7 and justified on pages B-8 and B-9.

These requirements seek to instill improved administrative restrictions on the Low Temperature Overpressure Protection (LTOP) System thereby improving availability when the potential for an overpressure event is the highest and especially during water-solid conditions.

PAGE 5 OF 7 ATTACHMENT 1

itt_ 91-06 (Rev. 1)

NLR-N92156 Salem Units 1 and 2 currently have technical specifications pertaining to PORVs used for LTOP; therefore, the only changes that have been proposed for these sections are to restrict the applicability of Action a to Mode 4 and to incorporate Action b from the modified technical specifications delineated in GL 90-06, Enclosure B, pages B-6 and B-7.

This is in compliance with the instructions given on page B-8 of the GL.

One additional administrative change has been proposed for the Unit 1 technical specification.

The reference to the specific ASME valve category has been deleted from surveillance requirement 4.4.9.3.1 (DPR-70).

This type of information is contained in the In-Service Test Program and is not normally included in technical specifications.

Specification 3.5.3, "ECCS SUBSYSTEMS -

T ave < 350°F".

Changes are proposed for specification 3.5.3 in order to more clearly specify the applicability of Surveillance 4.5.3.1. and the note pertaining to the LCO.

The surveillance and note apply when: 1) the plant is in Mode 4 and any RCS cold leg temperature is less than or equal to 312°F (plant specific value), 2) Mode 5, and 3) Mode 6 when the head is on the reactor vessel.

Since this specification is applicable only in Mode 4, the guidance provided by the surveillance and note has been restated in specification 3.1.2.3, applicable in Modes 5 and 6, and specification 3.1.2.4, applicable in Modes 1, 2, 3, and 4.

As these changes do not delineate any new or differing guidance and are proposed for clarity only, they are considered administrative in nature.

IV.

Significant Hazards Consideration PSE&G has, pursuant to amendment to determine hazards consideration.

Salem Units 1 and 2 in 10 CFR 50.92, reviewed the proposed whether our request involves a significant We have determined that operation of accordance with the proposed change:

1.

Will not involve a significant increase in the probability or consequences of an accident or malfunction of equipment important to safety previously evaluated.

This change will instill administrative restrictions on the Low Temperature Overpressure Protection System and the PORVs thereby improving reliability and availability to respond to a Steam Generator Tube Rupture and overpressure transient.

The proposed amendment requires that power be maintained to block valves that are closed to isolate a leaking PORV.

This change ensures that the block valves can be opened on demand from the control room.

Power is maintained to the PAGE 6 OF 7 ATTACHMENT 1

LI. 91-06 (Rev. 1)

NLR-N92156 block valves so that it is operable and may be subsequently opened to allow the PORV to be used to control reactor pressure.

This change actually improves overall plant safety.

Therefore, the proposed amendment does not involve a procedural or physical change to any structure, system or component that significantly affects accident/malfunction probabilities or consequences previously evaluated in the UFSAR.

2.

Will not create the possibility of a new or different kind of accident from any previously evaluated.

The proposed amendment does not involve any physical changes to plant structures, components, or systems.

With the exception of maintaining power to a block valve closed to isolate a leaking PORV, which does not create the possibility of a new or different kind of accident, the proposed change will not impose any different requirements on plant operation.

Therefore, the proposed changes do not create the possibility of a new or different accident from any previously evaluated.

3.

Will not involve a significant reduction in a margin of safety.

The proposed changes actually increase the overall margin of safety by improving the availability and reliability of the PORVs and Block valves in response to Steam Generator Tube Rupture events, and the PORVs in response to overpressure transients.

v.

Conclusions Based on the above discussions and those presented in the Justification Section, it has been determined that the proposed Technical Specification revisions do not involve a significant increase in the probability or consequences of an accident over previous evaluations, create the possibility of a new or different kind of accident, or involve a significant reduction in a margin of safety.

Therefore, the requested license amendment does not involve a significant hazards consideration.

PAGE 7 OF 7 ATTACHMENT 1

ATTACHMENT 2 LCR 91-06 (Rev. 1)

NLR-N92156 REQUEST FOR LICENSE AMENDMENT INCORPORATION OF GENERIC LETTER 90-06 REQUIREMENTS SALEM GENERATING STATION UNITS 1 AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311

e LCR 91-06 (Rev. 1)

NLR-N92156 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES The following Technical Specifications are affected by this requested amendment:

Facility Operating License No. DPR-70 (Unit Technical Specification Page 3.1.2.3 3/4.1-10 3.1.2.4 3/4 1-11 3/4.4.3 3/4 4-5 3.4.9.3 3/4 4-30 3/4 4-31 3.5.3 3/4 5-6 3/4 5-6a Facility Operating License No. DPR-75 (Unit Technical Specification Page 3.1.2.3 3/4 1-9 3.1.2.4 3/4 1-10 3/4.4.5 3/4 4-8 3.4.10.3 3/4 4-31 3.5.3 3/4 5-7 3/4 5-8 ATTACHMENT 2

1)

2)

'-* ~J

-.1;.

REACTIVITY CONTROL SYSTEMS CHARGING ?UMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2".3 At least one charging pump in the boron injection flow path required by Specification 3.l.2.1 shall be OPERABLE.:i,e.

APPLICABILITY:

MODES 5 and 6*.

ACTION:

With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until one charging pwnp fs restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS ALEM - UNIT 1 3/4 1-10

/

LCR 91-06 (Rev. 1)

NLR-N92156 Insert A for page 3/4 1-10 4.1.2.3 In addition to the requirements of Specification 4.0.5, all safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to be inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while in MODE 5 or MODE 6 and the head is on the reactor vessel by either of the following methods:

a.

By verifying that the motor circuit breakers have been removed from their electrical power supply circuits, or

b.

For testing purposes, by verifying that the pump is in a recirculation flow path and that the manual discharge valve is closed.

Insert B for page 3/4 1-10

A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE while in MODE 5 or MODE 6 and the head is on the reactor vessel.

ATTACHMENT 2

(

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pu~s shall be OPERABLE.#=

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only one charging pu~ OPERABLE, resto*re at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months *or bt in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1: Qk/k at 200°F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two-charging pumps to OPERABLE.

status within the next 7 days *or bt in COLO SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE IREMENTS ALEM - UNIT 1 3/4 1-11

e LCR 91-06 (Rev. 1)

NLR-N92156 Insert A for page 3/4 1-11 All safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to be inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 312*F by either of the following methods:

a.

By verifying that the motor circuit breakers have been removed from their electrical power supply circuits, or

b.

For testing purposes, by verifying that the pump is in a recirculation flow path and that the manual discharge valve is closed.

Insert B for page 3/4 1-11

A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE in MODE 4 when the temperature of one or more of the RCS cold legs is less than or equal to 312°F.

ATTACHMENT 2

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11 of full vet.

Alllndmnt No. 39

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Insert A for page 3/4 4-5:

A. 91-06 (Rev. 1)

NLR-N92156

a.

With one or both PORVs inoperable because of excessive seat leakage, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s); otherwise, 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 and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one PORV inoperable due to causes other than excessive seat leakage, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With both PORVs inoperable due to causes other than excessive seat leakage, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either restore at least one PORV to OPERABLE status or close the associated block valves and remove power from the block valves and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

With. one block valve inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valve to OPERABLE status or place the associated PORV in manual control; restore the block valve 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 and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e.

With both block vaives inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valves to OPERABLE status or place the associated PORVs in manual control; restore at least one block valve to OPERABLE status within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

f.

The provisions of Specification 3.0.4 are not applicable.

ATTACHMENT 2

e LCR 91-06 (Rev. 1)

NLR-N92156 Insert B for page 3/4 4-5:

4.4.3.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:

a.

Operating the PORV through one complete cycle of full travel during MODES 3 or 4, and

b.

Operating solenoid valves, air control valves, and check valves on associated air accumulators in PORV control systems through one complete cycle of full travel, and

c.

Performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.3.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, or c in Specification 3.4.3.

ATTACHMENT 2

1'*

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At 111st one of the following over~ressure orotection syst!ms shall be OPERABL~:

a.

Two Pressurizer Overiiressure Protection Syst1m relief vahes (POPs) with a lift sitting of less tl'lan or equal to 375 psi;, er

b.

A reactor coolant system vent of greater than or eaual to 3.1~.

square inches.

of APPLICABILITY:

When tha temc:ieratYre of one or more\\.'the ~CS cold legs ~s less than or equal to 312°F, except when tn1 rea.ctor vessel head is l

iti "'10DE I/ on4 ~ho f.,..l",..-h,,._ of ont or tnor< oj ~

removed.

ACT!ON:

~ t,,1dv9s is 'u" ~

ot e""o..l h, 31Z 0 ~

I With one POPs inoperab1, tither restore the inoperable ?O~s ~~

OPERABLE status within 7 days or d1p~ssurize and vent the ~~s through a 3. 14 square inch vent(s) within the next e nours; maintain the RCS in a vented condition until both POPs nave be~r:

a.

restol"ld to OPERABLE status.

(

With both POPs inoperable, depressurize and vent.the ~cs thr~u;!'I a 3.14 square inch vent(s) within S hours; maintain the ~cs ir. a v1nted condi tin unti 1 both POPs have been restored to OPE~.:.5L:'.

status.

In th1 event either the POPs or the RCS vent(s) are use~ ~~

mitigate a RCS pressure trans11nt, a Special Report sha11 :e prepared and submitted to the Colllftission pursuant to Sceci~-

1cat1on 6.9.2 within 30 days. ih1 report shall deser~:! t~!

cfrcU1111tanc1s initiating th1 transient, the effect of t~e ~a~s ~~ 1-v1nt(s) on the transient and any corrective act1o~ ne:essary ::

1 pr1v1nt recurT'tnce.

I The provisions of Specification 3.0.4 are not app1icabie.

SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each POPS shall be demonstrated OPE~.ASLE by:

SALEM

UN IT 1 3/4 4-30 Amendment ~o. 2'

-'\\

L

~

91-06 (Rev. 1)

NLR-N92156 Insert A for page 3/4 4-30

b.

With one POPS inoperable in MODES 5 or 6 with the Reactor Vessel Head installed, restore the inoperable POPs to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or complete depressurization and venting of the RCS through at least a 3.14 square inch vent(s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented condition until both POPs have been restored to OPERABLE status.

ATTACHMENT 2

REACTOR COOLANT SY.STEM SURVEILLANCE REQUIREMENTS (Continued)

a.

Perf'onnance of a CHANNEL FUNCTIONAL TEST on the POPS actuation channel, but excluding valve oper'!tion, within 31 days prior to enteP1ng a condition fn which the POPS fs required OPERABLE. _

b.

Per1'onnanc1 of a CHANNEL CALIBRATION on the POPS actuation -

channel at least once per 18 months.

c.

Verifying the POPS f solation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the POPS f s bein~ usld for ov1rprtssure P1"0t1Ction.

P""'s"a...,+

to 5per:../::cQ.f1"D"1

'l*O.$.

d.

Testing ift aeeal'taAee wiih the iR11rvi;1 t11t reqwf 1!'4R11Rt1 f~

'A5ME Sa*egel')' ' v11v1s PW"4WIRi u Spec11'1GU1oR 4.Q.Sp"'"'

4.4~9.3.2 The RCS vent(s) shall be verified ~o be open at least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s* when the vents ( s) fs being used for. *overprtssure protection.

1Eicept when the vent pathway f s providtd with a valvt which fs locked, staled, or oth1n1is1 secured fn th* open position, then verify these valves open at least once per 31 days.

SALEM ~ UNIT 1 3/4 4-31 Amendment No. 24

EMU.GA CORE COOL!~G SYS!E2'!S

!CCS SUBSYST!HS

T

<J50°F LIMITING CONDITION FOR OPERATION 3.S.3 As a minimum, one ECCS subsyst~omprised of the following shall be OP!RABL!:

a.

-On* OP!RABL! cantrifu1al charging pump~nd associatad flov path capable of taking suction from the rafualin1 watar stora1* tank and transfarrin1 suction to the rasidual heat ramoval pump discharge pipin1 and;

l.

Uischargin1 into aach Raactor Coolant System tRCS) cold leg.

b.

One OPERABLE residual heat removal pump and associatad residual heat removal heat axchan1er and flow path capable of taking suction from the rafuelin1 watar stora1* tank on *- safaty injection signal and transf arrin1 suction to the containment sump durin1 th*

racirculation phase of operation and;

l.

Oischar1in1 into each RCS cold l*1, and; upon manual initiation,

2.

Dischar1in1 into tvo RCS hot l*I**

APPLICABILITY.:

MOD! 4.

ACTION:

a.

b.

c:*.

With no ECCS subsystea OP!RABL! because of th* inoperability of either the cantrifu1al char1in1 pump or the flov path from th*

refuelin1 water storage tank, restore at least one ECCS subsystem to OPERABLE statu. within l hour or be in COLD Sll\\JTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

Within no !CCS subsyst.. OP!RABL! becau.e of the inoperability of either th* residual heat removal heat exchan1*r or residual haat removal pump, restore at i... t one !CCS subsyst.. to OP!RABLE status or maintain the Reactor Coolant Syst.. T lass than 350*1 by use of altemat* hut nmoval mthod9.

avs lll"thrcomt ta KG i* Ktw.6* anct-inj<<ts vat*!' into. th&- Reactor Cool.Mt Sy.t*, a Special Raport shall be prepared and submitted to the C~ssion pursuant to Specification 6.9.2 within 90 days da8cribin1 th* circumstances of the actuation and th* total accumalated actuation cycle* to date.

n1 pump SALEK

UNIT l 3/4 5*6 Amendment No. 94

Insert A for page 3/4 5-6 L~R 91-06 (Rev. 1)

NLR-N92156

A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE in MODE 4 when the temperature of one or more of the RCS cold legs is less than or equal to 312°F, Mode 5, or Mode 6 when the head is on the reactor vessel.

ATTACHMENT 2

' 1 EMERGENCY CORE COOLING SYSTEMS ECCS SYISYSTEMS

Tavg < 3SO*F SURYEILL.ANCE RE(UIREMEHTS 4.5.3.l The ECCS subsyst1111 shall bl d11anstr1tld OPERABLE per app11cablt Surv11111nc1 Requ1r11111nts of 4.S.2.

1. By verifying th1t th* nator circuit br'11kers *have been r111avld fro* their 1lec:tric1l power supply circuits or,

b. For testing purposes, by verifying thlt the pU8' is in 1 reci rculit1on flaw path ;nd that ttlt *nual d1scb1rg1 YA1wt ts closed.

SALEM

UN IT 1 3/4 s-ea Amtncm.nt No. 66

Insert A for page 3/4 5-6a

.. 91-06 (Rev. 1)

NLR-N92156 4.5.3.2 All safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to be inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 312*F, MODE 5, or MODE 6 when the head is on the reactor vessel by either of the following methods:

ATTACHMENT 2

' r REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION

3. 1.2.3 At least one charging pump 1n the boron injection flow path required by Specification 3. 1.2. l shall be OPERABLE.;f#:

APPLICABILITY:

MODES 5 and 6.

ACTION:

With no charging PUllP OPERABLE, suspend all operations involving CORE ALTERA-TIONS or positive reactivity changes until one charging pump is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS SALEM

UNIT 2

. 3/4 1-9

Insert A for page 3/4 1-9 A. 91-06 (Rev. 1)

NLR-N92156 4.1.2.3 In addition to the requirements of Specification 4.0.5, all safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to be inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while in MODE 5 or MODE 6 and the head is on the reactor vessel by either of the following methods:

a.

By verifying that the motor circuit breakers have been removed from their electrical power supply circuits, or

b.

For testing purposes, by verifying that the pump is in a recirculation flow path and that the manual discharge valve is closed.

Insert B for page 3/4 1-9

A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE while in MODE 5 or MODE 6 and the head is on the reactor vessel.

ATTACHMENT 2

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION

3. 1.2.4 At least two charging PUllPS shall be OPERASLE..ff' APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only one charging pump OPERABLE, restore at least two charging PUllPS 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 and borated to a SHUTDOWN MARGIN equivalent to at least 11 delta k/k at 200°F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging Pu.QI to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

se requ1re y

SALEM - UNIT 2 3/4 1-10

Insert A for page 3/4 1-10 A. 91-06 (Rev. 1)

NLR-N92156 All safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to be inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 312*F by either of the following methods:

a.

By verifying that the motor circuit breakers have been removed from their electrical power supply circuits, or

b.

For testing purposes, by verifying that the pump is in a recirculation flow path and that the manual discharge valve is closed.

Insert B for page 3/4 1-10

A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE in MODE 4 when the temperature of one or more of the RCS cold legs is less than or equal to 312°F.

ATTACHMENT 2

I REACTOR COOLANT SYSTEM 3/4.4.5 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.5 Two power relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

SURVEILLANCE REQUIREMENTS SALEM - UNIT 2 3/4 4-8

(.

Insert A for page 3/4 4-8:

'R 91-06 (Rev. 1)

NLR-N92156

a.

With one or both PORVs inoperable because of excessive seat leakage, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s); otherwise, 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 and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one PORV inoperable due to causes other than excessive seat leakage, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

.With both PORVs inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore at least one PORV to OPERABLE status or close the associated block valves and remove power from the block v~lves and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

With one block valve inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valve to OPERABLE status or place the associated PORV in manual.control; restore the block valve 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 and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e.

With both block valves inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valves to OPERABLE status or place the associated PORVs in manual control; restore at least one block valve to OPERABLE status within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

f.

The provisions of Specification 3.0.4 are not applicable.

ATTACHMENT 2

e LCR 91-06 (Rev. 1)

NLR-N92156 Insert B for page 3/4 4-8:

4.4.5.l In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:

a.

Operating the PORV through one complete cycle of full travel during MODES 3 or 4, and

b.

Operating solenoid valves, air control valves, and check valves on associated air accumulators in PORV control systems through one complete cycle of full travel, and

c.

Performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.5.2

Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, or c in Specification 3.4.5.

ATTACHMENT 2

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITIOM FOR OPERATION 3.4.10.3 At least one of the following overpressure protection systems shall be OPERABLE:

a.

Two Pressurizer Overpressure Protection System relief valves (POPSs) with a lift setting of less than or equal to 375 psig, or

b.

The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 3. 14 square inches.

APPLICABILITY:

When the temperature of one or more of *the RCS cold legs is less than or equal to 312°F, except when the reactor vessel head is removed.

ACTION:

hlollE L/ 0ind. the. +~f'tra:lvr~ J' o1\\t ""mor& o-e &. Pcs Ill eukt ~f i..s I~ *""°' or eCf111LI +o 3 IZ 0 r

+ A \\fe~

a.

With one POPS i noperabl.Y, restore the ir,operable POPS to OPERABLE

'!rt-\\e' -}'+-"

status within 7 days or depressurize and vent the RCS through a I

3. 14 square i n~h vent(s; within the next a* hours,,;,,,,.,..,.,_,,..., 1'1f! lfcs,*.,

f./11..

)"

"'., *.,-1-~ ~ *.,J,*f;u.., 14.,~.* '""" """' lt,...w "9*** ~*S-1-o,.r::d f* oY'e~~dl.E' shic.~s

c )L With both POPSs inoperable, depressurize and vent the RCS through a J

~'

3. 14 square inch vent(s) within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ,.; m,.,.,.f,.,*., t'tff iecc,*., "-

o1e..,1eo co..,J,'f-1'1.,.. ~;:1 "-141 ~~ hesve w.~ ~,,"".Jo~,.J

<Jo.*

O~E~""'dl. s:J'<J..,s.

cl.t'.

In the event either the POPSs or the RCS vent(s) are used to mitigate a RCS pressure transient, a Special Report shall be prepared and subllitted to the C011111ission pursuant to Specification 6.9.2 within 30 days.

The report shall describe the circU11stances initiating the.

transient, the effect of the POPSs or vent(s) on the transient and any corrective action necessary to prevent recurrence.

e,I.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMEHTS 4.4.10.3. 1 Each POPS* shall be demonstrahd OPERABLE by:

SALEM - UNIT 2 3/4 4-31

Po-----------------------------------------**---*- ------

e LCR 91-06 (Rev. 1)

NLR-N92156 Insert A for page 3/4 4-31

b.

With one POPs inoperable in MODES 5 or 6 with the Reactor Vessel Head installed, restore the inoperable POPs to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or complete depressurization and venting of the RCS through at least a 3.14 square inch vent(s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in. a vented condition until both POPs have been restored to OPERABLE status.

ATTACHMENT 2

==-~ERGE..\\iC( C8RE

ccr..:~G 3'(57~5 ECCS SUl~'EHS - T

<350"F aog LIMITING CONDITION FOR OPERATION 3.5.3 As a mini.mum. one ECCS subsyst~omprised of the following shall be OPERABLE:

~

a.

One OPERABLE centrifugal charging pump\\,(nd associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and;

l.

Discharging into each Reactor Coolant System (RCS) cold leg.

b.

One OPERABLE residual heat removal pump and associated residual heac:

removal heat exchanger and flow path c~pAble of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump durin1 the recirculation phase of operation and;

1.

Discharging into each RCS cold leg, and; upon manual initiation.

2.

Disch~~sin1 into two RCS hot l*1s.

APPLICAB~LITY: MOD! 4.

ACTION:

a.

With no !CCS 9ubsystam OPERABLE because of the inoperability of either the centrifugal char1in1 pump or the flow path from the rafuelin1 water storage tank, restore at least one ECCS subsystem c:o OPERABLE status within l hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months *.

b.

With no !CCS subsystem OPERABLE because of the inoperability of either the re*idu.l heat removal heat exchanger or residu.l heat ramoval pump, restore at least one !CCS subsystem to OPERABLE status or maintain the Reactor Coolant Systaa Tavi less than Jso*r by use of alternate heat ramoval methods.

c.

IA tba.999ftt tha ECCS"is actuated and injects vat~ into the R*actor Coolant Syat... a Special Report shall be prepared and submitted to tha ec..:ls*ion pursu.nt to Specification 6.9.2 within 90 days descrtbtn1 the circumstances of the actuation and the total accumalat9d actuation cycles to date.

'l'b9 curnat valua ot the usa1e factor for each affected safety-injectian. nozzle shall be provided in this Special Report vb9nev.r its value exceeds 0.70.

SALEH - UNIT 2 3/4 5-7 Amendment No. 70

~

.J.'.J lJ

_l'I

.4.

91-06 (Rev. 1)

NLR-N92156 Insert A for page 3/4 5-7

A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE in MODE 4 when the temperature of one or more of the RCS cold legs is less than or equal to 312°F, Mode 5, or Mode 6 when the head is on the reactor vessel.

ATTACHMENT 2

-~"'

EMERGENCY ~E COOLING SYSTEMS ECCS SUBSYSTEMS

T1vg < 350-F SURVEILLANCE REOJIREMENTS 4.S.3.1 Thi ECCS subsysttt11 shall be d1aanstr1tld. OPERABLE per applicable Surve1111nc1 Requireinents of 4.S.2.

~a~ ~

.~

4.5.3.Z All s ety 1nject1on

~s. except th OPERABLE pu~

t-e(,~ ~""\\.t allowed abov, shall bl dem trltld 1nop1r1 e 1t l1ast one

'1 p1r 12 ho whenever the er1tur1 of o or 11are of t CS

~11'>t1.

cold 11 1s less than o eq~;l to 312.,

iy th@ followin *

~(/ ~

1. By verifying that the aator circuit br1u1rs have been r11Dvld fro* th11r 1l1etrical power suppl1 c1rcutts or,

b. For t11t1ng purposes, by ver1fytnt that the 'pu9' ts fn a reef rcul1tion f1ow path and that the *._.al discharge valve* ts closed.

SALEM

UNIT 2 3/4 s-a Amendment No. 41

f' I

Insert A for page 3/4 5-8 I,ip.R 91-06 (Rev. 1)

NLR-N92156 4.5.3.2 All safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to be inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 312*F, MODE 5, or MODE 6 when the head is on the reactor vessel by either of the following methods:

ATTACHMENT 2

ML18096B111

Text

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