ML071780293

License Amendment Request, Proposed Changes to Accident Monitoring Instrumentation Technical Specifications

ML071780293
Person / Time
Site:	Limerick
Issue date:	06/27/2007
From:	Cowan P Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML071780293 (16)

Text

Exelon Nuclear www.exe1oncorp.com 200 Exelon Way Nuclear Kennett Square, PA 19348 10 CFR 50.90 June 27,2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos.

NPF-39 and NPF-85 NRC Docket No.ciancL50-353

SUBJECT:

License Amendment Request Proposed Changes to Accident Monitoring Instrumentation Technical Specifications Pursuant to 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (Exelon), proposes changes to the Technical Specifications (TS), Appendix A of Operating License Nos. NPF-39 and NPF-85 for Limerick Generating Station (LGS), Units 1 and 2, respectively. The proposed changes relocate the operability and surveillance requirements for the drywell air temperature and suppression chamber air temperature instrumentation from LGS TS Section 3.3.7.5, "Accident Monitoring Instrumentation," to the LGS Technical Requirements Manual (TRM). The proposed changes conform to 10 CFR 50.36 for the contents of TS, and to the improved Standard Technical Specifications approved by the NRC in NUREG-1433, "Standard Technical Specifications - General Electric Plants, BWRI4." A similar change, to relocate the operability and surveillance requirements for the safetyhelief valve position indication instrumentation from TS Section 3.3.7.5 to the TRM, was approved by the NRC by issuance of Amendment Nos.

179 and 141 for LGS, Units 1 and 2, respectively, by letter dated September 27, 2005.

Exelon has concluded that the proposed changes present no significant hazards consideration under the standards set forth in 1 OCFR 50.92. This amendment request contains no regulatory commitments.

Exelon requests approval of the proposed amendment by June 27,2008. Upon NRC approval, the amendment shall be implemented within 60 days of issuance. These proposed changes have been reviewed by the Plant Operations Review Committee.

License Amendment Request Changes to Accident Monitoring Instrumentation Docket Nos. 50-352 and 50-353 June 27,2007 Page 2 We are notifying the State of Pennsylvania of this application for changes to the Technical Specifications by transmitting a copy of this letter and its attachments to the designated State Official.

If you have any questions or require additional information, please contact Glenn Stewart at 61 0-765-5529.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 27th day of June, 2007.

Respectfully, Pamela B. &wan Director - Licensing

& Regulatory Affairs Exelon Generation Company, LLC Attachments:

1. Evaluation of Proposed Changes

2. Markup of Proposed Technical Specifications Pages cc: Regional Administrator - NRC Region I W/ attachments NRC Senior Resident Inspector - Limerick Generating Station I1 NRC Project Manager, NRR - Limerick Generating Station 11 Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Protection I1 ATTACHMENT 1 License Amendment Request Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 and 50-353 EVALUATION OF PROPOSED CHANGES

Subject:

Proposed Changes to Acci dent Monitoring Instrumentation Technical Specifications

2.0 PROPOSED CHANGE

S

7.0 REFERENCES

License Amendment Request Attachment 1 Changes to Accident Monitoring Instrumentation Page 1 of 8

Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

1.0 DESCRIPTION

Pursuant to 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon

Generation Company, LLC (Exelon), proposes changes to the Technical Specifications (TS),

Appendix A of Operating License Nos. NPF-39 and NPF-85 for Limerick Generating Station (LGS), Units 1 and 2, respectively.

The proposed changes relocate the operability and surveillance requirements for the drywell air

temperature and suppression chamber air temper ature instrumentation from the Accident Monitoring Instrumentation section of TS, i.e., from LGS TS 3.3.7.5 and 4.3.7.5 to the LGS

Technical Requirements Manual (TRM). The TRM is incorporated by reference into the LGS Updated Final Safety Analysis Report (UFSAR) and is subject to the controls of 10 CFR 50.59.

Accordingly, any future changes to the drywell air temperature and suppression chamber air

temperature instrumentation operability and surveillance requirements will be performed pursuant to 10 CFR 50.59.

The proposed changes conform to 10 CFR 50.36 (Reference 1) for the contents of TS, and to

the improved Standard Technical Specifications approved by the NRC in NUREG-1433, "Standard Technical Specifications - General Electric Plants, BWR/4" (Reference 2). A similar

change, to relocate the operability and surveillance requirements for the safety/relief valve

position indication instrumentation from TS Section 3.3.7.5 to the TRM, was approved by the

NRC by issuance of Amendment Nos. 179 and 141 for LGS, Units 1 and 2, respectively (Reference 3).

2.0 PROPOSED CHANGE

S The changes requested by this amendment application are described below.

1. Delete Item 5, "Suppression Chamber Air Temperature," from TS Table 3.3.7.5-1, "Accident Monitoring Instrumentation," on TS page 3/4 3-85. This table identifies the operability

requirements for this instrumentation.

2. Delete Item 7, "Drywell Air Temperature," from TS Table 3.3.7.5-1, "Accident Monitoring Instrumentation," on TS page 3/4 3-85. This table identifies the operability requirements for

this instrumentation.

3. Delete Item 5, "Suppression Chamber Air Temperature," from TS Table 4.3.7.5-1, "Accident Monitoring Instrumentation Surveillance Requirements," on TS page 3/4 3-87. This table

identifies the surveillance requirements for this instrumentation, i.e., a channel check and

channel calibration are specified. The frequency for performing these surveillance

requirements is specified in the LGS Surve illance Frequency Control Program (SFCP), which will also be revised to delete the associated surveillance frequencies from the SFCP upon

implementation of the approved amendment.

The surveillance requirements from TS and the frequency for performing the surveillance requirements from the SFCP will be relocated

to the LGS TRM.

License Amendment Request Attachment 1 Changes to Accident Monitoring Instrumentation Page 2 of 8

Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

4. Delete Item 7, "Drywell Air Temperature," from TS Table 4.3.7.5-1, "Accident Monitoring Instrumentation Surveillance Requirements," on TS page 3/4 3-87. This table identifies the

surveillance requirements for this instrumentation, i.e., a channel check and channel

calibration are specified. The frequency for performing these surveillance requirements is

specified in the LGS SFCP, which will also be revised to delete the associated surveillance

frequencies from the SFCP upon implement ation of the approved amendment. The surveillance requirements from TS and t he frequency for performing the surveillance requirements from the SFCP will be relocated to the LGS TRM.

Prior to implementation of the amendment, oper ability and surveillance requirements for the drywell air temperature and suppression chamber air temperature instrumentation will be incorporated into the LGS TRM. The operability requirements will identify compensatory

measures and completion times for these instruments. Any subsequent changes to the TRM

requirements will be performed in accordance with 10 CFR 50.59.

There are no changes to the TS Bases section proposed by this amendment application since

the drywell air temperature and suppression cham ber air temperature instrumentation is not specifically identified in the TS Bases.

3.0 BACKGROUND

The NRC provided guidance for the contents of TS in its "Final Policy Statement on Technical

Specifications Improvements for Nuclear Po wer Reactors" (58 FR 39132, July 22, 1993; Reference 4). In particular, the NRC indicated that certain items could be relocated from the TS

to licensee-controlled documents. The Final Policy Statement identified future criteria to be used

in determining whether particular safety functions are required to be included in the TS, as

follows: (1) installed instrumentation that is used to detect, and indicate in the control room, a

significant abnormal degradation of the reactor coolant pressure boundary; (2) a process

variable, design feature, or operating restriction that is an initial condition of a Design Basis

Accident or Transient analysis that either assumes the failure of, or presents a challenge to the

integrity of a fission product barrier; (3) a structure, system, or component that is part of the

primary success path and which functions or actuates to mitigate a Design Basis Accident or

Transient that either assumes the failure of, or presents a challenge to the integrity of a fission

product barrier; (4) a structure, system, or component which operating experience or

probabilistic safety assessment has shown to be significant to public health and safety. The

NRC adopted amendments to 10 CFR 50.36 (60 FR 36953, July 19, 1995; Reference 5) to

codify and incorporate these criteria.

The NRC's policy statement provides that those existing TS requirements which do not satisfy

these four specified criteria may be relocated to licensee-controlled documents, such that future

changes could be made to these provisions pursuant to 10 CFR 50.59. Subsequently, the

nuclear steam supply system owners' gr oups and the NRC staff developed improved standard technical specifications (STS) that would establish models of the Commission's policy for each

primary reactor type. The NRC issued the improved STS for General Electric BWR/4 plants as

NUREG-1433, which was developed utilizing the guidance and criteria in the Commission's

policy statement.

License Amendment Request Attachment 1 Changes to Accident Monitoring Instrumentation Page 3 of 8

Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

4.0 TECHNICAL ANALYSIS

The proposed license amendment relocates the drywell air temperature and suppression

chamber air temperature instrumentation operab ility and surveillance requirements from the LGS TS to the LGS TRM. The TRM is referenced in the LGS UFSAR and is subject to the controls of

10 CFR 50.59. The TRM has been used to capture and control other requirements associated

with previous LGS license amendments.

As discussed in the Background section above, an NRC policy statement concluded that those

existing TS requirements which do not satisfy the screening criteria specified in 10 CFR 50.36

may be deleted from the TS, and the requirements established in licensee-controlled documents

that are subject to the controls of 10 CFR 50.59. The NRC position on application of the

screening criteria to accident monitoring instrumentation is documented in correspondence

dated May 9, 1988, T. E. Murley (NRC) to R. F. Janecek (BWR Owners' Group) (Reference 6).

The NRC position is that Regulatory Guide 1.97 (Reference 7), Type A, and Category 1, accident monitoring instrumentation should be incorporated into the plant's TS. The

requirements for those instruments not meeting these criteria may be removed from the TS and established in a licensee-controlled document subject to the controls of 10 CFR 50.59.

Regulatory Guide 1.97, Revision 2, defines Type A instruments as those that monitor primary

information required to permit the control room operator to take specific manually controlled

actions for which no automatic control is provi ded and that are required for safety systems to accomplish their safety functions for design basis accident events. Category 1 instruments are

designed for full qualification, redundancy, continuous real-time display, and onsite (standby)

power.

Regulatory Guide 1.97, Revision 2, designates drywell air temperature instrumentation as Type

D, Category 2, instrumentation. Type D instruments provide information to indicate the operation

of individual safety systems and other systems im portant to safety. Category 2 instruments are designed to less stringent qualifications that do not require seismic qualification, redundancy, or

continuous display, and require only a high reliability power source (not necessarily standby

power). From a plant-specific perspective, LGS UFSAR Section 7.5 and UFSAR Table 7.5-3

also identify the drywell air temperature instrumentation as Type D, Category 2. Relocating

drywell air temperature instrumentation from t he TS to a licensee-controlled document conforms with this NRC position on application of the screening criteria to accident monitoring

instrumentation.

Regulatory Guide 1.97, Revision 2, does not include suppression chamber air temperature as an

accident monitoring variable. Likewise, the LGS UFSAR does not specifically identify

suppression chamber air temperature by itself as a Regulatory Guide 1.97 variable. However, LGS UFSAR Section 7.5 does describe the use of suppression chamber air temperature for

monitoring the effectiveness of suppression chamber spray flow (a Type D, Category 2 variable).

Relocating suppression chamber air temperatur e instrumentation from the TS to a licensee-controlled document conforms with this NRC position on application of the screening criteria to

accident monitoring instrumentation.

License Amendment Request Attachment 1 Changes to Accident Monitoring Instrumentation Page 4 of 8

Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

NUREG-1433 identifies improved TS that were developed based on the screening criteria in the "Final Commission Policy Statement on Technical Specifications Improvement for Nuclear Power

Reactors," that were subsequently codified in 10 CFR 50.36. According to NUREG-1433, accident monitoring instrumentation that satisfies the definition of Type A in Regulatory Guide

1.97 meets Criterion 3 of 10 CFR 50.36(c)(2)(ii). Also, Category I, non-Type A instrumentation is

retained in TS because they are intended to assist operators in minimizing the consequences of

accidents. Therefore, Category I, non-Type A variables are important for reducing public risk.

However, as stated previously, the LGS UFSAR indicates that the drywell air temperature

instrumentation is Type D, Category 2 and suppression chamber air temperature is used for

monitoring the effectiveness of suppression chamber spray flow (a Type D, Category 2 variable).

An assessment of the subject accident monitoring instrumentation against the four criterion of 10

CFR 50.36 is provided below.

Criterion 1: The drywell air temperature and suppression chamber air temperature

instrumentation does not provide the primary information used to detect or indicate a significant

abnormal degradation of the reactor coolant pressure boundary considered by Criterion 1. This

is consistent with the Commission's Final Policy Statement which indicated that the first criterion

was intended to assure that TS controlled those instruments specifically installed to detect

reactor coolant leakage.

Criterion 2: The Commission's Final Policy Statement indicates that the basic concept in

adequate protection of the public health and safety is that the plant be operated within the

bounds of the initial conditions assumed in the existing design basis accident and transient

analyses, and that the plant will be operated to preclude unanalyzed transients and accidents.

Therefore, Criterion 2 applies to process variables that are parameters for which specific values

or ranges of values have been chosen as reference bounds in the design basis accident or

transient analyses, and which are monitored and controlled during normal power operation such

that process values remain within the analysis bounds. According to Regulatory Guide 1.97, Revision 2, accident monitoring instrumentation is provided to monitor plant variables and

systems during and following design basis accidents or transients. Therefore, Criterion 2 does

not apply to accident monitoring instrumentation since accident monitoring instrumentation

provides indication of plant variables required by operators during accident conditions to take

preplanned manual actions to accomplish safety functions rather than instrumentation that

provides indication of process variables that are monitored and controlled by operators during

normal plant operations to ensure that the initial conditions for accident analyses are met. As

such, the drywell air temperature and suppressi on chamber air temperature instrumentation does not provide the primary information used to monitor process variables, design features or

operating restrictions that are an initial condition of a design basis accident or transient analysis

considered in Criterion 2.

Criterion 3: Drywell air temperature and suppre ssion chamber air temperature instrumentation does not initiate any automatic safety function. Drywell air temperature and suppression

chamber air temperature instrumentation is not used as the primary information required to permit operators to take specific manually controlled actions for which no automatic control is

provided, and that are required for safety systems to accomplish their safety functions for design License Amendment Request Attachment 1 Changes to Accident Monitoring Instrumentation Page 5 of 8

Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

basis accident events. The drywell air temperature indication does indicate the performance of safety systems and other systems important to safety. As such, the drywell air temperature instrumentation is considered Type D, Category 2 (refer to Table 7.5-3 of the LGS UFSAR).

Suppression chamber air temperature is used fo r monitoring the effectiveness of suppression chamber spray flow (a Type D, Category 2 variable). Hence, drywell air temperature and

suppression chamber air temperature instrument ation is not part of the primary success path used to mitigate a design basis accident or transient involving a failure of or challenge to the

integrity of a fission product barrier considered in Criterion 3.

Criterion 4: The loss of the subject accident monitoring instrumentation has negligible effect on

the probabilistic safety assessment, and has not been shown to be significant to public health

and safety as considered in Criterion 4.

Consequently, the drywell air temperature and suppression chamber air temperature instrumentation does not meet any of the screening criteria contained in the Commission's Final

Policy Statement and 10 CFR 50.36. This conclusion is supported by the NRC screening criteria

for accident monitoring instrumentation required to be in TS as documented in Reference 6 and

NUREG-1433 which indicate that only Regulatory Guide 1.97, Type A and Category 1, non-Type

A instrumentation as defined by plant-specific analyses are required to be listed in the Accident

Monitoring Instrumentation section of TS. As indicated previously, LGS UFSAR Section 7.5 designates the drywell air temperature and suppression chamber air temperature

instrumentation as other than Type A or Category 1, non-Type A instrumentation. Accordingly, the drywell air temperature and suppression chamber air temperature instrumentation requirements can be established in a licensee-controlled document. Future changes to drywell

air temperature and suppression chamber air tem perature instrumentation requirements will be subject to the controls of 10 CFR 50.59.

5.0 REGULATORY ANALYSIS

5.1 No Significant Hazards Consideration Exelon has evaluated whether or not a significant hazards consideration is involved with

the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No. The failure of the drywell air temperature or suppression

chamber air temperature instrumentation is not assumed to be an initiator of any analyzed event in the UFSAR. The proposed changes do not alter the physical

design of this instrumentation or any ot her plant structure, system, or component.

The proposed changes relocate the drywell air temperature and suppression

chamber air temperature instrumentation operability and surveillance

requirements from the Limerick Generating Station (LGS) Technical License Amendment Request Attachment 1 Changes to Accident Monitoring Instrumentation Page 6 of 8

Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

Specifications (TS) to a licensee-controlled document under the control of 10 CFR 50.59.

The proposed changes conform to NRC regulatory requirements regarding the

content of plant TS as identified in 10 CFR 50.36, and also the guidance as

approved by the NRC in NUREG-1433, "Standard Technical Specifications-

General Electric Plants, BWR/4."

Therefore, the proposed changes do not involve a significant increase in the

probability or consequences of an accident previously evaluated.

2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No. The proposed changes relocate the drywell air temperature and

suppression chamber air temperature instrumentation operability and

surveillance requirements from the LG S TS to a licensee-controlled document under the control of 10 CFR 50.59.

The proposed changes do not alter the physical design, safety limits, or safety analysis assumptions associated with the

operation of the plant. Accordingly, the proposed changes do not introduce any

new accident initiators, nor do they reduce or adversely affect the capabilities of

any plant structure, system, or component in the performance of their safety function.

Therefore, the proposed changes do not create the possibility of a new or

different kind of accident from any accident previously evaluated.

3. Do the proposed changes involve a significant reduction in a margin of safety? Response: No. The subject instrumentation does not provide primary information

required to permit operators to take specific manually controlled actions for which

no automatic control is provided, and that are required for safety systems to accomplish their safety functions for design basis accident events. The

instrumentation provides only drywell air temperature indication and suppression

chamber air temperature indication, and does not provide an input to any

automatic safety function. Operab ility and surveillance requirements will be established in a licensee-controlled document to ensure the reliability of drywell

air temperature and suppression chamber air temperature instrumentation

capability. Changes to these requirements will be subject to the controls of 10

CFR 50.59, providing the appropriate level of regulatory control.

Therefore, the proposed changes do not involve a significant reduction in a

margin of safety.

License Amendment Request Attachment 1 Changes to Accident Monitoring Instrumentation Page 7 of 8

Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

Based on the above, Exelon concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

5.2 Applicable Regulatory Requirements/Criteria The NRC provided guidance for the contents of TS in its "Final Policy Statement on

Technical Specifications Improvement for Nu clear Power Reactors" (58 FR 39132, July 22, 1993). In particular, the NRC indicated that certain items could be relocated from the

TS to licensee-controlled documents, and identified criteria to be used to determine the

functions to be included in the TS. The NRC adopted revisions to 10 CFR 50.36 to

codify and incorporate these criteria. The NRC published in NUREG-1433 improved

standard technical specifications indicating that Regulatory Guide 1.97, Type A and

Category 1, non-Type A variables should be included in TS. The TS requirements

proposed for relocation do not meet this criteria based on plant-specific analysis

described in LGS UFSAR Section 7.5, and accordingly, are not required to be in the TS.

Operability and surveillance requirements for the drywell air temperature and

suppression chamber air temperature instrumentation will be maintained in the LGS

TRM, subject to the controls of 10 CFR 50.59.

In conclusion, based on the considerations discussed above, (1) there is reasonable

assurance that the health and safety of the public will not be endangered by operation in

the proposed manner, (2) such activities will be conducted in compliance with the

Commission's regulations, and (3) the issuance of the amendment will not be inimical to

the common defense and security or to the health and safety of the public.

6.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would change a requirement

with respect to installation or use of a facility component located within the restricted

area, as defined in 10 CFR 20, or would change an inspection or surveillance

requirement. However, the proposed amendment does not involve (i) a significant

hazards consideration, (ii) a significant change in the types or significant increase in the

amounts of any effluent that may be released offsite, or (iii) a significant increase in

individual or cumulative occupational radiation exposure. Accordingly, the proposed

amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR

51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact

statement or environmental assessment need be prepared in connection with the

proposed amendment.

7.0 REFERENCES

1. 10 CFR 50.36, "Technical Specifications."

2. NUREG-1433, "Standard Technical Specifications-General Electric Plants, BWR/4,"

Revision 3.1, dated December 1, 2005.

License Amendment Request Attachment 1 Changes to Accident Monitoring Instrumentation Page 8 of 8

Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

3. Letter dated September 27, 2005, from T. Tate (USNRC) to C. Crane (Exelon Nuclear), "Limerick Generating Station, Units 1 and 2 - Issuance of Amendments RE: Relocation

of Operability and Surveillance Requirement s for the Safety/Relief Valve Position Instrumentation (TAC Nos. MC3454 and MC3455)." 4. NRC "Final Policy Statement on Technical Specifications Improvement for Nuclear Power Reactors," 58 FR 39132, dated July 22, 1993.

5. NRC Final Rule, 10 CFR 50.36, "Technical Specifications," 60 FR 36953 (July 19, 1995).

6. Letter, T. E. Murley (USNRC) to R. F. Janecek (BWR Owners' Group), dated May 9, 1988.

7. Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," Revision 2, dated December 1980.

ATTACHMENT 2 License Amendment Request Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 and 50-353

Proposed Changes to Accident Monitoring Instrumentation Tec hnical Specifications Markup of Proposed Technical Specifications Pages Unit 1 TS Pages 3/4 3-85 3/4 3-87 Unit 2 TS Pages 3/4 3-85 3/4 3-87 TABLE 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION

MINIMUM APPLICABLE REQUIRED NUMBER CHANNELS OPERATIONAL

INSTRUMENT OF CHANNELS OPERABLE CONDITIONS ACTION

1. Reactor Vessel Pressure 2 1 1,2 80

2. Reactor Vessel Water Level 2 1 1,2 80

3. Suppression Chamber Water Level 2 1 1,2 80

4. Suppression Chamber Water Temperature 8, 6 locations 6, 1,2 80

1/location

5. Suppression Chamber Air Temperature Deleted 1 1 1,2 80

6. Drywell Pressure 2 1 1,2 80

7. Drywell Air Temperature Deleted 1 1 1,2 80

8. Deleted

9. Deleted

10. Deleted

11. Primary Containment Post-LOCA Radiation Monitors 4 2 1,2,3 81

12. North Stack Wide Range Accident Monitor** 3* 3* 1,2,3 81

13 Neutron Flux 2 1 1,2 80

LIMERICK - UNIT 1 3/4 3-85 Amendment No. 29 , 151 , 173 , 179 TABLE 4.3.7.5-1

ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

CHANNEL CHANNEL

INSTRUMENT CHECK(a) CALIBRATION(a)

1. Reactor Vessel Pressure

2. Reactor Vessel Water Level

3. Suppression Chamber Water Level

4. Suppression Chamber Water Temperature

5. Suppression Chamber Air Temperature Deleted

6. Primary Containment Pressure

7. Drywell Air Temperature Deleted

8. Deleted

9. Deleted

10. Deleted

11. Primary Containment Post LOCA Radiation Monitors **

12. North Stack Wide Range Accident Monitor***

13. Neutron Flux

(a) Frequencies are specified in the Surveillance Frequency Control Program unless otherwise noted in the table.

• • CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector,

for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an

installed or portable gamma source.

• • • High range noble gas monitors.

LIMERICK - UNIT 1 3/4 3-87 Amendment No. 116 , 173 , 179 , 186 TABLE 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION

MINIMUM APPLICABLE REQUIRED NUMBER CHANNELS OPERATIONAL INSTRUMENT OF CHANNELS OPERABLE CONDITIONS ACTION

1. Reactor Vessel Pressure 2 1 1,2 80

2. Reactor Vessel Water Level 2 1 1,2 80

3. Suppression Chamber Water Level 2 1 1,2 80

4. Suppression Chamber Water Temperature 8, 6 locations 6, 1,2 80

1/location

5. Suppression Chamber Air Temperature Deleted 1 1 1,2 80

6. Drywell Pressure 2 1 1,2 80

7. Drywell Air Temperature Deleted 1 1 1,2 80

8. Deleted

9. Deleted

10. Deleted

11. Primary Containment Post-LOCA Radiation Monitors 4 2 1,2,3 81

12. North Stack Wide Range Accident Monitor** 3* 3* 1,2,3 81

13. Neutron Flux 2 1 1,2 80

LIMERICK - UNIT 2 3/4 3-85 Amendment No. 115 , 135 , 141 TABLE 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

CHANNEL CHANNEL INSTRUMENT CHECK (a) CALIBRATION (a)

1. Reactor Vessel Pressure

2. Reactor Vessel Water Level

3. Suppression Chamber Water Level

4. Suppression Chamber Water Temperature

5. Suppression Chamber Air Temperature Deleted

6. Primary Containment Pressure

7. Drywell Air Temperature Deleted

8. Deleted

9. Deleted

10. Deleted

11. Primary Containment Post LOCA Radiation Monitors **

12. North Stack Wide Range Accident Monitor***

13. Neutron Flux

(a) Frequencies are specified in the Surveillance Frequency Control Program unless otherwise noted in the table.

• • CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an

installed or portable gamma source.

• • • High range noble gas monitors.

LIMERICK - UNIT 2 3/4 3-87 Amendment No. 78 , 135 , 141 , 147