ML033570201

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Request for Change to Technical Specifications Regarding the Control Room Emergency Filtration System
ML033570201
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 12/12/2003
From: Bakken A
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LCR H02-01, LRN-03-0418
Download: ML033570201 (25)
v • d • e


Text

PSEG Nuclear LLC hi . P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 DEC 1 2 2003 LRN-03-0418 PSEG LCR H02-01 NuclearLLC U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CONTROL ROOM EMERGENCY FILTRATION SYSTEM HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354

Reference:

Letter LR-N03-0003, Request For Change To Technical Specifications Relaxation of Secondary Containment Operability Requirements and Elimination of FRVS Recirculation Charcoal Filters, dated January 18, 2003.

Pursuant to 10 CFR 50.90, PSEG Nuclear LLC (PSEG) hereby requests a revision to the Technical Specifications (TS) for Hope Creek Generating Station. In accordance with 10CFR50.91(b)(1), a copy of this submittal has been sent to the State of New Jersey.

Amendment 146 issued April 15, 2003 in response to the referenced letter, contained revisions to TS 3.7.2, CONTROL ROOM EMERGENCY FILTRATION SYSTEM for incorporation of Alternative Source Term (AST) for the fuel handling accident and consistency with TSTF-51, Rev. 2. However, it did not address all of the required changes. Changes to TS Table 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION and Table 4.3.7.1-1, RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS are also required. The proposed amendment would revise TS 3.7.2, Table 3.3.7.1-1,and Table 4.3.7.1-1 to reflect both changes required by TSTF-51, Rev. 2, and changes to be consistent with NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants.

PSEG has evaluated the proposed changes in accordance with 10CFR50.91(a)(1),

using the criteria in 10CFR50.92(c) and has determined that this request involves no significant hazards considerations. An evaluation of the requested changes is provided in Attachment 1 to this letter. In addition, there is no significant increase in the amounts or types of any effluents that may be released offsite, and there is no significant increase in individual or cumulative occupational radiation exposure. Consequently, the 4A0 1 95-2168 REV. 7/99

Document Control Desk 2 DEC 1 2 2003 LRN-03-41 8 LCR H02-01 proposed amendment satisfies the criteria of I OCFR51.22(c)(9) for categorical exclusion from the requirement for an environmental assessment. The marked up Technical Specification pages affected by the proposed change are provided in . Re-typed Technical Specification pages affected by the proposed change are provided in Attachment 3.

If you have any questions or require additional information, please contact Mr. Michael Mosier at (856) 339-5434.

I declare under penalty of perjury that the foregoing is true and corrct Executed on I//V12/a '?

/ / A. Christopher Bakken-Ill Sr. Vice President - Site Operations Attachments (3)

Document Control Desk 3 LRN-03-418 DEC 1 2 208 LCR H02-01 DC220 C: Mr. H. Miller, Administrator- Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. Boska, Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625

Document Control Desk LRN-03-0418 Attachment I LCR H03-05 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CONTROL ROOM EMERGENCY FILTRATION SYSTEM

1. DESCRIPTION .................................................... 2
2. PROPOSED CHANGE .................................................... 2
3. BACKGROUND .................................................... 4
4. TECHNICAL ANALYSIS ....................................................5 4.1 TSTF-51, Rev. 2 ................................................... 5 4.2 Revision 2 to NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants ................................................... 5
5. REGULATORY SAFETY ANALYSIS .................................................. 6 5.1 No Significant Hazards Consideration Determination ...................................... 6 5.2 Applicable Regulatory Requirements/Criteria .................................................. 9
6. ENVIRONMENTAL IMPACT EVALUATION .................................................. 9
7. REFERENCES...........................................................................................................9

Documnent Control Desk LRN-03-0418 Attachment I LCR H02-01 REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CONTROL ROOM EMERGENCY FILTRATION SYSTEM

1. DESCRIPTION This letter is a request to amend Facility Operating License NPF-57 for the Hope Creek Generating Station (HCGS). In our letter dated January 18, 2003 PSEG requested changes to the Technical Specifications (TS) to provide flexibility in scheduling outage tasks and to modify unnecessarily restrictive containment closure and ventilation system requirements. The elimination of the selected TS Engineered Safety Feature (ESF) requirements during core alterations and during the movement of sufficiently decayed irradiated fuel is consistent with TSTF-51, Rev. 2. Two additional changes, omitted from the original submittal, are included in Section 2 of this LCR as items a and b.

Changes to be consistent with NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants are proposed as items a through g of Section 2 of this LCR. Changes involving the deletion of Operational Condition 5 (Refueling) from the Control Room Ventilation Radiation Monitor are included as items c and d.

Changes involving the deletion of Operational Condition 4 (Cold Shutdown) from the Control Room Emergency Filtration (CREF) System are included as items e and f.:

Also, the addition of operations with the potential for draining the reactor vessel (OPDRV) is included in items a, b and g.

2. PROPOSED CHANGE The proposed changes to the TS are included in Attachment 2 of this submittal. In summary, it is requested that:
a. TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION (PAGE 314 3-64), under TABLE NOTATION currently states:

is revised to read:

2

Document Control Desk LRN-03-041 8 LCR H02-01

b. TABLE 4.3.7.1-1, RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (PAGE 314 3-67), under TABLE NOTATION currently states:

is revised to read:

c. TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION (PAGE 314 3-63), currently states:

APPLICABLE INSTRUMENTATION CONDITIONS

1. Control Room 1,2,3,5 and*

Ventilation Radiation Monitor is revised to read:

APPLICABLE INSTRUMENTATION CONDITIONS

1. Control Room 1,2,3 and*

Ventilation Radiation Monitor

d. TABLE 4.3.7.1-1, RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (PAGE 314 3-66): CURRENTLY STATES:

OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE INSTRUMENTATION REQUIRED

1. Control Room Ventilation Radiation Monitor 1, 2, 3, 5 and
  • Is revised to read:

3

Document Control Desk LRN-03-041 8 LCR H02-01 OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE INSTRUMENTATION REQUIRED

1. Control Room Ventilation Radiation Monitor 1, 2, 3, and *
e. Limiting Condition for Operation 3.7.2 (PAGE 314 7-6) under APPLICABILITY currently states:

APPLICABILITY: OPERATIONAL CONDITIONS 1,2, 3, 4, and *.

is revised to read:

APPLICABILITY: OPERATIONAL CONDITIONS 1,2,3, and *.

f. Limiting Condition for Operation 3.7.2 (PAGE 314 7-6) under ACTION b.

currently states:

INOPERATIONAL CONDITION 4 or

  • is revised to read:

INOPERATIONAL CONDITION *

g. Limiting Condition for Operation 3.7.2 (PAGE 314 7-6) under footnote currently states:

is revised to read:

3. BACKGROUND By letter dated January 18, 2003 PSEG requested changes to the Technical Specifications (TS) to provide flexibility in scheduling outage tasks and to modify unnecessarily restrictive containment closure and ventilation system requirements.

The elimination of the selected TS Engineered Safety Feature (ESF) requirements during core alterations and the movement of sufficiently decayed irradiated fuel is consistent with TSTF-51, Rev. 2. This change allows the flexibility 4

Document Control Desk LRN-03-041 8 LCR H02-01 to move personnel and equipment and perform work that would affect containment OPERABILITY during the handling of irradiated fuel. However, two additional changes, omitted from the original submittal, are included in Section 2 of this LCR as items a and b.

Changes to be consistent with NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants are proposed as items a through g of Section 2 of this LCR. Changes involving the deletion of Operational Condition 5 (Refueling) from the Control Room Ventilation Radiation Monitor are included as items c and d.

Changes involving the deletion of Operational Condition 4 (Cold Shutdown) from the CREF System are included as items e and f. Also, the addition of operations with the potential for draining the reactor vessel (OPDRV) is included in items a, b and g.

4. TECHNICAL ANALYSIS 4.1 TSTF-51, Rev. 2 The changes associated with items a and b of Section 2 are being made for consistency with TSTF-51, Rev. 2.

Following reactor shutdown, decay of the short-lived fission products greatly reduces the fission product inventory present in irradiated fuel. Amendment 146 was based on Alternative Source Term (AST) methodology for the fuel handling accident. The analysis also assumed a decay period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to take advantage of the reduced radionuclide inventory available for release in the event of a fuel handling accident. Following this period, the primary success path for mitigating the fuel handling accident no longer includes the functioning of the active containment systems. Therefore, the OPERABILITY requirements of the TS are modified to reflect that water level and decay time are the primary success paths for mitigating a fuel handling accident.

4.2. NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants.

Changes to be consistent with NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants are proposed as items a through g of Section 2 of this LCR. Changes involving the deletion of Operational Condition 5 (Refueling) from the Control Room Ventilation Radiation Monitor are included as items c and d. Changes involving the deletion of Operational Condition 4 (Cold Shutdown) from the CREF System are included as items e and f. Also, the addition of operations with the potential for draining the reactor vessel (OPDRV) is included in items a, b and g.

5

Document Control Desk LRN-03-0418 Attachment I LCR H02-01 Section 9.4.1.1.3 of the UFSAR states that the CREF system is designed to maintain control room habitability by providing filtration of fresh air and recirculated air during any accident that may release high radioactivity. In Operational Conditions 1, 2, and 3, a loss of coolant accident (LOCA) could lead to a fission product release to primary containment that leaks to secondary containment. In Operational Conditions 4 and 5, the probability and consequences of a LOCA are reduced because of the pressure and temperature limitations. Therefore, CREF system operability is not required except for other situations under which significant releases of radioactive material can be postulated, such as operations with the potential for draining the reactor vessel or movement of recently irradiated fuel assemblies in secondary containment.

The Control Room Ventilation Radiation Monitor is required to be OPERABLE in MODES 1, 2, and 3 and during OPDRVs and movement of recently irradiated fuel assemblies in secondary containment, to ensure that control room personnel are protected during a LOCA, FHA, or vessel draindown event.

During MODES 4 and 5, when these specified conditions are not in progress, the probability of a LOCA is low: thus; the monitor is not required.

5. REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Determination PSEG Nuclear LLC (PSEG) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10CFR50.92, "Issuance of Amendment," as discussed below:
1. Does the change involve a significant increase in the probability or consequences of an accident previously analyzed?

Response: No.

The proposed changes to Table 3.3.7.1-1, Radiation Monitoring Instrumentation, and Table 4.3.7.1-1, Radiation Monitoring Instrumentation Surveillance Requirements, adds 'recently" to modify irradiated fuel in the "*" footnote to provide consistency with TSTF-51, Rev. 2. Proposed changes to eliminate Operational Condition 5 from Tables 3.3.7.1-1 and 4.3.7.1-1, Control Room Ventilation Radiation Monitor, Operational Condition 4 from Control Room Emergency Filtration (CREF) System and adding operations with the potential for draining the reactor vessel (OPDRV) to Tables 3.3.7.1-land 4.3.7.1-1 footnote`

and the CREF System are consistent with NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants.

6

Document Control Desk LRN-03-0418 Attachment I LCR H02-01 The proposed changes associated with the fuel handling accident (FHA) do not involve a change to structures, components, or systems that would affect the probability of an accident previously evaluated in the Hope Creek Updated Final Safety Analysis Report (UFSAR). The FHA for the Hope Creek Generating Station (HCGS) is defined as a drop of a fuel assembly over irradiated assemblies in the reactor core 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reactor shutdown. Alternative Source Term (AST) is used to evaluate the dose consequences of a postulated accident. The FHA has been analyzed without credit for Secondary Containment, Filtration Recirculation and Ventilation System (FRVS), and CREF system. The resultant radiological consequences are within the acceptance criteria set forth in 10CFR50.67 and Regulatory Guide (RG) 1.183. This amendment does not alter the methodology or equipment used in fuel handling operations. The equipment hatch, personnel air locks, other containment penetrations, or any component thereof is not an accident initiator. Actual fuel handling operations are not affected by the proposed changes.

Consequently the probability of a previously analyzed FHA is not affected by the proposed amendment. No other accident initiator is affected by the proposed changes.

Therefore, this proposed amendment does not involve a significant increase in the probability of occurrence or radiological consequences of an accident previously analyzed.

2. Does the change create the possibility of a new or different kind of accident from any accident previously analyzed?

Response: No The proposed changes to Table 3.3.7.1-1, Radiation Monitoring Instrumentation, and Table 4.3.7.1-1, Radiation Monitoring Instrumentation Surveillance Requirements, adds 'recently" to modify irradiated fuel in the "*n footnote provides consistency with TSTF-51, Rev. 2. Proposed changes to eliminate Operational Condition 5 from Tables 3.3.7.1-1 and 4.3.7.1-1, Control Room Ventilation Radiation Monitor, Operational Condition 4 from CREF System and adding OPDRVto Table 3.3.7.1-1 land 4.3.7.1-1 footnote "*" and the CREF System are consistent with NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants.

The proposed amendment will not create the possibility for a new or different type of accident from any accident previously evaluated because changes to the allowable activity in the primary and secondary systems do not result in changes to the design or operation of these systems. The evaluation of the effects of the proposed changes indicates that all design standard and applicable safety 7

Document Control Desk LRN-03-0418 Attachment I LCR H02-01 criteria limits are met. Equipment important to safety will continue to operate as designed. Component integrity is not challenged. The changes do not result in any event previously deemed incredible being made credible. The changes do not result in more adverse conditions or result in any increase in the challenges to safety systems. The systems affected by the changes are used to mitigate the consequences of an accident that has already occurred. The proposed TS changes do not significantly affect the mitigative function of these systems.

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

3. Does the change involve a significant reduction in the margin of safety?

Response: No The proposed changes to Table 3.3.7.1-1, Radiation Monitoring Instrumentation, and Table 4.3.7.1-1, Radiation Monitoring Instrumentation Surveillance Requirements, adds urecently" to modify irradiated fuel in the `*"footnote provides consistency with TSTF-51, Rev. 2. Proposed changes to eliminate Operational Condition 5 from Tables 3.3.7.1-1 and 4.3.7.1-1,Control Room Ventilation Radiation Monitor, Operational Condition 4 from CREF System and adding OPDRVto Table 3.3.7.1-1 land 4.3.7.1-1 footnote "*" and the CREF System are consistent with NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants.

The proposed changes revise the TS to establish operational conditions where specific activities represent situations during which significant radioactive releases can be postulated. These operational conditions are consistent with the design basis analysis and are established such that the radiological consequences remain at or below the regulatory guidelines. Safety margins and analytical conservatisms are retained to ensure that the analysis adequately bounds all postulated event scenarios. The proposed TS continue to ensure that the total effective dose equivalent (TEDE) for the control room (CR), the exclusion area boundary (EAB), and low population zone (LPZ) boundaries are below the corresponding acceptance criteria specified in IOCFR50.67 and RG 1.183.

Therefore, these changes do not involve a significant reduction in margin of safety.

Based on the above, PSEG concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10CFR50.92(c),

and, accordingly, a finding of "no significant hazards consideration" is justified.

8

Document Control Desk LRN-03-0418 Attachment I LCR H02-01 5.2 Applicable Reguiatory Requirements/Criteria The proposed amendment would revise TS 3.7.2, Table 3.3.7.1-1, and Table 4.3.7.1-1 to reflect both changes required by TSTF-51, Rev. 2, and changes associated with OPERATIONAL CONDITIONS to be consistent with NUREG-1433 Vol. 1, Rev. 2, Standard Technical Specifications, General Electric Plants. The FHA dose analysis was performed using AST and TEDE dose criteria in accordance with the guidance provided in RG 1.183.

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. ENVIRONMENTAL IMPACT EVALUATION PSEG 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. REFERENCES 7.1. Letter LR-N02-0002, Request For Change To Technical Specifications Relaxation Of Secondary Containment Operability Requirements And Elimination Of FRVS Recirculation Charcoal Filters, dated June 28, 2002.

7.2. USNRC Regulatory Guide 1.183, uAltemative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", July 2000.

7.3.1 OCFR50.67, uAccident Source Term".

7.4.TSTF-51, Rev. 2.

9

Document Control Desk LRN-03-041 8 Attachment I LCR H02-01 7.5. Hope Creek Amendment 146, April 15, 2003, Relaxation Of Secondary Containment Operability Requirements And Elimination Of FRVS Recirculation Charcoal Filters.

10

Document Control Desk LRN-03-021 7 LCR H02-01 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS)

TECHNICAL SPECIFICATION PAGE WITH PROPOSED CHANGE The following are marked-up Technical Specifications for Facility Operating License NPF-57 affected by this change request:

Technical Specification Paqe Table 3.3.7.1-1 3/4 3-63 Table 3.3.7.1-1 3/4 3-64 Table 4.3.7.1-1 3/4 3-66 Table 4.3.7.1-1 3/4 3-67 3/4.7.2 3/4 7-6

TABLE 3.3.7.1-1 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM/TRIP INSTRUMENTATION OPERABLE CONDITIONS SETPOINT ACTION

1. Control Room 2/intake 1,2,30 and *
  • 2x105PC/cc** 71 Ventilation Radiation Monitor
2. Area Monitors
a. Criticality Monitors
1) New Fuel 1 2 5 mR/hr jnd 72 Storage Vault
  • 20 mR/hr
2) Spent Fuel 1 2 5 mR/hr and 72 Storage Pool
  • 20 mR/hr )

b.. Control Room Direct 1 At all times 2.5 mR/hr(a) 72 Radiation Monitor

3. Reactor Auxiliaries Cooling 1 At all times 9 x 10 5 pc/cc(a) 73 Radiation Monitor
4. Safety Auxiliaries Cooling 1/loop At all times 6 x 10 pC/cc 73 Radiation Monitor
5. Offgas Pre-treatment 1 (b) 74 Radiation Monitor HOPE CREEK 3/4 3-63 AclmI\ o

TABLE 3.3.7.1-1 (Continued)

RADIATION MONITORING INSTRUMENTATION LA TABLE NOTATION

      • When the offgas treatment system is operating.
  1. With fuel in the new fuel storage vault.
    1. With fuel in the spent fuel storage pool.

(a)Alarm only.

(b)Alarm setpoint to be set in accordance with Specification 3.11.2.7.

HOPE CREEK 3/4 3-64

&P7?%J-,

Oa3O* I

TABLE 4.3.7.1-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS OPERATIONAL CHANNEL CONDITIONS FOR CHANNEL FUNCTIONAL CHANNEL WHICH SURVEILLANCE INSTRUMENTATION CHECK TEST CALIBRATION REQUIRED

1. Control Room Ventilation Radiation Monitor S Q R 1, 2, 30and
  • I
2. Area Monitors
a. Criticality Monitors
1) New Fuel Storage Vault S Q R
2) Spent Fuel Storage Pool S Q R
b. Control Room Direct S Q R At all times Radiation Monitor
3. Reactor Auxiliaries Cooling S Q R At all times Radiation Monitor
4. Safety Auxiliaries Cooling S Q R At all times Radiation Monitor
5. Offgas Pre-treatment S Q R Radiation Monitor HOPE CREEK 3/4 3-66 Amendment No. a I

TABLE 4.3.7.1-1 (Continued)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

/k TABLE NOTATION

  1. With $iel in the new fuel storage vault.
    1. With fuel in the spent fuel storage pool. n A
  • When irradiated fuel is being handled in the secondary containmentav
    • When the offgas treatment system is operating.

HOPE CREEK 3/4 3-67 A 0 0-

PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent control room emergency filtration system subsystems shall be OPERABLE with each subsystem consisting of:

a) One control room supply unit, b) One filter train, and c) One control room return air fan.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3,$ and *.

ACTION:

a. In OPERATIONAL CONDITION 1, 2 or 3 with one control room emergency filtration subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. In OPERATIONAL CONDITION S *: I
1. With one control room emergency filtration subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the pressurization/recirculation mode of operation.
2. With both control room emergency filtration subsystems inoperable, suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
c. The provisions of Specification 3.0.3 are not applicable in Operational Condition *.

SURVEILLANCE REQUIREMENTS 4.7.2 Each control room emergency filtration subsystem shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal to 85*F*.
b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, the control area chilled water pump, flow
  • When recently irrada dfel f is being handled in the secondarv contai entX A l OThis does not require starting the non-running control emergency filtration subsystem.

HOPE CREEK 3/4 7-6 Amendment No.

Document Control Desk LRN-03-0217 LCR H02-01 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS)

TECHNICAL SPECIFICATION PAGE WITH PROPOSED CHANGE The following are retyped Technical Specifications for Facility Operating License NPF-57 affected by this change request:

Technical Specification Page Table 3.3.7.1-1 3/4 3-63 Table 3.3.7.1-1 3/4 3-64 Table 4.3.7.1-1 314 3-66 Table 4.3.7.1-1 3/4 3-67 314.7.2 3/4 7-6

TABLE 3.3.7.1-1 RADIATION MONITORING INSTRUMENTATION ..

MINIMUM CHANNELS APPLICABLE ALARM/TRIP INSTRUMENTATION OPERABLE CONDITIONS SETPOINT ACTION

1. Control Room 2/intake 1,2,3 and * < 2x10-5 pC/cc** 71 I Ventilation Radiation Monitor
2. Area Monitors
a. Criticality Monitors
1) New Fuel 1 #t > 5 mR/hr 4nd 72 Storage Vault
  • 20 mR/hr aV
2) Spent Fuel 1 > 5 mR/hr and 72 Storage Pool < 20 mR/hr a
b. Control Room Direct 1 At all times 2.5 mR/hr(a) 72 Radiation Monitor
3. Reactor Auxiliaries Cooling 1 At all times 9 x 10 PC/cc 73 Radiation Monitor
4. Safety Auxiliaries Cooling l/loop At all times 6 x 10 PC/cc ) 73 Radiation Monitor
5. Offgas Pre-treatment 1 (b) 74 Radiation Monitor HOPE CREEK 3/4 3-63 Amendment No. I

TABLE 3.3.7.1-1 (Continued)

RADIATION MONITORING INSTRUMENTATION TABLE NOTATION

      • When the offgas treatment system is operating.
  1. With fuel in the new fuel storage vault.
    1. With fuel in the spent fuel storage pool.

(a)Alarm only.

(b)Alarm setpoint to be set in accordance with Specification 3.11.2.7.

HOPE CREEK 3/4 3-64 Amendment No.

TABLE 4.3.7.1-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS OPERATIONAL CHANNEL CONDITIONS FOR CHANNEL FUNCTIONAL CHANNEL WHICH SURVEILLANCE INSTRUMENTATION CHECK TEST CALIBRATION REQUIRED

1. Control Room Ventilation Radiation Monitor S Q R 1, 2, 3, and
  • I
2. Area Monitors
a. Criticality Monitors
1) New Fuel Storage Vault S Q R
2) Spent Fuel Storage Pool S Q R
b. Control Room Direct S Q R At all times Radiation Monitor
3. Reactor Auxiliaries Cooling S Q R At all times Radiation Monitor
4. Safety Auxiliaries Cooling Q R At all times Radiation Monitor
5. Offgas Pre-treatment S Q R Radiation Monitor HOPE CREEK 3/4 3-66 Amendment No.

I

TABLE 4.3.7.1-1 (Continued)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION

  1. With fuel in the new fuel storage vault.
    1. With fuel in the spent fuel storage pool.
    • When the offgas treatment system is operating.

HOPE CREEK 3/4 3-67 Amendment No.

PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent control room emergency filtration system subsystems shall be OPERABLE with each subsystem consisting of:

a) One control room supply unit, b) One filter train, and c) One control room return air fan.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and *.

ACTION:

a. In OPERATIONAL CONDITION 1, 2 or 3, with one control room emergency filtration subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. In OPERATIONAL CONDITION *: I
1. With one control room emergency filtration subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 30 days or initiate and maintain operation of the OPERABLE subsystem in the pressurization/recirculation mode of operation.
2. With both control room emergency filtration subsystems inoperable, suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
c. The provisions of Specification 3.0.3 are not applicable in Operational Condition
a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal to 85'F*.
b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, the control area chilled water pump, flow

'This does not require starting the non-running control emergency filtration subsystem.

HOPE CREEK 3/4 7-6 Amendment No.

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