ML073450040

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Tech Spec Pages for Amendment 173 Control Room Habitability
ML073450040
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 01/24/2008
From:
NRC/NRR/ADRO/DORL/LPLI-2
To:
Ennis R, NRR/DORL, 415-1420
Shared Package
ML073450034 List:
References
TAC MD5338
Download: ML073450040 (11)
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Text

(4) PSEG Nuclear LLC, pursuant to the Act and 10 CFF Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Farts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at reactor core power levels not in excess of 3339 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 173, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Inservice Testing of Pumps and Valves (Section 3.9.6, SSER No. 4)*

This License Condition was satisfied as documented in the letter from W. R. Butler (NRC) to C. A. McNeill,.Jr.

(PSE&G) dated December 7, 1987. Accordingly, this condition has been deleted.

  • The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.'

Amendment No. 173

(18) Upon implementation of Amendment No. 173 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by Surveillance Requirement 4.7.2.2.a, in accordance with TS 6.16.c.(i), the assessment of CRE habitability as required by Specification 6.16.c. (ii), and the measurement of CRE pressure as required by Specification 6.16..d, shall be considered met. Following implementation:

a. The first performance of Surveillance Requirement 4.7.2.2.a, in accordance with Specification 6.16.c.(i), shall be within the specified frequency of 6 years, plus the 18 month allowance of Surveillance Requirement 4.0.2, as measured from July 29, 2001, the date of the most recent successful tracer gas test, as stated in the December 9, 2003 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
b. The first performance of the periodic assessment of CRE habitability, Specification 6.16.c(ii), shall be 3 years, plus the 9 month allowance of Surveillance Requirement 4.0.2, as measured from July 29, 2001, the date of the most recent successful tracer gas test, as stated in the December 9, 2003 letter response to Generic Letter 2003-01,. or within .the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.
c. The first performance of the periodic measurement of CRE pressure, Specification 6.16.d, shall be within 18 months, plus the 138 days allowed by Surveillance Requirement 4.0.2, as measured from April 5, 2006, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.

Amendment No. 173

D. The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10. CFR Part 70. An exemption from. the criticality alarm requixements of 10 CFR 70.24 was granted in Special Nuclear Material License No. 1953, dated August. 21, 1985. This exemption is described in Section 9.1 of Supplement No. 5 to the SER. This previously granted exemption is continued in this operating license. An exemption from certain requirements of Appendix. A to .10 CFR Part 50, is described in Supplement No. 5 to the SER. This exemption is a schedular exemption to the requirements of General Design Criterion 64, permitting delaying functionality of the Turbine Building Circulating Water System-Radiation Monitoring System until 5 percent power for local indication, and until 120 days after fuel load for control room indication (Appendix R of SSER 5). Exemptions from certain requirements of Appendix J to 10 CFR Part 50, are described in Supplement No. 5 to the SER. These include an exemption from the requirement of Appendix J, exempting main steam isolation valve leak-rate testing at 1.10 Pa (Section 6.2.6 of SSER 5); an exemption from Appendix J, exempting Type C testing on traversing incore probe system shear valves (Section 6.2.6 of SSER 5); an exemption from Appendix J, exempting Type C testing for instrument lines and lines containing excess flow check valves (Section 6.2.6 of SSER 5); and an exemption from Appendix J, exempting Type C testing of thermal relief valves (Section 6.2.6 of SSER 5). These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

Amendment No. 173

E. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and: 0 CFR 50.54 (p). The plans,

.submitted by letter dated May 19, 2006, are entitled: "Salem-Hope Creek Nuclear Generating Station Security Training and Qualification Plan,"

and "Salem-Hope Creek Nuclear Generating Station Security Contingency Plan". The plans contain Safeguards Information protected under10 CFR 73.21.

F. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, PSEG Nuclear LLC shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> to the. NRC Operations. Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).

G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

H. This license is effective as of the date of issuance and shall expire at midnight. on April 11, 2026.

-FOR THE NUCLEAR REGULATORY COMMISSION original signed by H.R. Denton Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

1. Appendix A - Technical Specifications (NUREG-1201)
2. Appendix B - Environmental Protection Plan Date of Issuance: July 25, 1986 Amendment No. 173

INDEX ADMINISTRATIVE CONTROLS SECTION .... ..................... ............................................ PAGE 6.10 RECORD RETENTION ......................................... ............. 6-21 6.11 -RADIATION PROTECTION PROGRAM.I.. .......................... ......... 6-23 .

6.12 HIGH RADIATION AREA...................................... ............. 6-24 6.13 PROCESS CONTROL PROGRAM (PCP) .......................... .............. 6-25.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) ................. ............. 6-25 6.15 TECHNICAL SPECIFICATION (TS) BASES CONTROL PROGRAM ..... ............. 6-26 6.16 CONTROL ROOM ENVELOPE HABITABILITY PROGRAM.............. 6-26 .

HOPE CREEK XXV Amendment No. 173

ADMINISTRATIVE CONTROLS 6.15 TECHNICAL SPECIFICATION (TS) BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
b. PSEG may make changes to the Bases without prior NRC approval provided the changes do not require either of the following:
1. A change in the TS incorporated in the License, or
2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
c. Proposed changes to the Bases that require either condition of Specification 6.15.b above shall be reviewed and approved by the NRC prior to implementation.
d. Changes to the Bases implemented without prior NRC approval shall

-be provided to the NRC on a frequency-consistent with 10 CFR 50.71(e).

e. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

6.16 CONTROL ROOM ENVELOPE HABITABILITY PROGRAM A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Filtration System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.

The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.
b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

HOPE CREEK 6-26 Amendment No. 173

ADMINISTTPRT IVE CONTROLS 6.16 CONTROL ROOM ENVELOPE HABITABILITY PROGRJA1I (Continued)

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the Control Room Emergency Filtration System, operating at the flow rate requi red by Surveillance Requirement 4.7.2.1.c.1, at a Frequency of 36 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 36 month assessment of the CRE boundary.
e. The quantitative limits on unfiltered air inleakage into the CRE.

These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of Specification 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

HOPE CREEK 6-27 Amendment No. 173

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
1. With one control room emergency filtration subsystem inoperable for reasons other than Condition a.2, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and in COLD SHUTDOWN within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
2. With one or more control room emergency filtration subsystems inoperable due to an inoperable control room envelope (CRE) boundary,
a. Immediately, initiate action to implement mitigating actions; and
b. Within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />, verify mitigating actions ensure CRE occupant exposures to radiological and chemical hazards will not exceed the limits and actions to mitigate exposure to smoke hazards are taken; and C. Within 90 days, restore the CRE boundary to operable status; Otherwise, be in at least HOT SHUTDOWN within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and in COLD SHUTDOWN within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.
b. In OPERATIONAL CONDITION *
1. With one control room emergency filtration subsystem inoperable for reasons other than Condition b.3, 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.

"IThe main control room envelope (GRE) boundary may be opened intermittently under administrative control.

HOPE CREEK 3/4 7-6 No. 173 HOPECREE 3/47-6Amendment

PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION (continued)

2. With both control room emergency filtration subsystems

.inoperable for reasons other zhan Condition b.3, suspend handlinq of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.

3. With one or more control room emergency filtration subsystems inoperable due to an inoperable CRE boundary#", immediately suspend handling of recently irradiated fuel and operations with a potential for draining the vessel.
c. The provisions of Specification 3.0.3 are not applicable in Operational Condition
a. At least once per 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> by verifying that the control room air temperature is less than or equal to 850F1.
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 through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least 10 hours0.417 days <br />0.0595 weeks <br />0.0137 months <br /> with the heaters on in order to reduce the buildup of moisture on the carbon adsorbers and HEPA filters.
  • This does not require starting the non-running control emergency filtration subsystem.

"'The main control room envelope (CRE) boundary may be opened intermittently under administrative control.

HOPE CREEK 3/4 7-6a Amendment No. 173

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

c. At least once per 18 months or (i) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any. ventilation zone communicating with the subsystem filter train by:
1. Verifying that the subsystem satisfies the in-place penetration testing acceptance criteria of less than 0.05% and uses the test procedure guidance in. Regulatory Positions C.5.a, C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system filter train 'flow rate is 4000 cfm +/- 10%.
2. Verifying within 31 days after removal, that a laboratory test of a sample of the charcoal adsorber, when obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide penetration less than 0.5% when tested in accordance with ASTM D3803-1989 at a temperature of 30 0C and a relative humidity 70%.
3. Verifying a subsystem filter train flow rate of 4000 cfm +/-

10% during subsystem operation when tested in accordance with ANSI N510-1980.

d. After every 720 hours30 days <br />4.286 weeks <br />0.986 months <br /> of charcoal adsorber operation by verifying.

within 31 days after removal from the Control Room Emergency Filtration units that a laboratory analysis of a representative carbon sample, when obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows a methyl iodide penetration less than 0.5% when tested in accordance with ATSM D3803 -

1989 at a temperature of 30*C and a relative humidity of 70%.

e. At least once per 18 months by:
1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 7.5 inches Water Gauge. while operating the filter train subsystem at a flow rate of 4000 cfm +/- 10%.
2. Verifying with the control room hand switch in the recirculation mode that on each of the below recirculation mode actuation test signals, the subsystem automatically switches to the isolation mode of operation and the isolation dampers close within 5 seconds:

HOPE CREEK 3/4 7-7 Amendment No. 173

PLANT SYS' EMS SURVEILLANCE REQUIREMENTS (Continued)

.a) High Drywell Pressure b.) Reactor Vessel Water Level Low Low Low, Level 1 c). Control room ventilation radiation monitors high.

3. Verifying with the control room hand switch in the outside air mode that on each of the below pressurization mode actuation test signals, the subsystem automatically switches to the pressurization mode of operation:

a) High Drywell Pressure I

b) Reactor Vessel Water Level Low Low Low, Level 1 c) Control room ventilation radiation monitors high.

4. Verifying that the heaters dissipate 13 +/- 1.3 Kw when tested in accordance with ANSI N510-1980 and verifying humidity is maintained less than or equal to 70% humidity through the carbon adsorbers by performance of a channel calibration of the humidity control instrumentation.
f. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetration testing acceptance criteria of less than 0.05% in accordance with Regulatory Positions C.5.a and C.5.c of Regulatory Guide 1.52, Revision 2, March 1978, while operating the system at a flow rate of 4000 cfm +/--10%.
  • g. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration testing acceptance criteria of less than 0.05%

in accordance with Regulatory Positions C.5.a and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 4000 cfm +/- 10%.

4.7.2.2 The control room envelope boundary shall be demonstrated OPERABLE:

a. At a frequency in accordance with the Control Room Envelope Habitability Program by performance of control room envelope unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.

HOPE CREEK 3/4 7-8 Amendment No. 173

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