ML073470515

Amd 286/License DPR-75, Technical Specifications, Established More Effective & Appropriate Action, Surveillance & Administrative Requirements Re Ensuring the Habitability of the Control Room Envelop

ML073470515
Person / Time
Site:	Salem
Issue date:	01/24/2008
From:	Richard Ennis NRC/NRR/ADRO/DORL/LPLI-2
To:	Levis W Public Service Enterprise Group
Ennis R B
Shared Package
ml073470339	List: ML073470344 ML073470408 ML073470515
References
TAC MD5367, TAC MD5368
Download: ML073470515 (8)

Text

-4 -(2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 269, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's*

Safety Evaluation Report "Special Low Power Test Program", dated August 22, .1980 (See Amendment No. 2 to DPR-75 for the Salem Nuclear Generating Station, Unit No. 2) prior to operating the facility at a power level above five percent.Within 31 days following completion of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report, PSE&G shall perform a boron mixing and cooldown test using decay heat and Natural Circulation.

PSE&G shall submit the test procedure to the.NRC for review and approval prior to performance of the test. The results of this test shall be submitted to the NRC prior to starting up following the first refueling outage.(4) Initial Test Program PSE&G shall conduct the post-fuel-loading initial test program (set forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making ahy major modifications of this program unless modifications have been identified and have received prior NRC approval.

Majormodifications are defined as: (a) Elimination of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential;(b) Modification of test objectives, methods or acceptance criteria for any test identified in Chapter 13 of the Final Safety Analysis.Report, as amended, as essential;(c) Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No. 269

-22c-(33) Upon implementation of Amendment No. 269 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE)unfiltered air inleakage as required by SR 4.7.6.2, in accordance with TS 6.17.c.(i), the assessment of CRE habitability as required by Specification 6.17.c. (ii), and the measurement of CRE pressure as required by Specification 6.17.d, shall be considered met. Following implementation:

• a. The first performance of SR 4.7.6.2, in accordance with Specification 6.17.c.(i), shall be within the specified frequency of 6 years, plus the 18 month allowance of SR 4.0.2, as measured from June 4, 2003, 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 6.17.c(ii), shall be 3 years, plus the 9 month allowance of SR 4.0.2, as measured from June 4, 2003, 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 6.17.d, shall be within 18 months, plus the 138 days allowed by SR 4.0.2, as measured from September 22, 2005, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.

Amendment No. 269 INDEX SECTION PAGE 6 .1 R E S PO N S I B IL IT Y .............................................................

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.....i............ ..... 6- 1 6.2 ORGANIZATION Onsite and Office Organizations

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6-1 F a c i l i t y S t a f f ................................................................................................................................................

6- 1 Sh ift T echn ical A dv isor ...............................................................................................................

.6-7 6.3 FACILITY STAFF QUALIFICATIONS

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6-7 6 .4 T R A I N I N G .......................................................................................................................................

...... 6- 7 6.5 REVIEW AND AUDIT (THIS SECTION DELETED) .............

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6-8 6.6 REPORTABLE EVENT ACTION .............

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6-16 6.7 SA FETY L IM IT V IOLA TION .......................................................................................................................

6-16 6.8 PROCEDURES AND PROGRAMS ................................................................................................................

6-17 6.9 REPORTING REQUIREMENTS

6.9.1 ROUTINE

REPORTS ..........................................................

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6-20 6 .9 .2 S PE C IA L R E P O R T S ...................................................................................................................................

6-2 4b 6 .10 R E CO R D R E T E N T IO N ...........................................................................................................................................

6-2 5 6.11 RADIATION PROTECTION PROGRAM ..............

6-2..............6.

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....6-26 6 .12 H IGH RA D IA T ION A REA ..............................................................................................................................

6-27 6.13 PROCESS CONTROL PROGRAM (PCP) ..................................................................................................

6-28 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) .........

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6-29 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS .................................................

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6-29 6.16 TECHNICAL SPECIFICATION (TS) BASES CONTROL PROGRAM ....................................

6-30 6.17 -CONTROL ROOM ENVELOPE HABITABILITY PROGRAM ...............................

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6-31 SALEM -UNIT 2 XVIII Amendment No. 269 PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONINGSYSTEM LIMITING CONDITION FOR OPERATION 3.7.6 The common control room emergency air conditioning system (CREACS)*shall be OPERABLE with: a. Two independent air conditioning filtration trains (one from each unit) consisting of: 1. Two fans and associated outlet dampers, 2. One cooling coil, 3. One charcoal adsorber and HEPA filter array, 4. Return air isolation damper.b. All other automatic dampers required for operation in the pressurization or recirculation modes.c. The control room envelope intact.NOTE: The control room envelope (CRE) boundary may be opened intermittently under administrative control.APPLICABILITY:

ALL MODES and during movement of irradiated fuel assemblies.

ACTION: MODES 1, 2, 3, and 4 a. With one filtration train inoperable, align CREACS for single filtration train operation within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />, and restore the inoperable filtration train to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.b. With CREACS aligned for single filtration train operation and with one of the two remaining fans or associated outlet damper inoperable, restore the inoperable fan or damper fo OPERABLE status within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.'c. With the Control Room Envelope boundary inoperable:

1. Immediately, initiate action to implement mitigating actions, and 2. Within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />, verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits, and 3. Within 90 days, restore the Control Room Envelope boundary to OPERABLE status, or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.The CREACS is a shared system with Salem Unit 1 SALEM -UNIT 2 3/4 7-15 Amendment No. 269 PLANT SYSTEMS L IMITING CONDITION F OR 02ERATION (C tontlinued)

d. With one or both series isolation damper(s) on a normal Control Area Air Conditioning System (CAACS) outside air intake or exhaust duct inoperable, close the affected duct within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> by use of at least one isolation damper secured in the closed position or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />. (Refer to ACTION 28 of Table 3.3-6.)e. With one or. both isolation damper(s) on an outside emergency air conditioning air intake duct inoperable, close the affected duct within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> by use of at least one isolation damper secured in the closed position and restore the damper(s) to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and, in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.f. With any isolation damper between the normal CAACS and the CREACS inoperable, secure the damper in the closed position within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> or be in *at -least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.MODES 5 and 6 or during movement of irradiated fuel assemblies

a. With one filtration train inoperable, align CREACS for single filtration train operation within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />, or suspend movement of irradiated fuel assemblies.

b. With CREACS aligned for single filtration train operation with one of the two' remaining fans or associated outlet damper inoperable, restore the fan or damper to OPERABLE status within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />, or suspend movement of irradiated fuel assemblies.

c. With two filtration trains inoperable, immediately suspend movement of irradiated fuel assemblies.

d. With the Control Room Envelope boundary inoperable, immediately suspend movement of irradiated fuel assemblies.

e. With one or both series isolation damper(s) on a normal CAACS outside air intake or exhaust duct inoperable, immediately suspend movement of irradiated fuel assemblies until the affected duct is closed by use of at least one isolation damper secured in the closed position.

,(Refer to ACTION 28 of Table 3.3-6.)f. With one or both series isolation damper(s) on an outside emergency air conditioning air intake duct inoperable, immediately' suspend movement of irradiated fuel assemblies until the affected duct is closed by use of at least one isolation damper secured in the closed position.

To resume movement of irradiated fuel assemblies, at least one emergency air intake duct must be operable on each unit.g. With any isolation damper between the CAACS and the CREACS inoperable,.

immediately suspend movement of irradiated fuel assemblies until the damper is closed and secured in the closed position.SALEM -UNIT 2 3N 3/4 7-16 Amendment No. 269 PLANT SYSTEMS SURVEILLANCE REQU-IREMENTS 4.7.6.1 The control room emergency air conditioning system shall be demonstrated OPERABLE: a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train(s) and verifying that the train(s)operates with each fan operating for at least 15 minutes.b. At least once per 18 months or prior to return to service (1) 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 system, by: 1. Verifying that the charcoal adsorbers remove 99% of a-halogenated hydrocarbon refrigerant test gas when they are tested in-place while operating the ventilation system at a flow rate of 8000 cfm+/-10%.2. Verifying that the HEPA filter banks remove 99% of the DOP when they are tested in-place while operating the ventilation system at a flow rate of 8000 cfm +/-10%.3. Verifying within 31 days after removal from the CREACS unit, 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 2.5% when tested'in accordance with ASTM D3803-1989 at a temperature of 30'C and a relative humidity.of 95%.c. 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 CREACS unit, 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 197.8, shows a methyl iodide penetration less than 2.5% when tested in accordance with ASTM D3803-1989 at a temperature of 30'C and a relative humidity of 95%.d. At least once per 18 months by: 1. Verifying that the pressure drop across the combined HEPA filter and charcoal adsorber*

bank is 3.5 inches water gauge while operating the ventilation system at a flow rate of 8000 cfm +/- 10%.2. Verifying that on a safety injection test signal or control room intake high radiation test signal, the system automatically actuates in the pressurization mode by opening the outside air supply and diverting air flow through the HEPA filter and charcoal adsorber bank.3. Deleted.SALEM, -UNIT 2 3/4 7-17 Amendment No. 269 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

4. Verifying that on a manual actuation signal, the system will actuate to the required pressurization or recirculation operating mode.5. Verify each CREACS train has the capability to remove the assumed heat load.e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 99% of the DOP when they are tested in-place while operating the filter system at a flow rate of 8000 cfm +/- 10%.f. After each complete or partial replacement of a charcoal absorber bank by verifying that the charcoal absorbers remove 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place while operating the filter system at a flow rate of 8000 cfm +/- 10%.4.7.6.2 Perform required CRE unfiltered air inleakage testing inaccordance with the Control Room Habitability Program (Refer to TS 6.17).SALEM -UNIT 2 3/4 7-17a Amendment No. 269 ADMINISTRATIVE CONTROLS 6.17 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 Air Conditioning System (CREACS), 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:ý

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.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 CREACS, operating at the flow rate required by the Surveillance Requirements, at a frequency of 36 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 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 Surveillance Requirement 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.

SALEM -UNIT 2 6-31 Amendment No. 269