ML082270698

Technical Specifications, Amendment No. 243 to NPF-49, Control Room Habitability

ML082270698
Person / Time
Site:	Millstone
Issue date:	09/24/2008
From:	Division of Operating Reactor Licensing
To:
Sanders, Carleen, NRR/DORL 415-1603
Shared Package
ml082270656	List: ML082270689 ML082270698
References
TAC MD6115, TAC MD6116
Download: ML082270698 (15)

Text

-4-(2) Technical Specifications The Technical Specifications contained in Appendix A, revised through Amendment No.2 4 3 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated into the license. DNC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.(3) DNC shall not take any action that would cause Dominion Resources, Inc. (DRI) or its parent companies to void, cancel, or diminish DNC's commitment to have sufficient funds available to fund an extended plant shutdown as represented in the application for approval of the transfer of the licenses for MPS Unit No. 3.(4) Immediately after the transfer of interests in MPS Unit No. 3 to DNC, the amount in the decommissioning trust fund for MPS Unit No. 3 must, with respect to the interest in MPS Unit No. 3, that DNC would then hold, be at a level no less than the formula amount under 10 CFR 50.75.(5) The decommissioning trust agreement for MPS Unit No. 3 at the time the transfer of the unit to DNC is effected and thereafter is subject to the following: (a) The decommissioning trust agreement must be in a form acceptable to the NRC.(b) With respect to the decommissioning trust fund, investments in the securities or other obligations of Dominion Resources, Inc. or its affiliates or subsidiaries, successors, or assigns are prohibited.

Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.(c) The decommissioning trust agreement for MPS Unit No. 3 must provide that no disbursements or payments from the trust, other than for ordinary administrative expenses, shall be made by the trustee until the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.(d) The decommissioning trust agreement must provide that the agreement can not be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

Renewed License No. NPF-49 Amendment No. 243 (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets 2. Communications

3. Minimizing fire spread 4. Procedures for implementing integrated fire response strategy 5. Identification of readily-available pre-staged equipment 6. Training on integrated fire response strategy 7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: 1. Water spray scrubbing 2. Dose to onsite responders (11) Upon implementation of Amendment No. 243 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 4.7.7.h, in accordance with TS 6.8.4.h.c.(i), the assessment of CRE habitability as required by TS 6.8.4.h.c.(ii), and the measurement of CRE pressure as required by TS 6.8.4.h.d, shall be considered met. Following implementation:.(a) The first performance of SR 4.7.7.h, in accordance with TS 6.8.4.h.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 16, 2004, the date of the most recent successful tracer gas test, as identified in the report referenced in the August 31, 2004 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, TS 6.8.4.h.c.(ii), shall be within 3 years; plus the 9-month allowance of SR 4.0.2, as measured from June 16, 2004, the date of the most recent successful tracer gas test, as identified in the report referenced in the August 31, 2004 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, TS 6.8.4.h.d, shall be within 24 months, plus the 180 days allowed by SR 4.0.2, as measured from March 23, 2007, the date of the most recent successful pressure measurement test, or within 180 days if not performed previously.

D. Exemptions from certain requirements of Appendix J to 10 CFR Part 50 (Section 6.2.6, SSER 4) and from a portion of the requirements-of General Design Criterion 4 (Section 3.9.3.1, SSER 4) of Appendix A to 10 CFR Part 50 have previously been granted. See Safety Evaluation Report Supplement 4, November 1985. 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.

Renewed License No. NPF-49 Amendment No. 2-3-4,, 2,43ý 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 10 CFR 50.54(p).

The combined set of plans, submitted by letter dated October 15, 2004, as supplemented by letter dated May 15, 2006, is entitled: "Millstone, North Anna and Surry Power Stations' Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 0" The set contains Safeguards Information protected under 10 CFR 73.21.F. Deleted.G. The licensee 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. Fire Protection (Section 9.5.1, SER, SSER 2, SSER 4. SSER 5)DNC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER (NUREG-1031) issued July 1985 and Supplements Nos. 2, 4, and 5 issued September 1985, November 1985, and January 1986, respectively, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.This renewed operating license is effective as of its date of issuance and shall expire at midnight on November 25, 2045.FOR THE NUCLEAR REGULATORY COMMISSION

/RA/J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments:

1. Appendix A -Technical Specifications

2. Appendix B -Environmental Protection Plan Date of Issuance:

November 28, 2005 Renewed License No. NPF-49 Amendment No. 243 INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.8 PROCEDURES AN D PROGRA M S ..............................................................................

6-14 6.9 REPO RTIN G REQ U IRE M EN TS ...................................................................................

6-17d 6.9.1 ROUTINE REPORTS ....................................

6-17d Startu p R ep ort ...........................................................................................

1 ..6-18 Annual Reports ..................................

.... ...618 Annual Radiological Environmental Operating Report .................................

6-19 Annual Radioactive Effluent Release Report ...............................................

6-19 CORE OPERATING LIM ITS REPORT ................................

......................

6-19a Steam Generator Tube Inspection Report ......................................................

6-21 6.9.2 SPECIAL REPORTS ..........................

' .............

6-21 6.10 DELETED 6.11 RADIATION PROTECTION PROGRAM ....... ... ........................................

6-21a 6.12 HIGH RADIATION AREA .......................................

6-21a 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM ) ..............................................................

6-24 6.14 RADIOACTIVE W ASTE TREATM ENT ....................................................................

6-24 6.15 RADIOACTIVE EFFLUENT CONTROLS PROGRAM ...........................

6-25 6.16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .....................

6-26 6.17 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM ..................

6-26 6.18 TECHNICAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM ....... 6-26 6.19 COMPONENT CYCLIC OR TRANSIENT LIMIT ..............................

6-27 MILLSTONE

-UNIT 3 xix Amendment No. 56, 69, 86, -I-+7, 4-8, N204, 2-4-2, --5, 2-223, 229, 3-, 243 TABLE 3.3-3 (Continued)

TABLE NOTATIONS# The Steamline Isolation Logic and Safety Injection Logic for this trip function may be blocked in this MODE below the P- II (Pressurizer Pressure Interlock)

Setpoint.* MODES 1, 2, 3, and 4.During movement of recently irradiated fuel assemblies.

Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.ACTION STATEMENTS I.ACTION 14-ACTION 15 -ACTION 16 -ACTION 17 -ACTION 18 -ACTION 19 -With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />;however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore.the inoperable channel to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />;however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 7 days.After 7 days, or if no channels are OPERABLE, immediately suspend movement of recently irradiated fuel assemblies, if applicable, and be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.MILLSTONE

-UNIT 3 3/4 3-24 Amendment No. -4, O, W89, 4-29, 203, 24-9, 22---, 242, 243 TABLE 4.3-2 (Continued)

TABLE NOTATION I. Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.2. This surveillance may be performed continuously by the emergency generator load sequencer auto test system as long as the EGLS autotest system is demonstrated OPERABLE by the performance of an ACTUATION LOGIC TEST at least once per 92 days.3. On a monthly basis, a loss of voltage condition will be initiated at each undervoltage monitoring relay to verify individual relay operation.

Setpoint verification and actuation of the associated logic and alarm relays will be performed as part of the CHANNEL CALIBRATION required once per 18 months.4. For Engineered Safety Features Actuation System functional units with only Potter &Brumfield MDR series relays used in a clean, environmentally controlled cabinet, as discussed in Westinghouse Owners Group Report WCAP- 13900, the surveillance interval for slave relay testing is R.MODES 1, 2, 3, and 4.During movement of recently irradiated fuel assemblies.

MILLSTONE

-UNIT 3 3/4 3-41 Amendment No. 4-5, 74, 7-9, 4-00, 9, 4-9k, 203, 2-+9, 229, 242, 243 TABLE 3.3-6 (Continued)

TABLE NOTATIONS With fuel in the fuel storage pool areas.ACTION STATEMENTS ACTION 28 -With less than the Minimum Channels OPERABLE requirement, recently irradiated fuel assembly movement may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel storage pool area. Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving movement of recently irradiated fuel assemblies.

ACTION 29 -With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.MILLSTONE

-UNIT 3 3/4 3-44A Amendment No. 46, 4-2-9, 2-2-9, 243 PLANT SYSTEMS 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7 Two independent Control Room Emergency Air Filtration Systems shall be OPERABLE.*

APPLICABILITY:

MODES 1, 2, 3, and 4.During movement of recently irradiated fuel assemblies.

ACTION: MODES 1,2, 3 and 4: a. With one Control Room Emergency Air Filtration System inoperable, except as specified in ACTION c., restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.b. With both Control Room Emergency Air Filtration Systems inoperable, except as specified in ACTION c., restore at least one inoperable system to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.c. With one or more Control Room Emergency Air Filtration Systems inoperable due to an inoperable CRE boundary, perform the following:

1. Immediately initiate action to implement mitigating actions, and 2. Verify, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, mitigating actions ensure CRE occupant exposures to radiological and chemical hazards will not exceed limits, and mitigating actions are taken for exposure to smoke hazards, and 3. Restore CRE boundary to OPERABLE status within 90 days.Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.During movement of recently irradiated fuel assemblies:

d. With one Control Room Emergency Air Filtration System inoperable, restoie the inoperable system to OPERABLE status within 7 days. After 7 days, either initiate and maintain operation of the remaining OPERABLE Control Room Emergency Air Filtration System in the emergency mode of operation, or immediately.suspend the movement of recently irradiated fuel assemblies.

• The Control Room Envelope (CRE) boundary may be opened intermittently under administrative control.,'1\/IILLSTONE

-UNIT 3 13/4 7-15 Amendment No. 2., 4-8+--, 24 9, 24-2. 243 PLANT SYSTEMS 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION ACTION: (Continued)

e. With both Control Room Emergency Air Filtration Systems inoperable, or with the OPERABLE Control Room Emergency Air Filtration System required to be in the emergency mode by ACTION d. not capable of being powered by an OPERABLE emergency power source, or with one or more Control Room Emergency Air Filtration System Trains inoperable due toan inoperable CRE boundary, immediately suspend the movement of recently irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS 4.7.7 Each Control Room Emergency Air Filtration System 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 95°F;b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying a system flow rate of 1,120 cfm +/- 20% and that the system operates for at least 10 continuous hours with the heaters operating;

c. At least once per 24 months or following painting, fire, or chemical release in any ventilation zone communicating with the system by: 1) Verifying that the system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Position C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revisions 2, March 1978,* and the system flow rate is 1,120 cfm +/- 20%;2) Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample 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 or equal to 2.5% when tested in accordance with ASTM D3803-89 at a temperature of 30'C (86°F), a relative humidity of 70%, and a face velocity of 54 ft/min; and 3) Verifying a system flow rate of 1,120 cfm + 20% during system operation when tested in accordance with ANSI N510-1980.

MILLSTONE

-UNIT 3 3/4 7-16 Amendment No. -2,4-24,4-8+,J484,40, 206, 23-7, 243 PLANT SYSTEMS 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

d. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample 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 or equal to 2.5%when tested in accordance with ASTM D3803-89 at a temperature of 30'C (86°F), and a relative humidity of 70%, and a face velocity of 54 ft/min.e. At least once per 24 months by;1) Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks .is less than 6.75 inches Water Gauge while operating the system at a flow rate of 1,120 cfm +/- 20%;2) Deleted 3) Verifying that the heaters dissipate 9.4 +/-1 kW when tested in accordance with ANSI N510-1980.

f. After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a DOP test aerosol while operating the system at a flow rate of 1120 cfm +/- 20%; and g. After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 fora halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 1120 cfm +/- 20%.h. By performance of CRE unfiltered air inleakage testing in accordance with the CRE Habitability Program at a frequency in accordance with the CRE Habitability Program.* ANSI N510-1980 shall be used in place of ANSI N510-1975 referenced in Regulatory Guide 1.52, Revision 2, March 1978.MILLSTONE

-UNIT 3 3/4 7-1!7 Amendment No. 2, 4-2-3, 84, 2-03, 220, 243 ELECTRICAL POWER SYSTEMS D. C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, one train (A or B) of batteries and their associated full capacity chargers shall be OPERABLE: a. Train -"A" consisting of: 1) Battery Bank 30 1A-I and a full capacity battery charger, and 2) Battery Bank 301A-2 and a full capacity battery charger.OR b. Train -"B" consisting of: 1) Battery Bank 301B-1 and a full capacity battery charger, and 2) Battery Bank 301B-2 and a full capacity battery charger.APPLICABILITY:

MODES 5 and 6.ACTION: With the required train inoperable, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity additions that could result in loss of required SDM or boron concentration, movement of recently irradiated fuel assemblies; crane operation with loads over the fuel storage pool, or operation with a potential for draining the reactor vessel; initiate corrective action to restore the required train to OPERABLE status as soon as possible.SURVEILLANCE REQUIREMENTS 4.8.2.2 The above required train shall be demonstrated OPERABLE in accordance with Specification 4.8.2.1.I MILLSTONE

-UNIT I 3/4 8-15 Amendment No. 4-9, 64, -1"0, 4-46, 230, 243 ELECTRICAL POWER SYSTEMS ONSITE POWER DISTRIBUTION SHUTDOWN LIMITING CONDITION FOR OPERATION (Continued)

4) Two 125 volt DC Busses consisting of: a) Bus #3011B-1 energized from Battery Bank #30 1B-1, and b) Bus #301B-2 energized from Battery Bank #301B-2.APPLICABILITY:

MODES 5 and 6.ACTION: With any of the above required electrical busses not energized in the required manner, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity additions that could result in loss of required SDM or boron concentration, movement of recently irradiated fuel assemblies, crane operation with loads over the fuel storage pool, or operations with a potential for draining the reactor vessel, initiate corrective action to energize the required electrical busses in the specified manner as soon as possible.SURVEILLANCE REQUIREMENTS 4.8.3.2 The specified busses shall be determined energized in the required manner at least once per 7 days by verifying correct breaker alignment and indicated voltage on the busses.MILLSTONE

-UNIT 3 3/4 8-18Sa Amendment No. 4-46, 2-30, 243 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.e. Provisions for monitoring operational primary to secondary LEAKAGE.h. 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 Ventilation System (CREVs), 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. I 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.The following are exceptions to Sections C. I and C.2 of Regulatory Guide 1.197, Revision 0: I. Appropriate application of ASTM E741 shall include the ability to take minor exceptions to the test methodology.

These exceptions shall be documented in the test report, and 2. Vulnerability assessments for radiological, hazardous chemical and smoke, and emergency ventilation system testing were completed as documented in the UFSAR and other licensing basis documents.

The exceptions to the Regulatory Guides (RG) referenced in RG 1.196 (i.e., RG 1.52, RG 1. 78, and RG MILLSTONE

-UNIT 3 6-17c Amendment No. 69, +86, 4-2,, 2-3-3, 243 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

1. 183), which were considered in completing the vulnerability assessments, are documented in the UFSAR/current licensing basis. Compliance with these RGs is consistent with the current licensing basis as described in the UFSAR and other licensing basis documents.

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 CREVs, operating at the flow rate required by the Surveillance Requirements, at a Frequency of 48 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 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.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.

6.8.5 Written

procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REMODCM.6.8.6 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of Specification

6.8.5 above

shallbe reviewed by an individual (other than the author) from the organization responsible for the REMP and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the organization responsible for the REMP, within 14 days of implementation.

6.9 REPORTING

REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U.S. Nuclear Regulatory MILLSTONE

-UNIT 3 6-17d Amendment No. 24b June 13, 2005 ADMINISTRATIVE CONTROLS Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident Inspector, unless otherwise noted.STARTUP REPORT 6.9. 1.1 A summary report of plant startup and power escalation testing shall be submitted following:

(1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, -thermal, or hydraulic performance of the unit.The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS*6.9.1.2 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted in accordance with 10 CFR 50.4.6.9.1.2a. Deleted 6.9.1.2b.

The results of specific activity analyses in which the reactor coolant exceeded the limits of Specification 3.4.8. The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radioiodinfe performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration (PiCi/gm)and one other radioiodine isotope concentration

([tCi/gm) as a function of time for the* A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.MILLSTONE

-UNIT 3 6-18 Amendment No. 69, 2-L--, 2-14, 2 43