ML033460233

Attachments to Ltr Correction of License and Technical Specifications for Arkansas Nuclear One Unit 2

ML033460233
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/11/2003
From:	Alexion T NRC/NRR/DLPM/LPD4
To:	Forbes J Entergy Operations
References
Download: ML033460233 (45)

Text

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ENCLOSURE 1 CORRECTIONS TO LICENSE AND TECHNICAL SPECIFICATION PAGES BASED ON NRC STAFF REVIEW OF THE LICENSEE'S RECORDS ARKANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-368 Replace the following pages of the operating license with the attached revised pages.

Remove Insert Amendment/Correction Ltr Reason Cover Itr NRC letter dated 07/18/78. Completeness (for reference).

6 6 Amendment 102 Heading missing.

7 7 Amendment 102 Amd. 102 not indicated, and also to remove "No." on line 2.C.(3)(k).

9 9 Amendment 106 Amd. 106 not indicated, capital letters missing in attachments clause, and wrong date of issuance.

Attach. 1 Amendment 10 Part of License.

Attach. 2 Original License (07/18/78) Part of License.

Attach. 2 Amendment 1 (09/01/78) Part of License.

Attach. 2 Amendment 7 (12/01/78) Part of License.

Replace the following pages of Appendix A Technical Specifications with the attached revised pages.

Remove Insert Amendment/Correction Ltr Reason

--- 1st coverpage Original License Completeness (for reference).

--- 2nd cover page Original License Completeness.

3/4 1-23 3/4 1-23 Correction Ltr 10/24/95 Need letter date on the TS page.

3/4 2-3 3/4 2-3 Correction Ltr 10/24/95 Need letter date on the TS page.

314 4-13 3/4 4-13 Amendment 231 Delete comma after 3.4.6.1 a text.

3/4 7-23b 3/4 7-23b Amendment 62 Add s in replacements (last sent.).

3/4 8-1 a 3/4 8-1 a Amendment 249 Delete 2nd line of heading.

3/4 8-5 3/4 8-5 Amendment 149 Change Surveillance Requirements to Surveillance Requirement.

3/4 9-1 3/4 9-1 Correction Ltr 10/24/95 Need letter date on the TS page.

3/4 9-7 3/4 9-7 Correction Ltr 10/24/95 Need letter date on the TS page.

3/4 10-1 3/4 10-1 Correction Ltr 10/24/95 Need letter date on the TS page.

3/4 10-2 3/4 10-2 Correction Ltr 10/24/95 Need letter date on the TS page.

6-2 6-2 Amendment 209 Item g has no period after 1st sent.

Replace the following pages of Appendix B Technical Specifications with the attached revised pages.

Remove Insert Amendment/Correction Ltr Reason 1st cover page Original License Completeness (for reference).

2nd cover 2nd cover Amendment 96 Title is slightly different.

page page

':ENSE,

AUTNHORT Wpy NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 JUL18 7 Docket No. 50-368 DO NOT REMOVE Arkansas Power and Light Company ATTN: Mr. William Cavanaugh III Executive Director of Generation and Construction P. 0. Box 551 Little Rock, Arkansas 72203 Gentlemen:

SUBJECT:

ISSUANCE OF FACLITY OPERATING LICENSE NO. NPF-6 (ARKANSAS NUCLEAR ONE, UNIT 2)

The Nuclear Regulatory Commission (the Commission) has issued the enclosed Facility Operating License No. NPF-6 including Technical Specifications (Appendices A and B) to the Arkansas Power and Light Company for Arkansas Nuclear One - Unit 2 (ANO-2) located in Pope County, Arkansas. License No. NPF-6 authorizes the Arkansas Power and Light Company to load nuclear fuel into Arkansas Nuclear One - Unit 2 and maintain it in a cold shutdown condition (Operational Mode 5) in accordance with Technical Specifications (Appendices A and B) of the license. A copy of the Notice of Issuance and the supporting Safety Evaluation for issuance of a fuel load license are enclosed.

Two signed copies of Amendment No. 6 to Indemnity Agreement B-65 are enclosed for your review and acceptance. Please sign and return one copy to the Director, Division of Project Management.

rely, Roger S. Bocd tor Division of ProjeE Office of Nuclear eactor Regulation

Enclosures:

1. Facility Operating License No. NPF-6

2. Notice of Issuance

3. Safety Evaluation for the Issuance of a Fuel Load License

4. Amendment No. 6 to Indemnity Agreement B-65 ccs w/encls:

See page 2 i.

Implementation Dates for Proposed Modifications (Continued)

Applicable Section of NUREG-0223 Date 3.9 Protection of Redundant Cables in the Lower South Electrical Penetratiorn Room (2111-T) September 30, 1978 3.10 Protection of Safe Shutdown Cables in the upper South Piping Penetration Room (2084-DD) September 30,.1978 3.11 Protection of Redundant Reactor Protection

• System Cables (2136-I) * **

3.12 Fire Dampers September 30, 1978 3.13 Portable Extinguisher for the Control Room (2199-J) November 15, 1978 3.14 Smoke Detectors 3.15 Manual Hose Stations (2055-JJ, 2084-DD, Containment, Elev. 317' of Auxiliary Building 3.16 Portable Smoke Exhaust Equipment December 1, 1978 3.17 Emergency Lighting December 1, 1976 3.18 Reactor Coolant Pump Oil Collection System -

3.19 Control of Fire Doors March 31, 1979 3.20 Administrative Control Changes December 1, 1978 (Numbers in parer.theses refer to fire zone designations in the AP&L fire hazards analysis.)

• Prior to startup following the first regularly scheduled refueling outage.

• • Technical Specifications covering these items should be proposed not later than 90 days prior to implementation.

2.C.(3)(f) Deleted per Amendment 24, 6/19/81.

2.C.(3)(g) Deleted per Amendment 93, 4/25/89.

2.C.(3)(h) Deleted per Amendment 29, (3/4/82) and its correction letter, (3/15/82).

- 7 (i) Containment Radiation Monitor AP&L shall, prior to July 31, 1980 submit for Commission review and approval documentation which establishes the adequacy of the qualifications of the containment radiation monitors located inside the containment and shall complete the installation and testing of these instruments to demonstrate that they meet the operability requirements of Technical Specifi-cation No. 3.3.3.6.

2.C.(3)(j) Deleted per Amendment 7, 12/1/78.

2.C.(3)(k) Deleted per Amendment 12, 6/12/79 and Amendment 31, 5/12/82.

2.C.(3)(1) Deleted per Amendment 24, 619/81.

2.C.(3)(m) Deleted per Amendment 12, 6/12/79.

2.C.(3)(n) Deleted per Amendment 7, 12/1/78.

2.C.(3)(o) Deleted per Amendment 7, 12/1/78.

(p) Secondary Water Chemistry Monitorin5 pA. Ia EOI shall implement a secondary water chemistry monitoring program using the overall plant administrative procedure "Steam Generator ater Chemistry Monitoring, Unit II", to minimize steam generator tube degradation.

The program shall be defined in specific plant procedures and shall include:

1. Identification of sampling schedule for the critical parameters arid control points for these parameters;

2. Identification of the procedures used to measure the values of the critical parameters;

3. Identification of process sampling points;

4. Procedure for the recording and management of data;

5. Procedures defining corrective actions for off control point chemistry conditions; and

6. A procedure identifying the authority responsible for the interpretation of te data, and the sequence and timing of administrative events required to initiate corrective action.

E. This license is subject to the following additional condition for the protection of the environment:

Before engaging in additional construction or operational activities which may result in an environmental impact that A ,7 was not evaluated by the Commission, EOI will prepare and record an environmental evaluation for such activity. When the evaluation indicates that such activity ay result in a significant adverse environmental impact that was not evaluated, or that is significantly greater than that evaluated, in the Final Environmental Statement (UREG-0254) or any addendum thereto, ,,

EOI shall provide a written evaluation of such activities and obtain prior approval fom the Director, Office of Nuclear Reactor Regulation.

F. This license is effective as of the date of issuance and shall expire at midnight, July 17, 2018. 7--

FOR THE NUCLEAR REGULATORY COMMISSIONM Original signed by D. B. Vassallo for Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactcr Regulation Attachments:

Preoperational Tests, Startup Tests and Other Items Which Must Be Completed By the Indicated Operational Mode Date of Issuance: September 1, 1978

Th NSE AULOhnMRITY FhLE -

ATTACHMENT 1 TO LICENSE AMENDMENT NO. 10 FACILITY OPERATING LICENSE NO. NPF 6 DOCKET NO. 50-368 The requirements of Technical Specification 3.6.1.6 requiring that the 54 inch purge supply and exhaust system isolation valves shall be closed during Modes 1, 2, 3 and 4 is temporarily suspended for Modes 3 and 4 only pursuant to the stipulation as stated below.

The licensee is permitted a one-time thirty-hour period for completing two eight-hour containment purge operations. This thirty-hour period is permitted in Operating Modes 3 and 4 only.

During the thirty-hour purging period the licensee shall:

(1) Sample reactor coolant activity prior to the two eight-hour purging operations and at four (4) hours into the two eight-hour purging operations to verify that the specific activity of Iodine-131 is not greater than 0.0001 micro Curie per gram.

(2) Until such time as the two eight-hour purging operations are complete, an hourly check shall be maintained with the process radiation monitor in the Chemical Volume Control System to verify that the Iodine-131 activity of the reactor coolant system is not greater than 0.0001 micro Curie per gram.

(3) During the two eight-hour purging operations, the purge supply and exhaust valves shall not be opened more than 30 degrees from the fully closed position.

ATTACHMENT 2 TO LICENSE NPF-6 J r t ' d Preoperational Tests, Startup Tests, and 1, Other Items Which Must be Completed Prior to Loading Fuel V ' ,

This attachment identifies certain preoperational tests, startup tetes and other items which must be completed to the Commission's satisfaction , ,

prior to proceeding to Operational Mode 6 (Fuel Loading). Arkansas Powe -

& Light Company shall not proceed into Operational Mode 6 without prior ACE -

written authorization from the Commission.

1. Completion of installation of excore nuclear instrumentation.

2. Completion of preoperational test 2.600.12A, "Special Tests /

of Boration/Dilution System."

3. Resolution of questions on installation of fire barriers at the ends of conduit rather than at wall penetrations.

ATTACHMENT 2 TO LICENSE NPF-6 Preoperational Tests, Startup Tests, and Other Items Which Must be Completed Prior to Proceeding To Succeeding Operational Modes This attachment identifies certain preoperational. tests, startup tests, and other items which must be completed to the Commission's satisfaction prior to proceeding to certain specified Operational Modes. Arkansas Power & Light Company shall not proceed beyond the authorized Operational Modes without prior written authorization from the Comnission.

A. The following items must be completed prior to proceeding to Operational Mode 2 (Initial Criticality).

1. Completion of significant startup punchlist items which dffect the operability of the following:

- Sampling System

- Auxiliary Building H&V (1)

- Emergency Feedwater System (2)

- Plant Protective System (4)

- Reactor Coolant System (3)

- Waste Gas System (1)

- Area Radiation Monitors (2)

- Air & Gas Radiation Monitors (6)

- Safety Injection System (2)

- Liquid Radwaste System (4)

2. Completion of the following Preoperational Tests:

2.083.01 Main Steam Supply and Safety Relief Valves

3. Closeout of outstanding Startup Program Test Deficiencies.

4. Approval and issuance of the following procedure:

2.800.01 App. U Unit Load Transient Test

5. Resolution of main feedwater line break potential ithin the containment piping penetration room.

TF i 978

6. Resolution of the following items relating to radiation protection.

a. Complete installation and calibration of health physics monitoring equipment.

b. Complete calibration of area radiation monitors.

c. Complete calibration of process radiation monitors.

7. Complete hanger installation.

8. Complete installation of independent DC power supplies to the series containment penetration breakers.

9. Resolution of discrepancies identified in the Facility Operating Procedures.

10. Resolution of test deficiencies relating to the failure of the Hydrogen Purge System to meet FSAR acceptance criterion. These deficiencies include:

- Failure of the filters to pass the Freon-112 test.

- Failure of the system to meet specified flow rate.

11. Resolution of LPSI Pump Motor Failure.

12. Resolution of loose part in safety injection system.

B. The following items must be completed prior to proceeding to Operational Mode 1 (Power Operation).

1. Completion of significant startup punchlist items which affect the operability of the following:

- Control Room HV (1)

- Miscellaneous H&V (1)

- Feedwater System (1)

- Steam Generators (2)

- Fuel Pool and Auxiliaries (8)

- Waste Gas System (1)

- Solid Radiation Waste System (4)

- Main Steam System (2)

2. Resolution of the following outstanding operations punchlist items:

- Instrumentation in place for CECEC Code verification

. -6 ATTACHMENT 2 TO AMENDMENT NO. 7 LICENSE NO. NPF-6 Preoperational Tests, Startup Tests, and Other Items Which Must be Completed Prior to Proceeding To Succeeding Operational Modes This attachment identifies certain preoperational tests, startup tests, and other items which must be completed to the Commission's satisfaction prior to proceeding to certain specified Operational lodes. Arkansas

~> Power & Light Company shall not proceed beyond the authorized Operational Modes without prior written authorization from the Commission.

A. The following items must be completed prior to proceeding to Operational Mode 2 (Initial Criticality).

1. Completion of significant startup punchlist items which affect the operability of the following:

- Sampling System

- Auxiliary Building H&V (1)

- Emergency Feedwater System (2)

- Plant Protective System (4)

Pa l - Reactor Coolant System (3)

- taste Gas System (1)

- Area Radiation Monitors (2)

- Air & Gas Radiation Monitors (6)

- Safety Injection System (2)

'V Liquid Radwaste System (4)

2. Completion of the following Preoperational Tests:

2.083.01 Main Steam Supply and Safety Relief Valves

3. Closeout of outstanding Startup Program Test Deficiencies.

4. Approval and issuance of the following procedure:

2.800.01 App. U Unit Load Transient Test

5. Resolution of main feedwater line break potential within the containment piping penetration room.

S J \

-' T

-^N 4 T

6. Resolution of the following items relating to radiation protection.

a. Complete installation and calibration of health physics monitoring equipment.

b. Complete calibration of area radiation monitors.

c. Complete calibration of process radiation monitors.

7. Complete hanger installation.

8. Complete installation of independent DC power supplies to the series containment penetration breakers.

9. Resolution of discrepancies identified in the Facility Operating Procedures.

10. Resolution of test deficiencies relating to the failure of the Hydroqen Purge System to meet FSAR acceptance criterion. These deficiencies include:

- Failure of the filters to pass the Freon-112 test.

- Failure of the system to meet specified flow rate.

11. Resolution of LPSI Pump Motor Failure.

12. Resolution of loose part in safety injection system.

13. Conformance to GDC-17 offsite power deficiencies.

14. Resolution of inverter deficiencies.

15. Chloride swipes within containment.

15. Resolution of Diesel Generator No. 2 failure.

17. Resolution of CRD-58 failure.

The following items must be completed prior to proceeding to Operational Mode 1 (Power Operation).

1. Completion of significant startup punchlist items which affect the operability of the following: .

I -

3--

- Control Room HV (1)

- Miscellaneous M&V (1)

- Feedwater System (1)

- Steam Generators (2)

- Fuel Pool and Auxiliaries (8)

- Waste Gas System (1)

- Solid Radiation Waste System (4)

- Main Steam System (2)

2. Resolution of the following outstanding operations punchlist items:

- Instrumentation in place for CECEC Code verification.

. S .

LICENSE AUTHORITY FILE COPt ARkANSAS NUCLEARZONE UNIT 2 DO NOT r- OvE N r- E l PE TECHNICAL PCCIFHCATION5 APPENDIX "A" TO LICENSE NO. N-6 JULY 18, 1978 ISUCD BY THC UNITCD STATCS NUCLCAR REGULATORY COMMISION

NUREG 0336 LICEN'5E AU I hUii 1*.Y I-ILL QOP._y P.7 -

p 79

/ /tL. A.

DO NOT REOVE ARKANSAS NUCLEAR ONE UNIT 2 TECHNICAL SPECIFICATIONS APPENDIX "A" TO LICENSE NO. NPF-6

R£ACTIVTIY CONTROL SYSTDMS CCA DROP TME LIMITING CONDITION rOR OPERATION 3.1.3.4 The individual CA drop time, from a fully withdrawn position, shall be S 3.5 seconds and the arithmetic average of the CA drop times of all CAs, from a fully withdrawn position, hall be 3.2 seconds from when the electrical power is interrupted to the CZA drive mechanisms until the CAs reach their 90 percent insertion positions with:

a. Tavg M2Ser, and

b. All reactor coolant pups operating.

APPLICABILTY: MODES I and 2.

ACTION:

a. With the CEA drop times determined to exceed either of the above limits, restore the CEA drop times to within the above limits prior to proceeding to MODE 1 or 2.

b. With the CEA drop times within limits but determined at less than full reactor coolant flow, operation may proceed provided THERML POWER is restricted to less than or equal to the maximum THEMKL POWER level allowable for the reactor coolant pump combination operating at the time of CEA drop time determination.

SURVEILLANCE REQUIIRE.nS 4.1.3.4 The CEA drop time of all CEAs shall be demonstrated through measurement prior to reactor criticality:

a. For all CAs following each removal of the reactor vessel head,

b. ror specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and C. At least onee per 19 months.

ARKANSAS - UNIT 2 3/4 1-23 Amendment No. 84,#4,45,169 C0r~t QeJWL~L f /O- c/<

POWER DISTRIBUTION LIMITS AZIMUTHAL POWER - TS LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL'POWER TILT (Tq) shall be less than or equal to the AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs).

APPLICABILITY: MODE 1 above 201 of RATED THERMAL POWER.*

ACTION:

a. With the measured AZIMUTHAL POWER TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the CPCs but within the limit specified in the CORE OPERATING LIMITS REPORT$ within two hours either correct the power tilt or adjust the AZIMUTHAL

-POWER TILT Allowance used in the CPCs to greater than or equal to the measured value.

b. With the measured AZIMUTHAL POWER TILT determined to exceed the limit specified in the CORE OPERATING LIMITS REPORT:

1. Due to misalignment of a CEA, within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS)

(when COLSS is being used to monitor the core power distribution per Specifications 4.2.1 and 4.2.4) is detecting the CEA misalignment.

2. Verify that the AZIMUTHAL POWER TILT is within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Linear Power Level - High trip setpoints to < 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95% or greater RATED THERMAL POWER.

• See Special Test Exception 3.10.2.

ARXANSAS - UNIT 2 3/4 2-3 Amendment No. 24,a&,169

'tDR~~~~~~ Qw - lo- / o 4-4

REACTOR COOLANT SYSTEM 3/4.4.6 REKCTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System leakage detection instrumentation shall be OPERABLE:

a. One containment sump level monitor

b. One containment atmosphere particulate radioactivity monitor, and

c. One containment atmosphere gaseous radioactivity monitor.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With one or more containment atmosphere radioactivity monitor(s) inoperable, operation may continue for up to 30 days for each inoperable monitor provided:

1. grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or

2. a Reactor Coolant System water inventory balance is performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with Surveillance Requirement 4.4.6.2.1.a;*

otherwise, 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 the containment sump level monitor inoperable, operation may continue for up to 30 days provided a Reactor Coolant System water inventory balance is performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with Surveillance Requirement 4.4.6.2.1.a;* otherwise, 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 />.

c. With the containment sump level monitor inoperable and one containment atmosphere radioactivity monitor inoperable, operation may continue for up to 30 days for each inoperable monitor provided a Reactor Coolant System water inventory balance is performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with Surveillance Requirement 4.4.6.2.1.a;* otherwise, 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 />.

d. The provisions of Specification 3.0.4 are not applicable.

• Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state conditions.

ARKANSAS - UNIT 2 3/4 4-13 Amendment No. 231 L., A

PLANT SYSTEMS

. SURVEILLANCE REQUIREMENTS (Continued)

-If any snubber selected for functional testing either fails to activate or falls to move, i.e., frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be evaluated in a manner to ensure their OPERABILITY. This require-ment shall be independent of the requirements stated in Specifica-tion 4.7.8.d for snubbers not meeting the functional test acceptance criteria.

g. Preservice Testing of Repaired, Replacement and New Snubbers Preservice operability testing shall be performed on repaired, replacement or new snubbers prior to installation. Testing may be at the manufacturer's facility. The testing shall verify the functional test acceptance criteria in 4.7.8.e.

In addition, a preservice inspection shall be performed on each repaired, replacement or new snubber and shall verify that:

1) There are no visible signs of damage or impaited operability as a result of storage, handling or installation;

2) The snubber load rating, location, orientation, position setting and configuration (attachments, extensions, etc.),

are in accordance with design;

3) Adequate swing clearance is provided to allow snubber movement;

4) If applicable, fluid is at the recommended level and fluid is not leaking from the snubber system;

5) Structural connections such as pins, bearings, studs, fasteners and other connecting hardware such.as lock nuts, tabs, fire, and cotter pins are installed correctly.

h. Snubber Seal Replacement Program The seal service life of hydraulic snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The expected service life for the various seals, seal materials, and applications shall be determined and established based on engineering information and the seals shall be replaced so that the expected service life will not be exceeded during a period when the snubber is required to be OPERABLE. The seal replacements shall be documented and the documentation shall be retained in accordance with Specification 6.10.2.

ARKANSAS-UNIT 2 3/4 7-23b Amendment No. 62

ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES LIMITING CONDITION FOR OPERATION

b. With one diesel generator of the above required A.C. electrical power source inoperable, perform the following:

1. Demonstrate the OPERABILITY of both the offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, and

2. Demonstrate the OPERABILITY of the remaining OPERABLE diesel generator within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by:

i. Determining the OPERABLE diesel generator Is not Inoperable due to a common cause failure, or ii. Perform Surveillance Requirement 4.8.1.1.2.a.4 unless:

a. The remaining diesel generator is currently in operation, or

b. The remaining diesel generator has been demonstrated OPERABLE within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

3. Restore the diesel generator to OPERABLE status within 14 days (See Note 1) 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 />.

Note 1 - If the Alternate A.C. Diesel Generator (AACDG) is determined to be Inoperable during this period, then a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> restoration period Is applicable until either the AACDG or the diesel generator is returned to operable status (not to exceed 14 days from the Initial diesel generator noperability).

ARKANSAS - UNIT 2 3/4 8-1a Amendment No. 249 I

ELECTRICAL POWER SYSTEMS SHUTDOWN T.TMTTTNG (nnTTTnfl np nPEPATON 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. One circuit between the offsite transmission network and the onsite Class E distribution system, and

b. One diesel generator with:

1. A day fuel tank containing a minimum volume of 280 gallons of fuel (equivalent to 50% of total tank volume),

2. A fuel storage system containing a minimum volume of 22,500 gallons of fuel (equivalent to 100% of total tank volume),

and

3. A fuel transfer pump.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVETLLANCE REQUTREMENT 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance

-Fequirements of 4.8.1.1.1 and 4.8.1.1.2 except for Requirement I 4.8.1.1.2a.5.

ARKANSAS - UNIT 2 3/4 8-5 Amendment No. 149 I'll r -.

3/4.9 REFUELING OPERATIONS BORON CONCENTR.ATiON LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head unbolted or removed, the boron concentration of the reactor coolant and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of following reactivity conditions is set:

a. Either a Xff of 0.95 or less, which ncludes

• 1 Ak/k conservative allowance for uncertainties, or

b. A boron concentration of 22500 ppm, which includes a 50 ppm, conservative allowance for uncertainties.

APPLICABILITY: MODE .

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations Involving CORE ALTERATIONS or positive reactivity changes and nitiate and continue boration at 2 40 gpm of Xffe is reduced to 0.95 or the boron concentration is restored to 2 2500 ppm, whichever is the more restrictive. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4... Th moersrcieoh bv w eciiycniin hl 4.9.2.2 The more restrictive of the bove two reactivity onditions hall be determined prior to:

a. Removing or unbolting the reactor vessel head, and

b. Withdrawal of any CA in excess of 3 feet from its fully nserted position within the reactor pressure vessel.

4.9.1.2 The boron concentration of the reactor coolant and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• The reactor shall be maintained in ODE 6 when the reactor vessel head in unbolted or removed.

ARKANSAS - UNIT 2 3/4 9-1 Amendment No. 4m,169 0 @ p-04W -( D -S

REMELZNG OPEATZONS ZF`JUELINGmxCmrNE OPESABILITY LflTING CONDITION rOR OPLRATIOh 3.9.6 he refueling machine hall be used for ovement of fuel ssemblies and shall be OPERABLE with:

a. A zinimum capacity of 3750 pounds,

b. An overload cut off limit of 100 pounds plus the combined weight of one fuel assembly, one C, and the grapple ln the fuel only" region, and

c. An overload cut off limit of S 00 pounds plum the combined weight of one fuel assembly, one CEA, the grapple, and the hoiut box in the 'fuel plus hoist box' region.

APPLICABILITY: During movement of CEAU or fuel assemblies within the reactor pressure vessel.

ACTION :

With the requirements for refueling machine OPERABSLITY not satisfied, suspend its use from operations involving the movement of CEAs and fuel assemblies within the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.6 The refueling machine shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of movement of fuel assemblies within the, reactor pressure vessel by performing a load test of at least 3750 pounds and demonstrating automatic load cut offs when the crane loads exceed 100 pounds plus the applicable loads.

3/4 9-7 Amendment No. 4 9 69 ARKANSAS - UNIT 2

,fi QjAL 104-3 9-4I

3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN )9RGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth and shutdown margin provided reactivity equivalent to at least the highest estimated C worth is available for trip insertion from OPERABLE CA(s).

APPLICABILITY: MODE 2.

ACTION:

a. With any CEA not fully inserted and with less than the above reactivity equivalent available for trip nsertion, Jimediately initiate and continue boration at 40 gpm of 2500 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

b. With all CEAs inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at 40 gpm of 2500 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREENTS 4.10.1.1 The position of each CEA required either partially or fully withdrawn hall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4.10.1.2 Each CEEA not fully inserted shall be demonstrated capable of full insertion when tzrpped from at least the 50% withdrawn position within 7 days prior to red ducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

ARXANSAS - UNIT 2 3/4 10-1 Amendment No. 4*,#,169 t %10-X-<0

SPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution limits of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7 and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 may be suspended during the performance of PHYSICS TESTS provided:

a. The THERMAL POWER is restricted to the test power plateau which shall not exceed 5% of RATED THERMAL POWER, and

b. The linear eat rate limit shall be maintained by either:

1. Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on linear heat rate (when COLSS is in service) or

2. Operating within the region of acceptable operation as specified in the CORE OPERATING LIMITS REPORT using any operable CPC channel (when COLSS is out of service.)

APPLICABILITY: During startup and PHYSICS TESTS.

ACTION:

With any of the above limits being exceeded while any of the above requirements are uspended, either:

a. Reduce THERMAL POWER sufficiently to satisfy the requirements of the above Specification, or

b. -Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which any of the above requirements are suspended and shall be verified to be within the test power plateau.

4.10.2.2 The linear heat rate shall be determined to be within its limits during PHYSICS TESTS above 5 of RATED THERMAL POWER in which any of the above requirements are suspended.

ARKANSAS - UNIT 2 3/4 10-2 Amendment No. 43,&,IO169 Ce~ode C

C. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor!

e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f. In MODES 1, 2, 3, or 4, an individual shall provide advisory technical support for the unit operations shift supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Conmission Policy on Engineering Expertise on Shift.

g. Administrative control shall be established to limit the amount of overtime worked by plant staff performing safety-related functions These administrative controls shall be in accordance with the guidance provided by the NRC Policy Statement on working hours (Generic Letter No. 82-12).

h. The operations manager or the assistant operations manager shall hold I a senior reactor operator license.

ARKANSAS - UNIT 2 6-2 Ainendment No. {,GGS;,G 44,a4,a44, aa,209 AU& 2 6 -z3

. I .

L!CENSE AUTHORITy FILE Q~p, ARKANSAS NUCLEAR ONE UNIT NO. 2 DO NOT REMOVL TECHNICAL 5PCHFICATON APPCNDI "B" TO LICCr4 C NO. NPf-6 ISUCD BY THE UNITED TATCS NUCLEAR REGULATORY COMMI5ION

ENVIRONMENTAL TECHNICAL SPECIFICATIONS ARKANSAS NUCLEAR ONE UNIT NO. 2 ARKANSAS POWER AND LIGHT COMPANY

- . JULY 1978 Appendix B to Operating License NPF-6 has been eliminated in its entirety by this amendment. See Amendment Nos. 40, 47, and 68.

Amendment.No. 96 JUN 1 1989

ENCLOSURE 2

, tR EG,

- Q t .EO(, UNITED STATES

'A NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 December 14, 1989 Docket Nos. 50-313 and 50-368 Mr. T. Gene Campbell Vice President, Nuclear Arkansas Power and Light Company P. 0. Box 551 Little Rock, Arkansas 72203

SUBJECT:

ISSUANCE OF AMENDMENT NOS. 128 AND 102 TO FACILITY OPERATING LICENSE NOS. DPR-51 AND NPF ARKANSAS NUCLEAR ONE, UNITS I AND 2 (TAC NOS. 68435 AND 68436)

The Conwission has issued the enclosed Amendment Nos.128 andlO2 to Facility Operating License Ncs. DPR-51 and NPF-6 for the Arkansas Nuclear One, Unit Nos. 1 and 2 (ANO-1 and ANO-2). The amendrient consists of chances to the License Conditions in response to your application dated J1uly 1, 1988 as supplemented by letter dated August 15, 1989.

The amendments change and add License Conditions to reflect the transfer of cperatons and maintenance of the Arkansas Nuclear Oe, Unit Ns. I and 2 to Entergy Operations, Inc. (EOI). Arkansas Power and Light Company (AP&L) will ensain as the wner of the facilities.

We have reviewed the operation agreement between SERI (now E) and AP&L and have determined that it is not appropriate to require it by a license cridi-ticn. A&L and EOI are joint licensees under the facility operating license coiditicn, each responsible for specific areas and jointly responsible for regulatory compliance and response. The operating areement between AP&L and COI will not circumvent these responsibilities. Finally, since EOI is to be operator of the plants, we intend to communicate on most all matters with EOI.

However, EI is expected to communicate with APAL to provide data, information, and other support, as may be necessary, to enable AP&L to satisfactorily discharge any responsibilities t may have as owner of the plants, with regard to maintaining regulatory compliance.

A copy of the Safety Evaluation supporting the amendments is also enclosed.

Notice of Issuance will be Included in the Commission's next biweekly Federal Register notice.

r

- s9122o0405 9121 3 FpDR P DoCK 0500031 ~~~Ppc i

IMr. T. Gene Campbell Two copies of Amendment No. 11 to Indemnity Agreement No. B-65 which covers the activities authorized under License Nos. DPR-31 and PF-6 are also enclosed. Please countersign all copies and return one signed copy of Amendment No. 11 to this office.

Sincerely,

/5]

Dennis N. Crutchfield, Associate Director for Special Projects Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No.128 to DPR-51

2. Amendment No. 102 to NPF-6

3. Safety Evaluation

4. Amendment No. 11 to Indemnity Agreement No. B-65 cc w/enclosures:

See next page DISTRIBUTION:

Docket File JeMVD PNoonan ACRS (10) NRC PDR TMeek (4) CHarbuck (2) GPA/PA Local PDR Wanda Jones FHebdon ARM/LFMB PD4 Reading OGC-Rockville DHagan EJordan Plant File CPoslusny (2) FHebdon LTR NAME: ANO AMENDMENT SERI 1S PTSO /J 11nS PD4/ PD4/PI1 PD4/PM1t PD47PM PNoonet D iggk :bJ CHarbuyc CPoslusny CThomas 09X'89 ON/C/89 ,w II /89 G9/0 /89 09/ /89 to -D t0 R kvi1 le PD4/Dij FHebdd elId 0g/fg/89C I t-W/J/89 *&/J+/89 Subject to the insertion of a response to the antitrust comments received by the Staff once the response has received OGC concurrence.

°vUNITED

-0 STATES NUCLEAR REGULATORY COMMISSION 4 ,' t WASHINGTON, D. C.20555 July 6, 1990 Docket Nos. 50-313 and 50-368 Mr. Neil S. Carns Vice President, Nuclear Arkansas Nuclear One P. 0. Box 551 Russellville, Arkansas 72801

SUBJECT:

ISSUANCE OF AMENDMENT NOS.131 AND 106TO FACILITY OPERATING LICENSE NOS. DPR-51 AND NPF ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 (TAC NOS. 66575 AND 66557)

The Commission has issued the enclosed Amendment Nos. 131and 106to Facility Operating License Nos. DPR-51 and NPF-6 for the Arkansas Nuclear One, Units I and 2 (ANO-1&2). These amendments consist of changes to the Technical Specifications (TSs) in response to your applications dated October 30, 1987 as supplemented on September 27, 1989 for Units I and 2 and January 29, 1990 for Unit 1 only.

The amendments change the expiration date for the Unit 1 Facility Operating License No. DPR-51 from December 6, 2008 to May 20, 2014, and change the expiration date for the Unit 2 Facility Operating License No. NPF-6 from December 6, 2012 to July 17, 2018.

'A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's next Bi-weekly Federal Register notice.

Sie Thomas W. Alexion, Project anager Project Directorate IV-1 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation Chester Poslusny, r., Project Manager Project Directorate IV-1 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No. 131 to DPR-51

2. Amendment No. 106 to NPF-6

3. Safety Evaluation cc w/enclosures:

See next page

MAR 3 0 1979 Docket No. 50-368 Mr. William Cavanaugh III Executive Director of Generation and Construction Arkansas Power & Light Company P. 0. Box 551 Little Rock, Arkansas 72203

SUBJECT:

ISSUANCE OF AMENDMENT NO. 10 TO FACILITY OPERATING LICENSE NO. NPF-6 FOR ARKANSAS NUCLEAR ONE, UNIT 2 By letted dated March 26, 1979, you requested that the requirements of the Arkansas Nuclear One, Unit 2 Technical Specification 3.6.1.6 be temporarily suspended for a one-time thirty-hour period to complete two eight-hour purging operations.

Facility Operating License NPF-6-is amended immediately, by making the following changes:

You are hereby permitted a one-time only thirty-hour period to complete two (2) eght-hour purging operations in Modes 4 and 3 only. The purge valves shall not be opened more than 30 degrees during the two eight-hour purging operations. As stipulated in this license amendment you shall perform the additional surveillance activities as delineated in your March 26, 1979 request for temporary suspension of Technical Sepci-fication 3.6.1.6.

We have determined that Amendment No. 10 does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact, and pursuant to 10 CFR Section 51.5(d)(4), that an environmen-tal impact appraisal need not be prepared in connection with the issuance of this amendment.

NRC ORM 318 (9-76) NRCM 0240

• U. a. OVZRNI4ENrPRINN oFFICES 1976-61"24

J-Mr. William Cavanaugh III MAR 3 0 1979 Copies of the license amendment, FEDERAL REGISTER Notice, and Safety Evaluation for this Technical Specification change are enclosed.

Sincerely, oriSlnal signeoab'7.

John F. Stolz, Chief Light Water Reactors Branch No. 1 Division of Project Management

Enclosures:

1. Amendment No. 10 to Facility Operating License o. NPF-6

2. FEDERAL REGISTER Notice

3. Safety Evaluation Supporting Amendment No. 9 to PF-6 cc: See page 3 DP__ __ __ DPM _OLWR#L ELD DM#DOR/STS1 SUMAM-- .EGHvlton:pcm LBEnqldA DBrinkmMr/ G JFStol VA7930 LM. /7Lt3/.2L._L. 9. 3I Jj9 03/ 2-r /79 3/3- ,79 _

NRC ORM 318 (9-76) NRCM 0240

• U.9*. 0VYRNKtCN- PRINT1NQ OrFIC91 1976-2"2

II SEP 1 1978 Docket No. 50-368 Arkansas Power and Liyht Company i ATTN: Mr. William Cavanaugh III Executive Director of Generation i and Construction I P. 0. Box 551 I

i Little Rock, Arkansas 72203 Gentlemen:

SUBJECT:

ISSUANCE OF AMENDMENT NO. 1 TO FACILITY OPERATING LICENSE NO. PF-6 (ARKANSAS NUCLEAR ONE, UNIT 2)

I The Nuclear Regulatory Comission has issued the enclosed Amendmient No. 1 to Facility Operating License No. PF-6 (enclosed) to the Arkansas Power and Light Company for the Arkansas uclear One - Unit 2 plant authorizing operation at 2815 megawatts thermal subject to the conditions I delineated therein. However, the operation of the facility is temporarily restricted to the sequence of operational odes described in Attachment I to the license until the preoperational tests, startup tests and other I

items noted in Attachment 1 are completed to the written satisfaction of the Commission. A cojy of the Notice of Issuance is also enclosed.

I The Corission's Office of Nuclear Reactor Regulation has also issued Supplement No. 2 to the Safety Evaluation Report. Two copies are.

enclosed for your information and use. ., *v -- .. .

The Commission has determined that te facility requires exemptions from i

certain requirerents of (1) Sections 50.55a(g)(2) and 50.55a(g)(4) of 10 CFR Part 50, (2) Appendices G and 1ito 10 CFR Part 50, and (3) Appendix J to 10 CFR Part 50. These exemptions are authorized y law and will not endanger life or property or the comnion defense and security and are I

otherwise in the public interest. These exemptions have, therefore, been i

i II *U°FNAM _lI- I DOATOW -r-.

NRC ORMS 38 9-76) NRCM 0240

• u. *. ovt^tmmcm- ^imrtm orricis i976o- s2"m

I SEP 1 1978 I

Arkansas Power and LIght Company I i

I granted. The Office of Nuclear Readtor Fegulation safety evaluations I supporting the granting of these exempti pns are enclosed.

i i

II Sincerely, LO" Sgned bv Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation

Enclosures:

1....Amendment No. I to Facility Operating License No. NPF-6

2. Federal Register Notice

3. Safety Evaluation Supporting Amendment No. 1 to NPF-6

4. Safety.:Eval.uations Supporting.

Exemptions

5. Supplement No. 2 to SER (NUREG-03Q8) ccs w/encls:

See page 2 I

I I

I

_~~~~~~~~~~Tr, -n.--MWYJ-e 1v-ff-- I rift

"-*d Jk I~X- ff brrtcru 1; LW 2EL l LWR'Y LWR P

• URNAIK*. n/red RMr in JStolz DBVassallo RSBoyd DA^r - 7 8/2f/78 78 8/-yV78 8/1?0/78 //78 I FORM 3._ _9.7~

NRC RM04 U__. 6VNMNPRT1OfCj0- 6._____

XRC ORM 318 (9-76) NRCM 0240

• U. . G0VnHltsHT RlrNrIN5 0OFFCsi *76 - *92

• -. . .4 P..:- -:'1-!., ,

o _, _,~ .*.. .. _... - , _ -

DEC 1 1978

.ocket No~ 50-36D Docket fo 50-368 Mr. William Cavanaugh III Executive Director of Generation

• . and Construction

. Arkansas Pouer & Light Company

1. - P.-O. Box 551

1. . P.,

' Little Rock, Arkansas 72203

Dear 1er. Cavanaugh:

-'SUBJECT- *ISSUANCE OF AMENDMENT NO. 7 TO FACILITY OPERATING LIC :ENSE

, NO. NPF-6 FOR ARKANSAS NUCLEAR OE, UNIT 2 The.Nuclear Regulatory Comission has issued the enclosed Mend Iment, No. 7 to Facility Operating License o. NPF-6 for the Arkansas Power and Light'Compahy for the Arkansas Nuclear One, Unit 2 plant. The amendment modifies.license No. NPF-6 to authorize'Mode 1 operat as

'noted below.. .

.I ..

The Appendix A Technical Specifications are odified to ref'Iect

.the'incorporation of portable containment radiation mnitor*sfor an interim nrerind-f

_. .2. Three license conditions have been deleted regarding equipm ent qual i-

... -.. ' . fication, fire barrier testing and implementation of modifi cations .....,...... ... ....

, . . for protection from degraded offsite power grid voltage. I~~~~~

. I .... .

... 3. License conditions have been modified regarding implenentat-ion

..of the'fire protection odifications and the staff positions on

-. - \ 'the core protection calculator system. .

Howlever, operation of the facility is temporarily restricted to the sequence of operational modes described in Attachment 2 to-the license until the preoperational tests, startup tests and other items noted in

. . I . Attachment 2 are completed to the written satisfaction of the Coinmnisslon.

I * .. . . . .

. 7 8 1 2 1+ 4.f i..

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tir. !illiam Cavanaugh III DEC 1 1978 i

Copies of the FEDERAL REGISTER 1... Evaluation supporting Amendment Notice of Issuance, and of the Safety No. 7 are also enclosed.

....  : Sincerely,

• t 8 t0diiTt~K ger S. Byd, Director

'Division of Project tManagement Office of Nuclear Reactor Regulation ns.. r.

. >.Encl osures:  : .

I. ..

.~ . .. :i. Amendm~ent Mo. 7 to Facility Operating License No.

2. FEDERAL REGISTER Notice NqPF-6 I 4

3. Safety Evaluation Supporting .

h~mendment N'o. 7 to NlPF-6

' .. - cc: See age 3. . .. .. : . , :1.4 I .. . .: . . .1 I

. I I.

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. . SEE PREt] IOUS YELtOW FOR CONCURRENCES*

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UNITED STATES tL~UJ . NUCLEAR REGULATORY COMMISSION B eIII~f~J~ WASHINGTON, D.C. 20555-ON1 October 24, 1995 Mr. Jerry W. Yelverton Vice President, Operations ANO Entergy Operations, Inc.

1448 S.R. 333 Russeliville, AR 72801

SUBJECT:

CORRECTION TO AMENDMENT NO. 169 TO FACILITY OPERATING LICENSE NO. NPF ARKANSAS NUCLEAR ONE, UNIT NO. 2 (TAC NO. M92064)

Dear Mr. Yelverton:

On October 12, 1995, the Commission issued Amendment No. 169 to Facility Operating License No. NPF-6 for the Arkansas Nuclear One, Unit No. 2. The amendment revised the Technical Specifications (TS) to delete requirements associated with part length control assemblies in response to your application dated April 4, 1995.

After issuance, it was discovered that amendment numbers were not included on all the revised TS pages and the overleaf pages were not included in the document. Enclosed are the corrected TS pages for Amendment No. 169 which are being reissued.

We regret any inconvenience this may have caused you.

Sincerely, Geo ge Kalma Sen or Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-368

Enclosure:

Corrected TS pages cc w/encl: See next page

May 29, 2001 Mr. Craig G. Anderson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russeliville, AR 72801

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE:

REACTOR COOLANT SYSTEM LEAK DETECTION SYSTEMS (TAC NO. MB1182)

Dear Mr. Anderson:

The Commission has issued the enclosed Amendment No. 231 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated February 6, 2001, as supplemented by letter dated May 1, 2001.

The amendment revises the TSs associated with the reactor coolant system leakage detection systems, to make them consistent with the requirements in NUREG-1432, Standard Technical Specifications, Combustion Engineering Plants."

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, IRA!

Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368

Enclosures:

1. Amendment No. 231 to NPF-6

2. Safety Evaluation cc w/encs: See next page

T LCO 1 January 29, 1985 Docket No. 50-368 DISTRIBUTION:

Docket File RDiggs NRC PDR LTremper Mr. John M. Griffin L PDR OPA, CMiles Senior Vice President ORB#3 Rdg ACRS-l0 Energy Supply DEisenhut DBrinkman Arkansas Power & Light Company PMKretuzer-3 WJones P. 0. Box 551 RSLee TBarnhart-4 Little Rock, Arkansas 72203 OELD JNGrace SECY LHarmon

Dear Mr. Griffin:

EJordan Gray File +4 The Commission has issued the enclosed Amendment No. 62 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2. The amendment consists of changes to the Technical Specifications (TS) in response to your applica-tion dated June 30, 1983 as superseded by letter dated May 19, 1984.

The amendment revises the Technical Specifications pertaining to hydraulic snubbers and adds new requirements for mechanical snubber operability and testing.

A copy of our Safety Evaluation is also enclosed. The notice of issuance will be included in the Comilssion's next monthly Federal Register Notice.

Sincerely,

/SI Robert Lee, Project Manager Operating Reactors Branch #3 Division of Licensing

Enclosures:

1. Amendment No. 62 to NPF-6

2. Safety Evaluation cc w/enclosures:

ORB#3D. QB#4: ORB#3:DL OELD %I*W AD: DL Pt zer JRMIller GC as

/ /85 9->

85 / />3/85 v /A\/85 ) /Ygj 85 UPDR AD13CK DR P

August 8, 2003 Mr. Craig G. Anderson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE:

EXTENSION OF EMERGENCY DIESEL GENERATOR ALLOWABLE OUTAGE TIME (TAC NO. MB6361)

Dear Mr. Anderson:

The Commission has issued the enclosed Amendment No. 249 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2. This amendment consists of changes to the Technical Specifications in response to your application dated September 19, 2002, and as supplemented by letters dated January 8, May 22, and July 1, 2003.

The amendment extends the allowable outage time for the emergency diesel generators from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to a maximum of 14 days.

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, IRA!

Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368

Enclosures:

1. Amendment No. 249 to NPF-6

2. Safety Evaluation cc w/encls: See next page

°- UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C.20555 July 26, 1993 Docket No. 50-368 Mr. Jerry W. Yelverton Vice President, Operations ANO Entergy Operations, Inc.

Route 3 Box 137G Russeliville, Arkansas 72801

SUBJECT:

ISSUANCE OF AMENDMENT NO. 149 TO FACILITY OPERATING LICENSE NO. NPF ARKANSAS NUCLEAR ONE, UNIT NO. 2 (TAC NO. M86420)

The Commission has issued the enclosed Amendment No. 149 to Facility Operating License No. NPF-6 for the Arkansas Nuclear One, Unit No. 2 (ANO-2). This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 7, 1993.

The amendment corrects typographical errors that were introduced in the original TSs and in subsequent amendments.

A copy of our related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, Thomas W. Alexion, Proje Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No. 149 to NPF-6

2. Safety Evaluation cc w/enclosures:

See next page

Mr. C. Randy Hutchinson Vice President, Operati .NO Au, _..26, 1999 Entergy Operations, Inc. -

1448 S. R. 333 Russellville, AR 72801 SCIBJECT: ARKANSAS NUCLEAR ONE, UNITS 1 AND 2- ISSUANCE OF AMENDMENTS RE: ADMINISTRATIVE CHANGES TO THE TECHNICAL SPECIFICATIONS (TAC NOS. MA4368 AND MA4382)

Dear Mr. Hutchinson:

The Commission has issued the enclosed Amendment No. 198 to Facility Operating License

.No. DPR-51 and Amendment No. 209 to Facility Operating License No. NPF-6 for the Arkansas Nuclear One, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated November 24, 1998, as supplemented by letters dated February 25, 1999, and July 14, 1999.

The amendments revise the administrative sections of the TSs to reflect the approved consolidated quality assurance program, clarify the responsibilities of the shift technical advisor position on shift, simplify the contents of the monthly operating report description, complete the relocation of the fire protection requirements from the TSs to the fire protection program, and replace selected position titles with descriptions of functional responsibility.

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, Is! 1y N.Hilton Nicholas D. Hilton, Project Manager, Section 1

-- Project Directorate IV & Decommissioning 9909070181 990826 Division of Licensing Project Management P P R Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368

Enclosures:

1. Amendment No. 198 to DPR-51

2. Amendment No.209 to NPF-6 z co a M

3. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Docket File PUBLIC K.Brockman, RIV LHurley, RIV PDIV-1 Reading J.Kilcrease, RIV OGC ACRS S.Richards (cover Itr only)

G.HilI (4) G0 r (-)3 IScholl (Email SE) to receive copy OT document, indicate: tic copy -itt PREVIOUS UUNiLNUhhtNU t OFFICE DLPMA 4q dOTB I OLB- l IQMB* SPLB*

NAME GDicAdb WBeckner 41 l } JHannon 11 vro DATE l 99 l 5/17/99 5/17/99 OFFICE PD1V-1/PM l PDIV-1/P PDIV-1 l OG<4 PDIVA1$C NAME WHilton bcC.Nolan C L.Berry ER C MTaw J R.Gramm DATE / /99 8 11t99 a\/99 I/f l99 ___W_ _

Uocument Name:  :\LAIV-1XANO1-2\AMD4368.WFU OFFICIAL RECORD COPY

4G* t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 0

June 1, 1989 Docket Nos. 50-313 and 50-368 Mr. T. Gene Campbell Vice President, Nuclear Operations Arkansas Power and Light Company P. 0. Box 551 Little Rock, Arkansas 72203

SUBJECT:

ISSUANCE OF AMENDMENT OS. 122AND 96 TO FACILITY OPERATING LICENSE NOS. DPR-51 AND NPF ARKANSAS NUCLEAR ONESr UNITS 1 AND 2 (TAC NOS. 73095 AND 57338)

The Commission has issued the enclosed Amendment Nos.122 and96 to Facility Operating License Nos. DPR-51 and PF-6 for the Arkansas Nuclear One, Units 1 and 2 (ANO-1&2). These amendments consist.of changes to the Technical Specifications (TSs) inresponse to your applications dated March 20 and 24, 1985 respectively.

The amendments delete .the remaining portions of the Appendix B TSs dealing with land management for both units. These are Section 3.5 for ANO-1 and Section 5.9 for ANO-2. Previously, Amendment Nos. 111 and 68 for ANO-1&2 respectively deleted those portions of Appendix B TSs not dealing with land management.

With the issuance of this amendment, the deletion of the entire Environmental Technical Specifications iscomplete for each unit. However, itshould be noted that you are still required by License Condition 2.E of the ANO-2 license to prepare an environmental evaluation before engaging inany activities which may result in-an environmental impact that was not evaluated by the Commission.

Inaddition, this license condition requires that when your evaluation indicates that such activities may result in a significant adverse environmental impact that was not evaluated, or that is significantly greater than that evaluated, in the Final Environmental Statement NUREG-0254), a written evaluation of such activities will be provided for our prior approval.

PDR ADOCK 890601 8906090264 000313:,

'1' P PDC

Mr. T. Gene Campbell - 2 -

A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's next B-weekly Federal Register notice.

Sincerely, C. Craig arbuck, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation Chester Poslusny, J , Project Manager Project Directorate - IV Division of Reactor Projects - Il, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No. 122 to DPR-51

2. Amendment No. 96 to NPF-6

3. Safety Evaluation cc w/enclosures:

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