ML19072A134

Amended Provisional Operating License DPR-5, 3-22-2019

ML19072A134
Person / Time
Site:	Indian Point
Issue date:	03/15/2019
From:	Office of Nuclear Reactor Regulation
To:	Entergy Nuclear Operations
Guzman R, NRR/DORL/LPL1, 415-1030
References
Download: ML19072A134 (21)

Text

ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO.50-003 INDIAN POINT NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 52 License No. DPR-5 The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee), dated May 30,2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations, and all applicable requirements have been satisfied.

Accordingly, License No. DPR-5 is hereby amended as indicated in the attachment to this license amendment, and paragraphs 3.B and 9 of Provisional Operating License No. DPR-5 are hereby amended to read as follows:

1. This license applies to the utilization facility consisting of a pressurized water reactor (hereinafter referred to as 'the reactor), and associated components and equipment hereinafter specified, which is owned by ENIP2, located in Westchester County, New York, and described in the amended and Substituted Application for Licenses dated November 30, 1960, as amended; in the Application for License amendment dated April 6, 1965, as supplemented May 6, 1965; and in the Application for License amendment dated December 3, 1965 (hereinafter referred to as 'the application'), and which is a part of the electric generating plant which has been designated by ENIP2 as the Indian Point Station Unit No. 1.

2. Subject to the conditions and requirements incorporated herein, the Amend 45 U.S. Nuclear Regulatory Commission (hereinafter referred to as "the 1-31-96 Commission") hereby licenses:

a) ENIP2 and ENO, pursuant to Section 104b. of the Act and Title 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess but not operate the facility at the Amendment No. 52

designated location in Westchester County, New York, in accordance with the procedures and limitations described in the application and this license; b) ENO, pursuant to the Act and 10 CFR Part 70, to receive and possess up to 1918 kilograms of contained uranium-235 previously received for reactor operation; c) Deleted; d) Deleted; e) ENO, pursuant to the Act and 10 CFR Parts 30 and 70, to receive Arndt. 45 and possess, but not to separate, such byproduct and special 1-31-96 materials as were produced by the prior operation of the facility; f) Deleted.

3. This license shall be deemed to contain and is subject to the conditions specified in Sections 50.54 and 50.59 of Part 50, Section 70.32 of Part 70, Section 40.41 of Part 40, and Section 30.32 of Part 30 of the Commissions regulations; is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now and hereafter in effect; and is subject to the additional conditions specified below:

a) Maximum Power Level ENO is prohibited from taking the reactor to criticality, and the facility shall not be operated at any power level.

b) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. ENO shall maintain the facility in accordance with the Technical Specifications.

c) Records In addition to those otherwise required under this license and applicable regulations, ENO shall keep the following records:

1. Reactor operating records, including power levels and period of operation at each power level.

2. Records showing the radioactivity released or discharged into the air or water beyond the effective control of ENO as measured at or prior to the point of such release or discharge.

3. Records of scrams, including reasons therefor.

4. Records of principal maintenance operations involving substitution or replacement of facility equipment or components and the reasons therefor.

Amendment No. 59

5. Records of radioactivity measurements at on-site and off-site monitoring stations.

6. Records of facility tests and measurements performed pursuant to the requirements of the Technical Specifications.

d) ENO 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 plans1 for the Indian Point Energy Center, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision 0, and was submitted by letter dated October 14, 2004, as supplemented by letter dated May 18, 2006.

ENO shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The ENO CSP was approved by License Amendment No. 55, as supplemented by changes approved by License Amendment Nos. 57, 59, and 60.

ENO has been granted Commission authorization to use stand alone preemption authority under Section 161A of the Atomic Energy Act, 42 U.S.C. 2201a with respect to the weapons described in Section II supplemented with Section III of Attachment 1 to its application submitted by letter dated August 20, 2013, as supplemented by letters dated November 21, 2013, and July 24, 2014, and citing letters dated April 27, 2011, and January 4, 2012. ENO shall fully implement and maintain in effect the provisions of the Commission-approved authorization.

1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Amendment No. 60

4. Deleted by Amendment No.7, dated 11-14-74.

5. Definitions - As used in this license the term facility means the following systems and components as described in the application:

a) The site as designated in Exhibit H-14 (Rev. 2) to the application, excluding: oil and coal storage facilities; the railroad spur; road systems and dock facility; and, to the extent not otherwise covered in this definition, the electrical transmissions lines and the Buchanan substation.

b) The reactor, including the reactor core, reactor vessel, support structure, instrumentation, and controls.

c) A primary coolant loop system, including piping, coolant pumps, nuclear boilers, pressurizer, auxiliary systems, instrumentation and controls.

d) A containment vessel to house the reactor and the primary loop system.

e) A cooling system for the containment vessel, including a system of pumps, piping, spray nozzles and heat exchangers.

f) A concrete radiation shield completely enclosing the containment vessel.

g) A system comprised of isolation valves and necessary operating controls to close penetrations of the containment vessel.

h) A ventilating system for the containment vessel, nuclear service building, chemical systems building, and fuel handling building.

i) A boron addition system, including mixing tanks, pumps, and piping.

j) Biological shielding, including water and concrete shields at the reactor vessel.

k) A decay heat cooling system, including heat interchangers, pumps and piping.

l) A closed, fresh-water coolant system, including heat interchangers, pumps and piping to provide cooling for the nuclear facility through heat interchangers where the heat in the fresh water is transferred to river water.

m) A chemical processing system, including ion exchangers, evaporators, heat interchangers, pumps, piping, and tanks to remove and dispose of gaseous, liquid and solid radioactive products from the primary coolant and waste liquids.

n) A fuel handling and storage system, including canals, transfer tube, stop valves, and fuel handling devices.

Amendment No. 58

o) An instrument system, including detectors, transmitters, amplifiers, receivers and controllers, panel boards and necessary circuitry to control the reactor and associated systems.

p) A radiation monitoring system, including detectors and measuring devices.

q) Secondary coolant system.

r) Auxiliary steam system.

s) Condensate and make-up water storage facilities.

t) Circulating system.

u) Component drain system.

v) Sampling system.

w) Electrical system excluding transmission lines and the Buchanan substation to the extent that they are not covered in the Technical Specifications.

6. On the closing date. of the transfer of the license, Con Edison shall transfer to ENIP2 all of the accumulated decommissioning trust funds for Indian Point Nuclear Generating Unit No.1 (IP1) and such additional funds to be deposited in the decommissioning trusts for IP1 such that the total amount transferred for IP1 and Indian Point Nuclear Generating Unit No. 2 (IP2) is no less than $430,000,000.

Furthermore, ENIP2 shall either (a) establish a provisional trust for decommissioning funding assurance for IP1 and IP2 in an amount no less than $25,000,000 (to be updated as required under applicable NRC regulations, unless otherwise approved by the NRC) or {b) obtain a surety bond for an amount no less than $25,000,000 (to be updated as required under applicable NRC regulations, unless otherwise approved by the NRC). The total decommissioning funding assurance provided for IP1 by the combination of the decommissioning trust and the provisional trust or surety bond at the time of transfer of the licenses shall be at a level no less than the amounts calculated pursuant to, and required under, 10 CFR 50.75. The provisional trust and surety bond shall be subject to or be consistent with the following requirements, as applicable:

(a) Deleted (b) Provisional Trust (i) The provisional trust agreement must be in a form acceptable to the NRC.

(ii) Investments in the securities or other obligations of Entergy Corporation or its affiliates, subsidiaries, successors, or assigns are and shall be 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 and shall be prohibited.

Amendment No. 61

(iii) The provisional trust agreement must provide that no disbursements or payments from the trust, other than for ordinary administrative expenses, shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The provisional 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.

(iv) The provisional trust agreement must provide that the agreement cannot be amended in any material respect, or terminated, without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(v) The appropriate section of the provisional trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a "prudent investor" standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commission's regulations.

(vi) Use of assets in the provisional trust, in the first instance, shall be limited to the expenses related to decommissioning IP1 or IP2 as defined by the NRC in its regulations and issuances, and as provided in this license and any amendments thereto.

(c) Surety Bond (i) The surety bond agreement must be in a form acceptable to the NRC and be in accordance with all applicable NRC regulations.

(ii) The surety company providing any surety bond obtained to comply with the requirements of the Order approving the transfer shall be one of those listed by the U.S. Department of the Treasury in the most recent edition of Circular 570 and shall have a coverage limit sufficient to cover the amount of the surety bond.

(iii) ENIP2 shall establish a standby trust to receive funds from the surety bond, if a surety bond is obtained, in the event that ENIP2 defaults on its funding obligations for the decommissioning of IP1. The standby trust agreement must be in a form acceptable to the NRC, and shall conform with all conditions otherwise applicable to the decommissioning trust agreement, and with all conditions that would be applicable to the provisional trust above, if established.

(iv) The surety agreement must provide that the agreement cannot be amended in any material respect, or terminated, without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

7. Deleted Amendment No. 61

8. ENIP2 and ENO shall take no action to cause Entergy Global Investments, Inc.,

or Entergy International Ltd. LLC or their parent companies to void, cancel, or modify the $55 million contingency commitment to provide funding for the IP1 and IP2 plants as represented in the application without the prior written consent of the Director of the Office of Nuclear Reactor Regulation.

9. The approved Decommissioning Plan supplements the Final Safety Analysis Report (FSAR) and the licensee may (i) make changes in the facility or procedures as described in the FSAR or the Decommissioning Plan and (ii) conduct tests, or experiments not described in the FSAR or Decommissioning Plan, without prior Commission approval, provided the requirements of 10 CFR 50.59 and 10 CFR 50.82(a)(6) and (7) are satisfied.

10. The amended license is effective as of the date of issuance, shall be implemented within 30 days, and shall expire at midnight, September 28, 2013.

FOR THE ATOMIC ENERGY COMMISSION Original signed by E.G. Case R.L. Doan, Director Division of Reactor Licensing Date of Issuance: October 29, 1965 Amendment No. 61

Appendix A to Provisional Operating License DPR-5 for Entergy Nuclear Indian Point 2, LLC and Entergy Nuclear Operations, Inc.

Indian Point Station Unit No. 1 Docket No. 50-3 Amendment No. 50

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS Section Title Page 1.0 General Information 1 1.1 Definitions 2 1.2 Exclusion Distance 3 1.3 Principal Activities 3 2.0 Reactor Facility Design Performance Requirements 4 2.1 Electrical Power Supply 4 2.2 Fuel Storage 4 2.3 Fire Protection 5 3.0 Administrative and Procedural Safeguards Responsibility 5 3.1 Responsibility 5 3.2 Organization 5 3.3 Operating Instructions and Procedures 6 4.0 Operating Limitations 8 4.1 General 8 4.2 Release of Radioactive Liquids and Gases Radioactive Waste 8 4.3 Radioactive Waste 8 4.4 Radiation Monitoring 8 4.5 Radiological Environmental Monitoring 8 4.6 Spent Fuel Storage and Handling DELETED 8 5.0 Maintenance 10 5.1 General 10 5.2 Testing 11 5.3 Spent Fuel Storage Pool Sampling DELETED 11 6.0 Plant Reporting Requirements 12 6.1 DELETED 6.2 DELETED 6.3 DELETED 6.4 DELETED

Appendix A to Provisional Operating License DPR-5 For the Entergy Nuclear Indian Point 2, LLC and Entergy Nuclear Operations, Inc.

1.0 GENERAL INFORMATION The facility, known as the Indian Point Station Unit No.1, is located on a site in the Village of Buchanan, Westchester County, New York. The Indian Point Station Unit No.2 and the Indian Point Station Unit No.3 share this site.

Indian Point Unit No.1 includes a pressurized water reactor, which operated with an authorized maximum steady state power level of 615 thermal megawatts until October 31, 1974. Pursuant to the June 19, 1980 Commission Order Revoking Authority to Operate Facility" and the Decommissioning Plan for Indian Point Unit No.1" approved by the NRC in an Order dated January 31, 1996, the reactor remains in a defueled status and the unit continues to operate as a support facility for overall Indian Point Units 1 and 2 operations. Unit No.1 and Unit No.2 are physically contiguous and share a number of systems and facilities as well as a common operating organization. The technical specifications contained herein recognize this commonality as well as the intended use of the Unit No.1 facilities to support Unit No.2 until retirement of that unit, and contain specific references to Appendix A to the Indian Point Unit No.2 Facility Operating License No. DPR-26. Unit No.1 contains radioactive waste processing facilities, which provide waste processing services for both Unit No.1 and Unit No.2.

Radiological effluent limits are met on an overall site basis and specific operating limits and surveillance requirements for effluent monitoring instrumentation, including stack noble gas monitoring, are discussed in the Offsite Dose Calculation Manual.

Amendment No. 50, 52, Page 1

1.1 Definitions 1.1.1 Final Safety Analysis Report The final Safety Analysis Report (FSAR) for Indian Point Unit. 1, shall be deemed to refer to , as appropriate, the "Final Hazards Summary Report for the Consolidated Edison Indian Point Reactor Core B" and the following exhibits, which are a part of the original license application for IP1:

• Docket 50-3 Exhibit K-5 (Rev. 1), "Hazards Summary Report Consolidated Edison Thorium Reactor: (January, 1960) Figures 1-2, 1-3, 3-14 only.

• Docket 50-3 Exhibit K-5A 11, "Supplementary Information on Plant Design of Consolidated Edison Nuclear Steam Generating Station,"

(August 1960) Section 3.7.1, pages 171 through 176 only and Section 3.7.2.

1.1.2 Operable-Operability A system, subsystem, train, component or device shall be operable or have operability when it is capable of performing its intended safety function(s). Implicit in this definition shall be the assumption that necessary instrumentation, controls, electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its safety function(s) are also capable of performing their related support functions.

1.1.3 Offsite Dose Calculation Manual (ODCM)

The Offsite Dose Calculation Manual contains the current methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the environmental radiological monitoring program. Requirements for the ODCM are specified in Appendix A to the Indian Point Nuclear Generating Unit No. 2 Facility Operating License No. DPR-26.

1.1.4 Site Boundary The Site Boundary is that line beyond which the land is neither owned, leased, nor otherwise controlled by either ENIP2, ENO, or other site licensee.

Amendment No. 50, 52, Page 2

1.1.5 Unrestricted Area An Unrestricted Area is any area at or beyond the Site Boundary, access to which is not controlled by either ENIP2, ENO, or other site licensee for purposes of protection of individuals from radiation and radioactive materials.

1.2 Exclusion Distance 1.2.1 The minimum distance from the reactor facility to the nearest land boundary of the exclusion area, as defined in 10 CFR 100 shall be 1400 feet.

1.2.2 The minimum distance from the reactor center line to the boundary of the site exclusion area and the outer boundary of the low population zone as defined in 10 CFR 100.3 is 460 meters and 1100 meters, respectively.

1.3 Principal Activities The principal activities carried on within the Exclusion Area shall be the generation, transmission and distribution of steam and electrical energy (except by gas-fired power plant); associated service activities; activities relating to the controlled conversion of the atomic energy of fuel to heat energy by the process of nuclear fission; and the storage, utilization and production of special nuclear, source and byproduct materials. Transmission and distribution of natural gas shall be through the use of facilities located as described in the application as amended.

Amendment No. 50, 52, Page 3

2.0 REACTOR FACILITY DESIGN PERFORMANCE REQUIREMENTS 2.1 Electrical Power Supply Power for electrical equipment shall normally be supplied by at least two independent transmission feeders from the Consolidated Edison system. If power is lost to the spent fuel storage area radiation monitor, a portable monitor will be promptly set up in the spent fuel storage area.

2.2 Fuel Storage 2.2.1 No fuel other than irradiated fuel from Indian Point Unit No.1 shall be stored in the Unit No.1 spent fuel storage area. No fresh fuel shall be stored at Unit No.1.

2.2.2 Spent fuel storage shall be provided in the storage pools in the Fuel Handling Building. The Fuel Handling Building and the spent fuel storage pool will contain the spent fuel until such time as offsite spent fuel management facilities are provided for, and the spent fuel is transferred to the Department of Energy, or as authorized by 10 CFR Part 72.

2.2.3 Spent fuel storage shall be provided with racks that shall limit the effective multiplication factor to less than 0.75.

2.2.4 Radiation levels in the spent fuel storage area shall be monitored continuously with a high level alarm indication in a location manned by a licensed operator* whenever there is irradiated fuel stored therein. If the monitor is inoperable, a portable monitor may be used. In such cases, provisions shall be made for prompt notification of a licensed operator upon actuation of the portable monitor's high level alarm.

Amendment No. 45, 52, Page 4

2.2.5 If a spent fuel pool contains spent fuel, the spent fuel cask shall not be moved over that pool or within a distance of that pool such that the cask could strike the pool if it fell or tipped.

2.2.6 A dead-load test shall be successfully performed on the fuel handling building crane before fuel movement begins. The load assumed by the crane for this test must be equal to or greater than the maximum load to be assumed by the crane during the fuel handling operation. A thorough visual inspection of the crane shall be made after the dead-load test and prior to fuel handling.

• licensed Operator for IP-2 2.3 Fire Protection Overall site fire protection is provided by a fire protection system, which is common to both Unit No. 1 and Unit No.2. Operation, maintenance and testing are controlled by common procedures.

3.0 ADMINISTRATIVE AND PROCEDURAL SAFEGUARDS 3.1 Responsibility Responsibilities are as specified in Appendix A to the Indian Point Nuclear Generating Unit No.2 Facility Operating license No. DPR-26.

Amendment No. 45, 48, 52, Page 5

3.2 Organization The organization requirements are as specified in Appendix A to the Indian Point Nuclear Generating Unit No.2 Facility Operating License No. DPR-26.

a. All fuel handling shall be under the direct supervision of a licensed operator

b. The Shift Manager is responsible for operations at the Unit No.1 facility.

• Licensed operator for IP-2 Amendment No. 45, 48, 49, 52, Page 6

3.3 Operating Instructions and Procedures 3.3.1 No fuel will be loaded into the reactor core or moved into the reactor containment building without prior review and authorization by the Nuclear Regulatory Commission.

3.3.2 Detailed written instruction setting forth procedures used in connection with the operation and maintenance of the nuclear power plant shall conform to the requirements specified in Appendix A to the Indian Point Nuclear Generating Unit No.2 Facility Operating License No. DPR-26.

3.3.3 Operation and maintenance of equipment related to safety when there is no fuel in the reactor shall be in accordance with written instructions.

Amendment No. 46, 48, 49, 52, Page 7

4.0 OPERATING LIMITATIONS 4.1 General Whenever any operation is being performed that could result in the release of radioactivity or create a change in radiation levels, supporting facilities shall be maintained and operated as required in these Technical Specifications.

4.2 Release of Radioactive liquids and Gases The concentration of radioactive materials released in liquid or gaseous form to unrestricted areas shall not exceed the limits specified in 10 CFR Part 20. The concentrations of radioactive material released in liquid effluents to unrestricted areas shall not exceed ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 - 20.2402. Release of radioactive liquids and gases shall also be consistent with the requirements of 10 CFR Part 50, Appendix I, as specified in the ODCM.

4.3 Radioactive Waste All radioactive waste material shall be handled in accordance with 10 CFR Part

20. In addition, solid radioactive waste shall be controlled as specified in the Process Control Program.

4.4 Radiation Monitoring Radiation monitoring systems shall be maintained operable for: (1) sphere foundation sump, (2) secondary purification blowdown cooling water, and (3) area radiation monitors. If monitoring systems are not operable, effluent sampling and/or local monitoring shall be accomplished to replace the non-operating system. In addition, Unit 1 radioactive effluent monitoring instrumentation shall be operable as specified in the ODCM.

4.5 Radiological Environmental Monitoring The Indian Point site Radiological Environmental Monitoring Program shall be conducted as specified in the ODCM.

Amendment No. 45, 52, Page 8

4.6 Spent Fuel Storage and Handling 4.6.1 All irradiated fuel shall be stored in the racks provided in the Fuel Handling Building Storage pools, with sufficient shielding that ensures that the radiation level on the operating deck is s 15 mr/hr. Should the radiation level be found to be above 15 mr/hr, corrective action shall be initiated to restore the level to < 15 mr/hr.

Amendment No. 51, 52, Page 9

4.6.2 Whenever, spent fuel storage pool water inventory is provided for personnel shielding, the normal water level shall be maintained at or above elevation 48 feet (approximately 6 feet above the top of the spent fuel racks). Any pool in which spent fuel is stored shall be subject to weekly verification of water level. Should the water level be found to be below elevation 48 foot, both pool level and radiation level on the operating deck shall be verified daily. Should the water level be found to be below elevation 47 foot, corrective action shall be initiated to investigate the reason for the reduced level and restore the level to > 48 foot.

4.6.3 Water chemistry in any spent fuel storage pool containing spent fuel shall be maintained within the following limits:

Chlorides: < 1.5 ppm pH: 4.0 - 8.0 Conductivity < 20 µs/cm Should any of the above parameters be found to deviate from the specified limits an effort shall be promptly initiated to investigate the cause of the deviation and a process to restore the parameter to within the applicable limit shall be established in a timely fashion.

4.6.4 Ventilation capable of directing all Fuel Handling Building airborne effluents through monitoring pathways shall be available during any fuel movement or other activity that might potentially damage spent fuel assemblies.

5.0 MAINTENANCE 5.1 General Components addressed in these technical specification requirements, which have been repaired, replaced, or otherwise subjected to temporary or permanent modification, shall be tested in accordance with procedures, which are appropriate in view of the nature of the repair, replacement, or modification, and the condition of the system.

Amendment No. 45, 52, Page 10

5.2 Testing 5.2.1 Functional radiation monitoring systems (only for the following: sphere foundation sump and secondary purification blowdown cooling water) and area radiation monitoring systems. shall be:

a. qualitatively checked daily to verify acceptable operability of instrument channel behavior during operation, and

b. tested quarterly by injection of a simulated signal into the instrument channel to verify that it is operable, including alann and/or trip initiating action. The quarterly interval is defined as quarterly plus or minus 25%

of the quarter.

5.2.2 Unit 1 radioactive effluent monitoring instrumentation shall satisfy the surveillance requirements as specified in the ODCM.

5.3 Spent Fuel Storage Pool Sampling Any spent fuel storage pool containing spent fuel stored in water shall be sampled monthly for chloride level, pH and Cesium 137 activity. If Cesium 137 activity is found to be elevated above normal levels, an effort shall be promptly initiated to investigate the cause of the elevated level and take subsequent corrective action, as appropriate.

Amendment No. 50, 52, Page 11

6.0 PLANT REPORTING REQUIREMENTS Reporting Requirements are as specified in Appendix A to the Indian Point Nuclear Generating Unit No. 2 Facility Operating License No. DPR-26.

Amendment No. 45, 52 Page 12