ML20207C342

Amend 27 to License NPF-29,authorizing Transfer of Control & Performance of Licensed Activities from Util to Sys Energy Resources,Inc & Granting Exemption from 10CFR100.11(a)(1)

ML20207C342
Person / Time
Site:	Grand Gulf
Issue date:	12/20/1986
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207C347	List: ML20207C342 ML20207C354
References
TAC-62754, NUDOCS 8612300118
Download: ML20207C342 (30)

Text

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1. jra 4%q'o, UNITED STATES

!T NUCLEAR REGULATORY COMMISSION c[ $

WASHINGTON, D. C. 20555 O

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MISSISSIPPI POWER & LIGHT COMPANY SYSTEM ENERGY RESOURCES, INC.

SOUTH MISSISSIPPI ELECTRIC POWEP ASSOCIATION DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. NPF-29 1.

The Nuclear Regulatory Commission (the Commission) has found that A.

The application for amendment by Mississippi Power & Light Company, System Energy Resources, Inc. (formerly Middle South Energy, Inc.)*

and South Mississippi Electric Power Association, (the licensees) dated September 2, 1986 as amended on October 4, 13 and 24, and as supplemented on November 20, 21, and December 2 and 3, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rulas and regulations of the Commission, except as duly exempted therefrom; C.

There is reasonable assurance (1) 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 Commission's regulations, except as exempted from compliance therefrom; 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 Commission's regulations and all applicable requirements have l

been satisfied.

2.

Accordingly, the license is hereby amended by changes, as indicated by bars in the margins, to Facility Operating License No. NPF-29 to read as follows (for convenience the license is provided in its entirety):

• The licensees state that on July 28, 1986, Middle South Energy Inc. was renamed and reconstituted as a new nuclear generating company. The newly named company, System Energy Resources, Inc. (SERI), upon necessary regulatory approvals and transfer of personnel, will succeed MP&L as operator of GGNS Unit I and will assunc exclusive responsibility for and control over operation and maintenance of the facility. By operation of this amendment, SERI also i

succeeds MSE as a licensee-owner.

8612300118 861220 PDR ADOCK 05000416 P

PDR t

. MISSISSIPPI POWER & LIGHT COMPANY SYSTEM ENERGY RESOURCES, INC.

SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1

~

FACILITY OPERATING LICENSE License No. NPF-29 1.

The Nuclear Regulatory Commission (the Commission or the NRC)'has found that:

A.

The application for license filed by Mississippi Power & Light Company (MP&L), for itself and Middle South Energy, Inc., (now renamed System Energy Resources, Inc. (SERI)) and South e

l Mississippi Electric Power Association (hereinafter referred

~

to as the licensees) complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act),

ar.d the Commission's regulations set forth in 10 CFR Chapter I,'

and all required notifications to other agencies or bodies have been duly made; B.

Construction of the Grand Gulf Nuclear Station, Unit 1 (the facility), has been substantially completed in conformity with Construction Permit No. CPPR-118 and the application, as amended, the provisions of the Act, and the regulations of the Commission; t

C.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.0.

below);

D.

There is reasonable assurance:

(i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below);

E.

System Energy Resources, Inc. (SERI)* is technically qualified l

to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I;

• SERI is authorized to act for itself and for SMEPA and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

I

.. F..

The licensees-have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G.

The issuance of this license will not be inimical 'to the comon defense and security or to the health and safety of the public; H.

After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other 4

costs and considering available alternatives, the issuance of Facility Operating License No. NPF-29, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix E, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I.

The receipt, possession, and use of source, by-product and special nuclear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 30, 40, and 70.

2.

Based on the foregoing findings regarding this facility and. pursuant to Commission Order CLI-84-19, dated October 25, 1984, License NPF-13, as amended, is superseded by this Facility Operating License NPF-29 which is hereby issued to the Mississippi Power & Light Company, System Energy Resources, Inc., and South Mississippi Electric Power l

Association to read as follows:

A.

This license applies to the Grand Gulf Nuclear Station (GGNS),

Unit 1, a boiling water nuclear reactor and associated equipment (the facility), owned by System Energy Resources, Inc., and South l

Mississippi Electric Power Association and operated by System Energy Resources, Inc. The facility is located in Claiborne County, Mississippi, and is described in the licensees' " Final Safety Analysis Report," as supplemented and amended, and in the licensees' Environmental Report, as supplemented and amended.

B.

Subject to the conditions and requirements incorporated herein, the Comission hereby licenses:

(1) System Energy Resources, Inc. (SERI) pursuant to Section 103

.l of ~the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Claiborne County, Mississippi, in accordance with the procedures and limitations set forth in this license; (2) System Energy Resources, Inc., and South Mississippi Electric l

Power Association to possess the facility at the designated location in Claiborne County, Mississippi, in accordance with the procedures and limitations set forth in this license; 4

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. (3) SERI, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as 4

reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) SERI, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) SERI, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any by-product, source or special nuclear material without restric-4 tion to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) SERI, pursuant to the Act and 10 CFR Parts 30, 40, and 70, l

to possess, but not separate, such byproduct and special 4

nuclear materials as may be produced by the operation of the facility.

4 C.

The license shall be deemed to contain and is subject to the conditions r

specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Comission now or hereafter in effect; i

and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level

^

SERI is authorized to operate the facility at reactor core power l

levels not in excess of 3833 rgawatts thermal (100% power) in a

accordance with the conditions coecified herein.

(2) Technical Speciffrations The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

, are hereby incorporated into this license. System Energy Resources, Inc. shall operate the facility

.l in accordance with the Technical Specifications and the Environ-mental Protection Plan.

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. (3) Antitrust Conditions MP&L and SERI shall comply with the antitrust conditions delineated in Appendix C.

MP&L is authorized to transfer its rights to possess, to use and to operate the facility to SERI, provided however, that until further authorization of the Com-mission, MP&L and SERI shall continue to be responsible for compliance with the obligations imposed on the licensees in these antitrust conditions, and provided further that SERI accepts the right to possess, use and operate the facility subject to the outcome of the pending separate antitrust review of the antitrust considerations of this transfer.

(4)

Independent Verification of Staff Performance and Other Plant Activities (Section 13.4, SER, 55ER #2)

(a) SERI shall establish a subcommittee of the Corporate Safety l

Review Committee to review and evaluate the:

(i) Status and readiness of the plant and systems needed to support intended modes of operation and/or testing; (ii) Readiness of personnel to conduct intended operation and testing; (iii) Morale and attitudes of plant personnel that have a bearing on safe plant operation; (iv) Past performance in plant operations and adherence to procedures and administrative controls; (v) Changes in current organization with regard to experience and qualifications of plant management and supervisory personnel since the last evaluation; (vi)ResultsandeffectivenessofthePlantSafetyReview h

Committee (PSRC),

l (vii) Status of plant as compared to other BWR startups j'

based on the subcommittee's knowledge and experience.

Reviews shall be conducted prior to exceeding 50 percent of full power and within 30 days following completion of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> warranty run. The subcommittee shall be composed of a minin'um of three professionals not employees of SERI l

with experience which will be responsive to the concerns l-presented above.

In conducting these evaluations, the

subcommittee shall conduct interviews of representatives of all levels of plant staff management. The subcommittee shall report directly to the Chainnan of the Corporate Safety Review Committee and, in turn, SERI shall submit the report of these reviews to NRC.

(b) The Plant Safety Review Consnittee shall review all Unit 1 Preoperational Testing and System Demonstration activities performed concurrently with the Unit 1 Startup Test Program to assure that the activity will not affect the safe-per-formance of the portion of the Unit 1 Startup Program being performed. The review shall address, as a minimum, system interaction, span of control, staffing, procedures, security and health physics, with respect to performance of the activities concurrent with the portion of the Unit 1 Startup Program being performed.

(5) Deferred Preoperational Deficiencies SERI shall satisfactorily resolve those deficiencies which were deferred from the preoperational testing program on a schedule that shall assure that the capability of a system required to be operable by Technical Specification is not degraded.

(6) Soil Structure Interaction (Section 3.7.1, SER, SSER #2)

Prior to startup following the first refueling outage, SERI shall l

complete structural modifications, if required, as a result of the NRC staff's completion of its review of MP&L* responses.

l (7) Seismic Instrumentation (Section 3.7.4, SER, SSER #2)

Prior to startup following the first refueling outage, the installation of triaxial strong motion accelerometers on reactor supports shall be completed.

(8) Masonry Walls (Section 3.8.3, SER, SSER #2)

Prior to startup following the first refueling outage, SERI shall complete structural modifications, if required, as a result of the NRC staff's complation of its review of the MP8L response to IE Bulletin 80-11.

• The original license authorized Mississippi Power & Light Company (MP&L) to operate the facility. Consequently, there are certain historical references to MP&L in this license.

T (9) Dynamic Testing (Section 3.9.2, SER, SSER #2, SSER f4, SSER #5)

SERI shall' conduct vibrational measurement and inspection pro-l ardms during preoperational and initial startup testing in accordance with the guidelines of R.G. 1.20, " Comprehensive 4

Vibration Assessment Program for Reactor Internals During Pre-operational and Initial Startup Testing," for prototype reactors.

An evaluation report demonstrating satisfactory results shall be provided to the NRC for review and approval no later than 6 months after completion of the startup test program.

(10) Dynamic Qualification (3.10, SER, SSER #1, SSER #2, SSER #4, SSER #5)

(a) Prior to startup following the first refueling outage, SERI shall complete any modifications or replacement of equipment found necessary as a result of the fatigue evaluation.

In the interim, SERI shall document the occurrence of every I

safety relief valve actuation into the suppression pool; the associated cumulative damage factors shall be calculated for typical representative equipment and kept up-to-date; and SERI shall report to NRC any malfunction of equipment I

that occurs due to any safety relief valve discharge.

(b) SERI shall perform an in-situ test of the High Pressure l

p Core Spray (HPCS) service water pump and evaluate the i

i effects of. flow induced vibration on the HPCS service. water pump. This evaluation shall be provided to the NRC for review and approval. Prior to startup following the first refueling outage SERI shall complete all modifications as I

a result of the NRC staff's review of the test results and evaluation.

(c) Prior to actual use in fuel handling operations, SERI shall l

qualify the fuel-handling and auxiliary platform, in-vessel rack, and storage container for defective fuel.

(11) Envircnmental Qualification (Section 3.11, SER; SSER #1;

]

Appendix H, SSER #2; SSER #5)

Prior to March 31, 1985, SERI shall environmentally qualify all l

i electrical equipment as required by 10 CFR 50.49.

(12) Surveillance of Control Blade (Section 4.2.3.14, SER) l Within 30 days after plant startup following the first refueling ll j

outage, SERI shall comply with itens 1, 2 and 3 of Bulletin No.

l 79-26 and submit a written response to NRC on item 3.

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. (13) Core Stability Analysis and Prohibition of Natural Circulation (Section 4.4.1, SER)

(a) Prior to startup following the first refueling outage, SERI l

shall submit a new core stability analysis for operation beyond cycle 1.

(b) Natural circulation shall be prohibited as an operating mode.

(14) Loose Parts Monitoring (Section 4.4.1, SER)

Prior to startup following the first refueling outage, SERI l

shall submit an evaluation of the Loose Parts Monitoring System to address conformance to R.G. 1.133, Rev. 1. dated May 1981.

(15) Scram Discharge Volume (Sections 4.6,SER)

Prior to startup following the first refueling outage, SERI l

shall incorporate the following additional modifications into the scram discharge volume system:

(i) Redundant vent and drain valves, and i

(ii) Diverse and redundant scram instrumentation for each instrumented volume, including both delta pressure sensors and float sensors'.

(16) Containment Purge (Se tion 6.2.4, SSER #5) l Prior to startup following the first refueling outage, SERI shall provide for NRC review a reevaluation of the need to use the con-tainment purge mode of the containment cooling system. This study should include,.but is not limited to, data gathered during the first fuel cycle related to airborne activity level (ALARA),

overall containment air quality and personnel access to contain-l ment.

Based on the above cited study, SERI shall propose the purge criteria to be used for the remainder of the plant life.

(17)ContainmentPressureBoundary(Section6.2.8,SER)

Prior to startup following the first refueling outage, SERI shall replace the feedwater' check valve disc with a disc made from a suitable material.

i (18) Pressure Interlocks o Valves Interfacino at Low and Hiah Pressure (Section 6.3.4, SSER #2) t i

Prior to startup following the first refueling outage, the licensee shall implement isolation protection against overpressurization of the low pressure emergency core cooling systems (PHR/LPCI and LPCS) at the high and' low pressure interface containing a check valve and a closed motor-operated valve.

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. (19) IE Information Notice 79-22, Qualification of Control System (Section 7.8.C, SER, SSER #2)

Prior to startup following the first refueling outage SERI shall I

complete any design changes found necessary as a result of this review.

(20) Standby Service Water System (Section 9.2.1 SER, SSER #2)

No irradiated fuel may be stored in the Unit I spent fuel storage pool prior to completion of modifications to either loop A or loop B of the standby service water (SSW) system and verification that the design flow can be achieved to all essential SSW system components in the modified loop. However, should a core offloading be necessary prior to completion of these modifications (scheduled for the first refueling outage), irradiated fuel may be placed in the spent fuel pool when the RHR system operating in the spent fuel pool cooling mode is available. Until the SSW loops are modified, the spent fuel pool cooler in an unmodified loop shall be isolated from the loop by locked closed valves or the loop shall be declared inoperable. The position of these valves shall be verified every 31 days until the design flowrate for the SSW loop is demonstrated.

The surveillance to be performed is to verify that any unmodified SSW loop with valves which are not locked closed is declared inoperable.

(21) Spent Fuel Pool Ventilation System (Section 9.4.2, SER, SSER #2)

If spent irradiated fuel is placed in the spent fuel pool prior to installation and operability of the safety related backup fuel pool cooling pump room coolers, the plant shall be placed in shutdown condition and remain shutdown with the RHR system dedicated to the fuel pool cooling mode.

(22) Remote Shutdown Panel (Section 9.5.4.1, SER, SSER #2)

Prior to startup following the first refueling outage, SFRI shall l

install electrical isolation switches between the control room and the Division 1 remote shutdown panel.

(23) Fire Protection Prooram (Section 9.5.9, SER)

SERI shall maintain in effect and fully implement all provisions of the approved Fire Protection Plan.

In addition, SERI shall maintain the fire protection program to meet the intent of i

Appendix R to 10 CFR Part 50, except that an oil collection system for the reactor coolant pump is not required.

. (24) Interplant Communication Systems (Section 9.6.1.2, SER, SSER #2, SSER #4, SSER #5)

Tests of the communication systems used to mitigate the con-sequences of an event and attain a safe plant shutdown shall be completed during preoperational and startup tests. An evaluation of the test results shall be provided for NRC review within 90 days after test completion. Any system modifications found necessary as a result of NRC review shall be completed prior to startup following the first refueling outage.

(25) Reliability of Diesel-Generators (Sections 8.3.1, 9.6.3 through 9.6.7, SER, 55ER #2, SSER #4, SSER #6)

(a) Prior to startup following the first refueling outage, a heavy duty turbocharger gear drive assembly shall be installed on all EMD diesel-generators.

(b) SERI shall comply with TDI emergency diesel generator require-l ments specified in Attachment 2 to this license.

(26) Turbine Disc Inteority (Section 10.2.1, SER, SSER #1)

SERI shall ultrasonically inspect the bores and keyways of the low l

pressure turbine discs for indications of cracking prior to exceeding 50,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of operation. All unacceptable indications and their dispositions shall be reported prior to startup for the next cycle of operation. These inspections shall continue on a 50,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> interval until the potential for turbine disc cracking has been assessed and an acceptable alternate inspection schedule has been established.

(27) Circulatina Water System (Section 10.4.5, SER)

SERI shall not fill the Unit 2 circulating water system (including l

the natural draft cooling tower basin) until Unit I flooding concerr.s related to this system are resolved to the. satisfaction of the,NRC staff.

(28)AdvisortotheVicePresident SERI shall have on its nuclear operations staff, one or more corporate l

management officials or advisors (who may be either permanent employees or contracted consultants) who have substantial commercial nuclear power plant operating management experience and who will advise on all decisions affecting safe operation of the plant. This requirement shall be in effect until the plant has accumulated at least 6 months at power levels above 90% of full power.

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(29) Operating Shift Advisor (Section 13.1.2, SER)

At least one individual on each operating shift shall have sub-stantive previous BWR operating experience, including startup and shutdown of a BWR and under conditions that one might expect to encounter during the initial startup and power escalation at the Grand Gulf plant. This individual is not required to be licensed on Grand Gulf Unit 1 and need not be a SERI employee, but as a minimum shall be retained on a I

contract basis to act as a consultant or advisor to the GGNS shift crew. Such an experienced person shall be assigned to each operating shift until the plant achieves and demonstrates full power operation.

(30) Training Instructors (Section 13.2, SER)

Permanent training center instructors and consultants assigned to training, who, after initial criticality will teach systems, integrated responses, transients, and simulator courses to license candidates or NRC-licensed personnel, shall either demonstrate or have previously demonstrated their competence to the NRC staff by successful completion of a senior operator examination prior to teaching ifcensed operators.

(31) Initial Test Program (Section 14, SER)

SERI shall conduct the post-fuel-loading initial test program (set forth in Section 14 of SERI's Final Safety Analysis Report, as amended) without making any major modifications of this pro-i gram unless such modifications have been identified and have received prior NRC approval. Major modifications are defined as:

(a) Elimination of any test identified in Section 14 of SERI's Final Safety Analysis Report, as amended, as being essential.,

(b) Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of SERI's l

Final Safety Analysis Report, as amended, as being essential; (c) Performance of an,y test at a power level different from that described in the program; and l

(d) Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized power level).

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. (32) Partial Feedwater Heatino (Section 15.1, SER, SSER #2)

Operation of the plant in the partial feedwater heating mode for-the purpose of extending the normal fuel cycle shall be prohibited until analyses which justify that operation are provided to and approved by the NRC staff.

(33) NUREG-0737 Conditions (Section 22.2)

SERI shall complete the following conditions to the satisfaction of the NRC. These conditions reference the appropriate items in Section 22.2, "THI Action Plan Requirements for Applicants for Operating Licenses", in the Safety Evaluation Report and Supple-ments 1, 2, 3, 4, and 5 NUREG-0831.

(a) Control Room Design Review (I.D.1, SER; Appendix E, SSER #2, SSER #4, SSER #5)

Prior to startup following the first refueling outage, SERI shall demonstrate the ability to maintain an " effective temperature" condition of 85'F or less in the remote shut-down panel (RSP) room for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with an ambient outdoor temperature of at least 95'F.

(b) TrainingDurinoLow-PowerTesting(I.G.1,SER)

Prior to restart following the first refueling outage, SERI l

shall complete the additional training and testing related to TMI Action Plan I.G.1 as described in Section 2.3 of the MP&L submittal dated April 3, 1986.

(c) PostAccidentSampling(II.B.3,SER,SSER#1,SSER#4, SSER #5)

Prior to startup following th'e first refueling outage, SERI shall incorporate the additional requirements into the procedure for relating radionuclide gaseous and ionic species to estimate core damage as discussed in Section II.B.3.1 of SSER #4.

(d) Hydrooen Control (Section II.B.7, SER, SSER #2, SSER #3, i

SSER #4, 55ER #5)

(1) During the first cycle of operation, SERI shall l

maintain a suitable program of analysis and testing

{

of the installed hydrogen ignition system. SERI shall submit to the NRC quarterly reports on the status of their research programs.

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. (a) SERI shall amend its research program on hydrogen l

control measures to include, but not be limited to, the following items:

1)

Perform containment sensitivity analysis to determine the adequacy of the hydrogen control system for a spectrum of degraded core accidents including the determination of accident sequences for which equipment survivability is assured; 2)

Research to investigate the conditions leading to and consequences resulting from hydrogen combus-tion in the wetwell and containment. Testing shall be performed in a larger scale facility such as the one-quarter scale test facility proposed by MP&L; 3)

Research to investigate the conditions leading to and consequences resulting from hydrogen combustion in the drywell; 4)

Confirmatory tests on thermal response of selected equipment exposed to hydrogen burns.

(b) SERI shall perform feasibility studies to examine the options for enhancing equipment survivability for essential equipment located in the vicinity of the suppression pool or other regions subjected to severe environments. The options to be studied in such feasibility studies shall include thermal shielding, additional cooling, and relocation of essential equipment.

(2)

(a) SERI shall complete its research program on hydrogen I

control to show that the hydrogen control system will perform its intended function in a manner that provides adequate safety margins. This research program shall be completed on a schedule which reflects the require-ments of 10 CFR 50.44.

(b)

If it is determined that plant modifications are required to obtain NRC approval that an adequate hydrogen control system for Grand Gulf is installed, then these modifications shall be completed on a schedule which is approved by the NRC.

(e)

Instrumentation for Detection of Inadequate Core Coolino (II.F.2, SER, SSER #2) 4 i

SERI shall submit a report addressing the analysis performed l

by the BWR Owners' Group regarding additional instrumentation j

relative to inadequate core cooling and shall implement the

. staff's requirements after the completion of the staff's review of this report. These modifications shall be completed on a schedule acceptable to the staff.

(f) Modification of Automatic Depressurization System Logic -

Feasibility for Increased Diversity for Some Event Sequences (II.K.3.18, SER, SSER #2, SSER #4)

Prior to startup following the first refueling outage, SERI l

shall provide, for NRC review, justification for the timer delay settings, revisions to the emergency procedures covering the use of the manual inhibit switch, proposed Technical Specification surveillance procedures for the timer and switch, and shall implement alternative logic modification (Option 4) of the automatic depressurization system.

(g) Qualification of ADS Accumulators (II.K.3.28, SSER #5)

Prior to startup following the fit:t refueling outage, SERI shall perform an integrated leak test on the ADS air system, perform sampling to establish instrument air quality, provide instrumentation to monitor ADS air receiver pressure, estab-lish suitable surveillance procedures for the ADS air system and provide proposed changes to the Technical Specifications associated with the surveillance procedures.

(34) SRV Test Program (Section A-39, Appendix C, SER, SSER #1, SSER #2)

During Cycle 1, an inplant SRV test program shall be carried out to confirm that the containment building response to SRV loads is acceptable. Results of these tests shall be provided to NRC no later than four months after test completion.

(35) Post-LOCA Vacuum Breaker Position Indicators Prior to startup following the first refueling outage, SERI shall install position indicators with redundant indication and alarm in the control room for the check valves associated with the dry-well post-LOCA vacuum breakers.

(36) Emergency Response Facilities (Generic Letter 82-33, NUREG-0737 Supplement 1, SSER #5)

SERI shall complete the emergency response capabilities as required l

by Attachment I to this license.

(37) Evaluation of Licensee's Technical Specification Problem Sheets (Section 16.3, SSER #6)

Prior to startup following the first refueling outage, SERI shall l

implement the following modifications:

. (a)

Include an emergency override of the test mode of the Division 3 HPCS diesel generator to pe mit response to emergency signals and to return the control of the diesel generator to the emeroency standby mode.

(Item No. 333, T.S. 4.8.1.. 2.d.12.b)

(b) Provide the second level undervoltage protection for Division 3 power supply (Item No. 373, T.S. Table 3.3.3-2).

(c)

Incorpnrate a bypass or coincident logic in all Division 1 and 2 diesel generator protective trips, except for trips on diesel engine overspeed and generator differential current (ltem No. 808, T.S. 4.8.1.1.2.d.16.d).

(38) Control Room Leak Rate (Section 6.2.6, SSER #6)

SERI shall operate Grand Gulf Unit I with an allowable control I

room leak rate not to exceed 590 cfm. Upon restart of construc-tion of Unit 2 control room, SERI will be permitted to operate at l

a leak rate of 760 cfm as evaluated in SSER No. 6.

(39) Temporary Secondary Containment Boundary Change For a period of time not to exceed 144 cumulative hours, the provisions of Specification 3/4.6.6.1 may be applied to the rail-road bay area including the exterior railroad bay door on the auxiliary building in lieu of the present secondary containment boundaries that isolate the railroad bay area. While the rail-road bay area is being used as a secondary containment boundary, the railroad bay door may be opened for the purpose of moving trucks in and out provided the four hour limitation in ACTION a of Technical Specification 3.6.6.1 is reduced to one hour. A fire watch shall be established in the railroad bay area while the door is being used as a secondary containment boundary.

(40) Temporary Ultimate Heat Sink Change With the plant in OPERATIONAL condition 4, SSW cooling tower basin A may be considered OPERABLE in accordance with Technical Specification 3.7.1.3 with less than a 30 day supply of water (without makeup) during the time that SSW basin B is drained to replace its associated service water pump provided:

(a) SSW basin A water level is maintained greater than or equal to 87".

(b) Atleasttwosourcesofwater(otherthannormalmakeup with one source not dependent on offsite power) are available for makeup to SSW basin A.

This license condition may remain in effect until plant startup following the outage scheduled for fall 1985.

i l D.

The facility requires exemptions from certain requirements'of Appendices A and J to 10 CFR Part 50 and from certain requirements l

of 10 CFR Part 100. These include: (a) exemption from General i

i Design Criterion 17 of Appendix A until startup following the first refueling outage, for (1) the emeroenc

-for the Division 3 diesel engine, (2) y override of the test mode i

the second level undervoltage protection for the Division 3 diesel engine, and (3) the generator ground over current trip function for the Division 1 and 2 diesel

-generators (Section 8.3.1 of SSER #7), and (b) exemption from the requirements of Paragraph III.D.2(b)(11) of Appendix J for the con-tainment airlock testing following normal door opening when containment l

integrity is not required (Section 6.2.6 of SSER #7). These exemptions are authorized by law and will not endanger life or property or tbc common defense and security and are otherwise in the public interest.

In addition, by exemption dated December 20,1986, the Comission exempted licensees from 10 CFR 100.11(a)(1), insofar as it incorporates the definition of exclusion area in 10 CFR 100.3(a), until April 30, 1987 regarding demonstration of authority to control all activities i

within the exclusion area (safety evaluation accompanying Amendment No. 27 toLicense(NPF-29). This exemption is authorized by law, i

and will not present an undue risk to the public health and safety, dnd is consistent With the Common defense and security.

In addition, special circumstances have been found justifying the exemption, i

Therefore, these exemptions are hereby granted pursuant to 10 CFR 50.12.

With the granting of 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.

E.

SERI shall maintain in effect and fully implement all the pro-l visions of the Commission-approved physical security plan, guard training and qualification plan and safeguards contingency plan, including amendments made pursuant to the authority of 10 CFR Section 50.54(p) approved plans, which are safeguards infomation protected under 10 CFR 73.21, are collectively entitled Grand Gulf Nuclear Station " Physical Security Plan," Revision 1, 2 and 3; the Grand Gulf Nuclear Station " Security Training and Qualifi-cation Plan," and the Grand Gulf Nuclear Station " Safeguards Contingency Plan." The identification of vital areas and measures used to control access to these areas, as described in the physical security plan, may be. subject to amendments in the futore based upon a confimatory evaluation of the plant to determine those areas where acts of sabotage might cause a release of radio-nuclides in sufficient quantities to result in dose rates equal to or exceeding 10 CFR Part 100 guidelines.

F.

SERI shall report any violations of the requirements contained l

in Section 2, Items C.(1), C.(4) through C.(38) of this license within twenty-four (24) hnurs.

Initial notification shall be made in accordance with the provisions of 10 CFR 50.72 with writtenfollow-up)inaccordancewiththeproceduresdescribed in 10 CFR 50.73(b, (c), and (e).

M_-

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I I

i 1 !

G.

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

H.

This license is effective as of the date of issuance and shall expire at midnight on June 16, 2022.

3.

Attachments 1 and 2 to Facility Operating License No. NPF-29, which have previously been incorporated into the license, are further amended bychanges(asindicatedbythebarsinmargins)asshowninAttachments 1 and 2 to this amendment. '

4.

The license is further amended by changes to the Appendices as follows:

A.

Change Appendix A, Technical Specifications, and Appendix B, Environmental Protection Plan, as indicated in Attachment 3 to this license amendment.

Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 27 are hereby incorporated into this license. System Energy Resources, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

B.

On page 1 of Appendix C Antitrust Ccnditions, change the phrase "The Mississippi Power & Light Company shall comply with the following antitrust conditions." To "MP&L and SERI shall comply with the following antitrust conditions."

5.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION L

(.

Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing I

Attachment:

Changes to the Technical Specifications and changes I

to the Environmental l

I Protection Plan Date of Issuance: December 20, 1986 1

l s

A

. G.

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

H.

This license is effective as of the date of issuance and shall expire at midnight on June 16, 2022.

3.

Attachments 1 and 2 to Facility Operating Licerise No. NPF-29, which have previously been incorporated into the license, are further amended by changes (as indicated by the bars in margins) as shown in Attachments 1 and 2 to this amendment.

4.

The license is further amended by changes to the Appendices as follows:

A.

Change Appendix A, Technical Specifications, and Appendix B, Environmental Protection Plan, as indicated in Attachment 3 to this license amendment.

Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 27 are hereby incorporated into this license. System Energy Resources, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

B.

On page 1 of Appendix C, Antitrust Conditions, chance the phrase "The Mississippi Power & Light Company shall comply with the following antitrust conditions." To "MP&L and SERI shall comply with the following antitrust conditions."

5.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION O'9**f daned by Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications and changes to the Environmental Protection Plan M F (ef 20,1986 D

• Previously concurred:

Date of Issuance:

PD#4/LA PD#4 PD#4/PH ICSB EPB/IE OGC

• M0'Brien

• REMartin

• LKintner:1b

• MSrinivasan FKantor

• Johnson 11/21/86 11/17/868 11/19/86 11/18/86

/ /86 12/19/86 12/08/86 PDl4/D PSB/D PRAB WButler

• GHulman

• Wlambe l'L /g0/86 12/09/86 12/09/86

h

Attachment:

1 November 1, 198*

SERI shall complete the following requirements on the schedule noted below:

l Emergency Response Facilities (Generic Letter 82-33. NUREG-0737 Supplement I 55ER #5)

SERI shall implement the specific items below, in the manner described I

inMP&Lletter(AECM-83/0232) dated April 15, 1983, as modified in MP&L letter (AECM-83/0486) dated August 22, 1983, no later than the following specified dates:

(a) SafetyParameterDisplaySystem(SPDS)

(1) Submit a safety analysis and an implementation plan to the NRC July 1985 (2) SPDS fully operational and Prior to startup operators trained following first refueling outage (b) Detailed Control Room Design Review (DCRDR) 4 (1) Submit a program plan to the NRC December 1984 (2) Submit a summary report to the NRC including a proposed schedule for implew ntation July 1986 1

(c) Regulatory Guide 1.97 - Application to Emergency Response Facilities (1) Submit a report to the NRC describing how the requirements of Supplement 1 to i

NUREG-0737 have been or will be met February 1985 (2) Implement (installation or upgrade)

Prior to startup requirements of R.G. 1.97 with the following first exception of flux monitoring, coolant refueling outage level monitoring, and SLCS flow j

monitoring.*

(3)

Implement (installation or upgrade)

Prior to startup l

requirements of R.G.1.97 for flux following second i

monitoring, coolant level monitoring, refueling outage i

and SLCS flow monitoring.

I (d) Upgrade Emergency Operating Procedures (EOP's)

(1) Submit a Procedures Generation Package l

to the NRC April 1985 i

1 Araendraent No. 27 4

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. (2)

Implement the upgraded E0P's Prior to starttp following the first refueling outage (e) Emergency Response Facilities (1) Technical Support Center fully Prior to startup functional with exception of following the Reoulatory Guide 1.97 first refueling implementation outage (2) Operational Support Center fully Prior to startup functional with exception of following the Regulatory Guide 1.97 first refueling implementation outage (3) Emergency Operations Facility Prior to startup fully functional with exception following the of Regulatory Guide 1.97 first refueling implementation outage a

l

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a 4

l i

i i

Transamerica Delaval Inc. (TDI) Diesel Generator Maintenance and Surveillance Requirements (NUREG-1216. August 1986)

'4 1.

Maintenance and Surveillance Program SERI shall implement and maintain in effect the provisions of the main-l tenance and surveillance program for the TDI emergency diesel generators t

at GGNS Unit I as identified in the MP&L letter dated July 18, 1986 (AECM-86/0172) and as approved in the staff's Safety Evaluation Report i

attached to the NRC letter dated December 9, 1986, subject to the provisions l

of paragraphs 2 and 3 below.

f 2.

Chances f

SERI may make changes to tFe approved maintenance and surveillance l

1 program without prior approval of the Commission provided the changes do i

not adversely affect the operability or reliability of the diesel j

generators or involve changes in the Phase 1 Surveillance requirements of L

paragraph 3 below or otherwise change license conditions.or Technical

. Specifications or result in an unreviewed safety question as, defined in l

10 CFR 50.59. SERI shall maintain in auditable form, a current record of l

(

all such changes, including an analysis of the effects of the change on 1

diesel generator operability and reliability, and shall make such records i

available to NRC inspectors upon request. All chanoes to the program shall be reported annually to the Director of the Office of Nuclear Reactor Regulation, along with the FSAR revisions required by 10 CFR 50.71(e).

\\

l 3.

Phase 1 Component Surveillance Requirements SERI shall comply with the following requirements:

3.1 Connectina Rods

\\

Connecting rod assembl.ies shall be subjected to the following inspections at each major engine overhau1*:

a.-

The surfaces of the rack teeth shall be inspected for signs, of i i

fretting.

If fretting has occurred, it shall be subject to an i i

engineering evaluation for appropriate corrective action.

I i

i The frequency of the major engine overhauls referred to in these requirements shall be consistent with Section IV.1. " Overhaul Frequency" in Revision 2 1

of Appendix II of the Design Review / Quality Revalidation report which was

{

transmitted by MP8L letter dated July 18, 1986.

Amendment No. 27

'y

_l b.

All connecting-rod bolts shall be lubricated in accordance with the engine manufacturer's instructions and torqued to the speci-fications of the manufacturer. The lengths of the two pairs of bolts above the crankpin shall be measured ultrasonically pre and post-tensioning.

The lengths of the two pair of bolts above the crankpin shall c.

i be measured ultrasonically prior to detensioning and disassembly

• of the bolts.

If bolt tension is less than an equivalent of 2400 ft-lbs, the cause shall be detemined, appropriate corrective action shall be taken, and the interval between checks of bolt tension shall be re-evaluated, d.

All connecting-rod bolts shall be visually inspected for thread damage (e.g., galling), and the two pairs of connecting rod bolts above the crankpin shall be inspected by magnetic particle testing (MT) to verify the continued absence of cracking. All washers used with the bolts shall be examined visually for signs of galling or cracking, and replaced if damaged.

A visual inspection shall be perfomed of accessible external e.

surfaces of the link rod box to verify the absence of.any signs of service induced distress.

3 f.

All of the bolt holes in the link rod box shall be inspected for thread damage (e.g., galling) or other signs of abnormalities.

In iddition, the bolt holes subject to the hichest stresses (i.e.,

the pair immediately above the crankpin) shall be examined with an appropriate nondestructive method to verify the continued absence of cracking. Any indications shall be recorded for engineering evaluation and appropriate corrective action.

g.

If the diesel generators are operated in excess of 5740 Kk' steady state, all connecting rods shall be disassembled and inspected at an interval of approximately 5 years coincident with the end of a fuel cycle, except that connecting rod disassembly and inspection is not required for limited post maintenance testing over 5740 KW for the purpose of seating new piston rings as described in the MP&L letter dated December 6,1985 (AECM-85/0395).

3.2 Cylinder Blocks Cylinder blocks shall be inspected for " ligament" cracks, a.

" stud-to-stud" cracks and " stud-to-end" cracks as defined in a

~,

report by Failure Analysis Associates, Inc. (FaAA) entitled,

" Design Review of TDI R-4 and RV-4 Series Emergency Diesel i

Generator Cylinder Blocks" (FaAA report no. FaAA-84-9-11.1) dated December 1984.**

(Note that the FaAA report specifies Transmitted to H. R. Denton, NRC from C. L. Ray, Jr., TDI Owners Group, by letter dated December 11, 1984.

6 i

! i i

additional inspections to be performed for blocks with "known" l

or" assumed"licamentcracks). The inspection intervals (i.e.,

i frequency) shall not exceed the intervals calculated using the cumulative damage index model in the subject FaAA report.

In

' addition, inspection method shall be consistent with or l

equivalent to those identified in the subject FaAA report.

l, b.

In addition to inspections specified in the aforementioned FaAA report, blocks with "known" or " assumed" ligament cracks (as defined in the FaAA report) shall be inspected at each refueling outage to detemine whether or not cracks have initiated on the top surface exposed by the removal of two or more cylinder 4

l heads. This process shall be repeated over several refueling i

outages untti the entire block top has been inspected. Liquid-penetrant testing or a similarly sensitive nondestructive i

testing technique shall be used to detect cracking, and eddy current shall be used as appropriate to detemine the depth of any cracks discovered.

c.

If inspection reveals cracks in the cylinder blocks between j

stud holes of adjacent cylinders (" stud-to-stud" cracks) or

" stud-to-end" cracks, this condition shall be reported promptly to the'NRC staff and the affected engine shall be considered inoperable. The engine shall not be restored to " operable" status until the proposed disposition and/or corrective actions have been approved by the NRC staff.

l 3.3 Cylinder Heads f

The following air roll test shall be performed as specified below, except when the plant is already in an Action Statement of Technical i

Specification 3/4.8.1, " Electric Power Systems. A.C. Sources":

The engines shall be rolled over with the airstart system and with the cylinder stopcocks open prior to each planned start, unless that

- l start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also be rolled over with the airstart system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown.

(In the event an engine is removed from service for any reason other than the rolling over procedure prior to expiration of the 8-hour or 24-hour periods noted above, that engine need not a

be' rolled over while it is out of service. The licensee shall air roll the engine over with the stopcocks open at the time it is returnedtoservice.) The' origin of any water detected in the i

i cylinder must be determined and any cylinder head which leaks due to i

a crack shall be replaced. The above air roll test may be discon-tinued following the first refueling outage subject to the following i

conditions:

i f

f

[ ;

i All cylinder heads are Group III heads (i.e. cast after a.

September 1980.)

b.

Quality revalidation inspections, as identified in the GGNS Design Review / Quality Revalidation Report, Revision 2, have been completed fur all cylinder heads.

Group III heads continue to demonstrate favorable leakage c.

i performance. This should be confirmed with TDI prior to deleting air roll tests.

3.4 Turbocharcers Periodic inspections of the turbochargers shall include the following:

The turbocharger thrust bearings shall be visually inspected for a.

excessive wear after 40 non-prelubed starts since the previous visual inspection, b.

Turbocharger rotor axial clearance shall be measured at each refueling outage to verify compliance with TDI/Elliott specifications.i In addition, thrust bearing measurements shall be compared with measurements taken previously to determine a i

need for further inspection or corrective action.

Spectrographic and ferrographic engine oil analysis shall be c.

performed quarterly to provide early evidence of bearing degradation. Particular attention shall be paid to copper level and particulate size which could signify thrust bearing degradation.

i d.

The nozzle ring components and inlet guide vanes shall be visually inspected at each refueling outage for missing parts or parts showing distress.

If such are noted, the entire ring i

assembly shall be replaced.

4 e

i i

e l

i N

4

ATTACHPENT 3 TO LICENSE AMENDMENT NO. 27 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix "A" Technical Specifications and the Appendix B Environmental Protection Plan with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Technical Specifications Remove Insert 6-3 6-3 6-9 6-9 Environmental Protection Plan Remove Insert Title page Title page 1-1 1-1 4-2 4-2 3

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I GRAND GULF-UNIT 1 6-3 Amendment No. 27

'l 1

l ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW COMMITTEE (SRC)

FUNCTION 6.5.2.1 The SRC shall function to provide independent review and audit of designated activities in the areas of:

a.

nuclear power plant operations b.

nuclear engineering !

c.

chemistry and radiochemistry d.

metallurgy e.

instrumentation and control f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practices COMPOSITION 6.5.2.2 The SRC shall be composed of the:

Chairman:

Vice President, Nuclear Operations Member:

Vice President, Nuclear Engineering & Support Member:

Director, Nuclear Plant Engineering Member:

Site Director, GGNS Member:

Director, Quality Assurance Member:

Designated l Representative, Middle South Services, Inc.

Member:

GGNS General Manager Member:

Director, Nuclear Licensing and Safety Member:

Manager, Radiological and Environmental Services Member:

Principal Engineer, Operations Analysis 4

Two or more additional voting members shall be consultants to System Energy l

Resources, Inc. consistent with the recommendations of the Advisory Committee I

on Reactor Safeguards letter, Mark to Palladino dated October 20, 1981.

The SRC members shall hold a Bachelor's degree in an engineering or physical science field or equivalent experience and a minimum of five years of technical experience of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.la through h.

In the aggregate, the membership of the committee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h.

ALTERNATES l

6.5.2.3 All alternate members:shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities 'at any one time.

GRAND GULF-UNIT 1 6-9 Amendment No. 27

a APPENDIX B TO FACILITY LICENSE NO. NPF-29 h

GRAND GULF NUCLEAR STATION UNIT I SYSTEM ENERGY RESOURCES, INC.

l DOCKET NO. 50-416 ENVIRONMENTAL PROTECTION PLAN 4

OCTOBER 1984 I

4 Amendment No. 27

~

• - 1.0 CBJECTIVES OF THE ENVIRONMENTAL PROTECTION PLAN The Environmental Protection Plan (EPP) is to provide for protection of environmental values during construction and operation of the nuclear facility.

The principal objectives of the EPP are as follows:

1 (1) Verify that the Plant is operated in an environmentally acceptable manner, as established by the FES and other NRC environmental impact assessments.

(2) Coordinate NRC requirements and maintain consistency with other Federal, State and local requirements for environmental protection.

(3) Keep NRC informed of the environmental effects of facility construction and operation and of action taken to control those effects.

Environmental concerns identified in the FES which relate to water quality matters are regulated by way of the GGNS NPDES permit.

k

(

1-1 Amendment No. 27

by the aerial surveys, and walking patrols will be directed to the problem areas to evaluate the extent of the problem to be corrected.

The Erosion Control Inspection Program shall begin upon commencement of normal.

transmission line inspection procedures.

Semi-annual surveys shall continue until stabilization of soil and vegetation (i.e., ground cover establishment) is achieved.

A summary of the field inspection program and any procedures implemented to control abnormal erosion conditions assoicated with transmission line mainw tenance activities shall be reported in the Annual Environmental Operation Report in accordance with Subsection 5.4.1.

Field logs indicating locations of erosion damage and measures taken to rectify erosion problem areas and estimation of the time to achieve effective stabilization will be maintained and available for inspection for a period of two years.

Results reported shall contain information encompassing but not limited to inspection,date, estimated size of erosion problem area, probable cause of erosion, type of stabilization program, and date of effective stabilization, as appropriate.

4.2.2 Cooling Tower Drift Program Seven sampling sites will be utilized to measure cooling tower drift-deposition.

At least two of the sampling sites will have duplicate sampling devices.

Six of the seven sampling sites will be located in areas where maximum salt deposition is predicted. These areas were extrapolated from the Bechtel Salt Deposition s

Model developed for the SERI Final Environmental Report.

The seventh sampling l

site will be a control site located south of Raymond, Mississippi.

l

' Fallout samples will be collected using buckets with a known volume of deionized water in each.

The buckets will be located four to six feet above the ground, fitted with bird rings, and covered with fine mesh screens to exclude leaves and insects. The samples will be collected on a quarterly basis and analyzed for calcium, magnesium, sodium, f ron, phosphates, nitrates, chloride, fluorides, sulfates, and total dissolved solids.

These parameters were selected because-past analyses have shown them to be prevalent in the coo. ling tower source water.

The results of these analyses will be correlated with local rainfall data and

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l 4-2 Amendment No. 27

-