ML17319A602

Amends 40 & 23 to Licenses DPR-58 & DPR-74,respectively, Revising Unit 1 Tech Specs Re Refueling Water Tank Operating Temp & Discharge Scour Bed Protection & Units 1 & 2 Plume Measurements of Water Discharge

ML17319A602
Person / Time
Site:	Cook
Issue date:	08/29/1980
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML17319A603	List: ML17319A602 ML17319A604 ML17319A605
References
NUDOCS 8009240084
Download: ML17319A602 (37)

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'UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20556 August 29, 1980 Docket Nos.

50-31 5 and 50-316 Mr. John Dolan, Vice President Indiana and Michigan El ectri c Company Post Office Box 18 Bowl ing Green Station New York, New York 10004

Dear Mr. Dolan:

The Commission has issued the enclosed Amendment No. 40 to Facil ity Operating License No.

DPR-58 and Amendment No.

23 to Facility Operating License No. DPR-74, respectively.

The amendments consist of changes to the Technical Specifications in response'to your letters dated April 6, 1979 (as supplemented September 13, 1979),

November 2, 1979 and April 3, 1980.

These amendments revise the Appendix A Technical Specifications to increase the minimum water temperature of the Unit No.

1 refueling water storage tank to 70'F and revise the Appendix B Technical Specifications to administratively eliminate the requirement for further thermal discharge plume studies and to administratively revise the scour studies to reflect the Unit No.

1 design modification proposed to repair damage caused by the high velocity plant discharges

'n accordance with the provisions 'of Environmental Technical Specifications Section 4.1.1.4 the NRC staff has reviewed and hereby approves the corrective

. ction you have proposed in your April 6, 1979 letter as supplemented

'n September 13, 1979, to correct the deficiencies found in the Unit No.

scour bed protection.

As, required by ETS Section 4.1.1.4, as revised, y,u are to conduct studies to verify the adequacy of this modified

cour bed and report the results in the Annual Operating Report.

At

'..ast'one full year of operating with the modified scour bed shall be

.v r d in these studies, as is considered with ETS Section 4.1.1.4, as

".vised.

No further approval is required to, adopt this modification to

> I>nit No.

2 scour protection.

gp 09340 084

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Mr. 'John Dolan Indiana and Michigan Electric Company August 29, l980 Copies of the Safety Evaluation and Environmental Impact Appraisal and the Notice of Issuance and Negative Declaration are also enclosed.

Sincerely, teven A. Varga, hief Operating Reactors Branch 81 Division of Licensing

Enclosures:

l.

Amendment No.

40 to DPR-58 2.

Amendment No.

23 to DPR-74 3.

Safety Evaluation and Environmental Impact Appraisal 4.

Notice of Issuance and Negative Declaration cc:

w/enclosures See next page

lhr.'ohn Do)an Indiana and Michigan Electric Company August 29, 1980 cc:

Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

Washington, D.

C.

20036 Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maude Preston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 Mr. D. Shaller, Plant Manager Donald C.

Cook Nuclear Plant P. 0.

Box 458

Bridgman, Michigan 49106 U. S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensvi lie, Michigan 49127 Mr.

Wade Schuler, Supervisor Lake Township

Baroda, Michigan 49101 Mr. William R.

Rustem (2)

Office of the Governor Room 1 - Capitol Building

Lansing, Michigan 48913 Honorable James

Bemenek, tlayor City of Bridgman, Michigan 49106 Director, Technical Assessment Division Office of Radiation Programs (AW-459)

U. S. Environmental Protection Agency Crystal Mall 42 Arlington, Virginia 20460 U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN' I S COORD INATOR 230 South Dearborn Street Chicago, Illinois 60604 Maurice S. Reizen, Y:.0.

Director Department of Public Health P. O..Box 30035'ansing, Michigan 48909 Villiam J.

Scanlon, Esquire 2034 Pauline Boulevard Ann Arbor, Michigan 48103

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UNITEDSTATES t NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20666 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE.

Amendment No.

40 License No.

DPR-58 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

E.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated April 6, 1979 (as supplemented on September 13, 1979

, and November 2, 1979, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8009340 084

/

't 2.'

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-58 is hereby amended to read 'as follows:

(2)

Technical S ecifications The Technical Spe'cifications contained in Appendices A and',

as revised through Amendment No.

40, are hereby incorporated in the license.

. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications i fu.

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0 tev n A. Varga, i ef Operating Reactors Branch Pl Division of Licensinq Date of Issuance:

August 29, 1980

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Al'TACHMENT TO LICENSE AMENDMENT N0.40 FACILITY OPERATING LICENSE NO.

DPR-58 DOCKET NO. 50-315 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of chance.

The corresponding overleaf pages are also provided for document completeness.

~Pe es 3/4 1-16 3/4 1-17 3/4 5-10 B3/4 5-3 {added)

D.

C.

Cook - Unit 1

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'I REACTIVITY CONTROL SYSTEMS BORATED INTER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be OPERABLE:

I a.

A boric acid storage system and associated heat tracing with:

1.

A minimum contained volume of 5170 gallons, 2.

Between 20,000 and 22,500 ppm of boron, and 3.

A minimum solution temperature of 145 F.

I b.

The refueling water storage tank with:

l.

A minimum contained volume of 350,000 gallons of water, I

2.

A minimum boron concentration of 1950

ppm, and 3.

A minimum solution temperature of 70'F.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

a b.

With the boric acid storage system inoperable, restore the storage system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a

SHUTDOWN MARGIN equivalent to at least lX rk/k at 200'F; restore the boric acid storage system to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour 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 SHUT-DOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS 4.1.2.8 Each borated water source shall be demonstrated OPERABLE:

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COOV. - UNIT 1

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3/4 1-16 i

Amendment No.

40

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE UIREMENTS Continued a.

At least once per 7 days by:

l.

Verifying the boron concentration in each water source, 2.

Verifying the water level of each water source, and 3.

Verifying the boric acid storage system solution temperature.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RllST temperature when the outside air.temperature is less than 70'F.

D.

C.

COOK - UNIT 1

3/4 1-17 Amendment No.

40

REACTIVITY CO>TROL SYSTEMS r

3/4.1. 3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rods which are inserted in the core, shall be OPERABLE and positioned within + 12 steps (indicated position) of their bank demand position.

APPLICABILITY:

MODES 1* and 2*

ACTION:

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b.

C.

With one or more full length rods inoperable due to being "immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1

hour and 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 />.

With more than one full length rod inoperable or misaligned from the bank demand position by more than

+ 12 steps (indicated position),

be in HOT STANDBY wi thin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With one full length rod inoperable or misaligned from its group step counter demand height by more than

+ 12 steps (indicated position),

POWER OPERATION may continue provided that within one hour either:

1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement. of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

a)

An analysis of the potential ejected rod worth is performed within 3 days and the rod worth is deter-mined to be

< 0.75%

ak at zero power and

< 0.38

hk at RATED THERMAL POWER for the remainder of the fuel cycle, and b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and "See Special Test Exceptions 3..10.2 and 3,10.4.

C.

COOK - UNIT 1

3/4 1-18 Amendment No.

7$,28

EMERGENCY CORE COOLING SYSTEMS HEAT TRACING LIMITING CONDITION FOR OPERATION r

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3.5.4.2 At least two independent channels of heat tracing shall be OPERABLE for the boron injection tank and f'r the heat traced portions of the associated flow paths.

APPLICABILITY:

NODES 1, 2 and 3.

ACTION:

With only one channel of heat tracing on either the boron inject'ion tank or on the heat traced portion of an associated flow path

OPERABLE, operation may continue for up to 30 days provided the tank and flow path temperatures are verified to be

> 145'F at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; otherwise, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.5.4.2 Each heat tracing channel for the boron injection tank and associated flow path shall be demonstrated OPERABLE:

a.

b.

At least once per 31 days by energizing each heat tracing

channel, and At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the tank and flow path temperatures to be

> 145 F.

The tank temperature shall be determined by measurement.

The flow path temperature shall be determined by either measurement or recirculation flow until establishment of equilibrium temperatures within the tank.

D.C.COOK-UNIT 1

3/4 5-9

F I

EMERGENCY CORE COOLING SYSTEMS REFUELING WATE:i STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.5 The refueling water storage tank (RWST) shall be OPERABLE with:

a.

A minimum contained volume of 350,000 gallons of borated water.

b.

A minimum boron concentration of 1950

ppm, and c.

A minimum water temperature of 70'F.

APPLICABILITY:

NODES 1, 2, 3 and 4.

ACT 10M:

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within 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 />.

SURVEILLANCE RE UIREMENTS 4.5.5 The RWST shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

l.

Verifying the water level in the tank, and 2.

Verifying the boron concentration of the water.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is less than 70'F.

. COOK-UNIT 1

3/4 5-110 Amendment No, 40

EMERGENCY CORE COOLING SYSTEMS BASES

'he contained water volume limit includes an allowance for water not usable because of,tank discharge line location or other physical characteristics.

The limits on contained water volume and boron. concentration of the RWST also ensure a

ph value of 'between 8.5'and 11.0 for tf.e solution recirculated within containment after a LOCA.

This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The ECCS analyses to determine F

limits in Specifications 3.2.2 and 3.2.6 assumed a

RWST water temperature of 70'F.

The temperature value of the RWST water determines that of the spray water initially delivered to the'containment following LOCA. It is one of the factors which determines the containment back-pressure in the ECCS analyses, performed in accordance with the provisions of 10 CFR 50.46 and Appendix K to 10 CFR 50.

D.

C.

COOK - UNIT 1

B 3/4 5-3 Amendment No. 40

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0 J7 fy*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINOTON, D. C. 20665 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET No. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

23 License No.

DPR-74 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated April 6, 1979 (as supplemented September 13, 1979, complies with the standards and require-ments 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission:

C, D.

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 Commission's regulations; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the ComIission's regulations and all applicable requirement;s have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C,(2) of Facility Operating License No.

DPR-74 is hereby amended to read as follows:

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 23, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

, B.g te en A. Varga, i ef Operating Reactors Branch A'1, Division of Licensing

Attachment:

Changes to the Technical Soecifications Date of Issuance:

August 29, 1980

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO.

DPR-58 AMENDMENT NO. 23 TO FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NOS. 50-315 AND 50-316 Revise Appendix A as follows:

Remove Pa es ETS 4.1-1 ETS 4.1-2 ETS 4.1-3 ETS 4.1-4 ITS 4.1-5 ETS 4.1-6 ETS 4.1-8 ETS 4.1-9 Insert Pa es

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ENVIRONMENTAL SURVEILLANCE 4.1 ECOLOGICAL SURVEILLANCE A

1 icabil it and Ob'ective of Environmental Surveillance The nonradiological environmental monitoring program applies to the monitoring of lake water temperature distribution, Plant discharge of chemicals, lake bottom scouring, beach erosion, biological'ariables in Lake Michigan and'on the Plant site itself, to the specifications for onsite and offsite restoration and maintenance of transmission line rights-of-way.

The objectives of the program are to determine (1) the relationship between the thermal plant discharge and the physical and biological characteristics of the lake water masses in the vicinity of the Plant site; (2) the aquatic ecology of this portion of the lake (South-eastern 'corner of Lake Michigan from the St.

Joseph River to Trail Creek in Michigan City, Indiana);

(3) the effects of the operation of the Donald C.

Cook Nuclear Plant on the physical, chemical, and biological variables of this portion of Lake Michigan and the Plant site including the beach; and (4) to minimize adverse impacts on terrestrial and aquatic biota within and adjacent to transmission rights-of-way.

4.1.1 ABIOTIC 4.1.1.1 B iocides A program for measuring or calculating the chlorine residual at the point of discharge to the lake is given in Specification 2.2.1.

4.1.1.2 Thermal Characteristics This section has been deleted.

F ETS 4.1-1 Amendment No. 40, Unit No.

1 Amendment No. 23, Unit No.

2

TMIS PAGE INTENTIONALLY LEFT BLANK ETS 4.1-2 Amendme'nt No. 40, Unit No.

1 Amendment No. 23, Unit No.

2

THIS PAGE INTENTIONALLY LEFT BLANK ETS 4.1-3 Amendment No. 40, Unit No. I Amendment No. 23, Unit No.

2

TMIS PAGE INTENTIONALLY LEFT BLANK ETS 4.1-4 Amendment No, 40, Unit No.

1 Amendment No. 23, Unit No.

2

THIS PAGE INTENTIONALLY LEFT BLANK ETS 4.1-5 Amendment No. 40, Unit No.

1 Amendment No. 23, Unit No.

2

THIS PAGE INTENTIONALLY LEFT BLANK ETS 4.1-6 Amendment No. 40, Unit No.

1 Amendment No. 23, Unit No.

2 r

Basis

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'he beach e'rosion monitoring program ~.ill attempt to verify the contention that ice buiding mechanisms will operate to repai r any ice-melting caused by the. discharge plume.

In addition, monitoring enables determination o

beach and near shore erosion direct effects of Plant discharges and direct or indirect effects of scour bed or protective pilings placed on shore or in the lake.

4.1.1.4 Scour Studies Ob ectives The scour monitoring orogram is intended to determine the adequacy of the scour bed bottom protection and to ensure that significant iona-or short-term scour does not result from the high velocity Plant discharge or from sediment displacement, by along-shore

currents, in areas adjacent to the scour bed.

Soecification A sounding study shall be conducted at 100 foot intervals from a point near the beach approximately 300 feet south of the discharge scour bed to a point 300 feet north of the extremity of the same scour bed.

Soundirg lines shall run paral1el to the actua1 pipelines, essentially east-west, from the near

shore, terminating about 400 feet west of tne intake cribs.

Readings shall be taken by a continuous recording fathometer (or instruments of equal or better accuracy) whose accuracy shall be at least to within a foot.

The sounding grid shall comprise a rectangle approximately 1,400 feet wide by 2,400 feet long, or shall encompass an area, larger or smaller, deemed necessary by the licensee to meet the objectives stated above.

Baseline surveys shall be conducted following issuance of an operating

license, but prior to testing of cooling water circulating pumps for b~'t No.

1; thereafter a survey shall be run at approximately 6-montn intervals until at least 1 full year following the startup of Unit No.

2 and for at least one full year following modifications or major repair of the scour bed Drotection.

Studies conducted to verify the adequacy of the scour bed (or modifications thereto) in preventing bottom scouring by the high velocity Plant discharge shall also describe the effects of the scour ETS 4.1-g Amendment No.

40 Unit 1

Amendment Ho.

23 Unit 2

bed on any movement, or displacement, of material moved by alongshore currents in the vicinity arid to the south and north of the scour beds.

Pesults of all monitoring or special studies necessary for model verification and demonstration of the effect of scour beds on along shore transport of sediment shall be reported in the annual Operating Reports.

If bottom scouring or erosion resulting from the high velocity discharge and/or implacement oi'ge protective scour bed occurs, and if judged to be significant by the staff, 1) the licensee shall submit plans for corrective action to the staff for approval and 2) implementation of any approved action shall be met by the time schedule specified.

Should the scour study indicate loss of function of the scour bed, the licensee would initiate an Engineering investigation to repai r the bottom protection in an appropriate fashion.

The licensee shall submit plans for corrective action to the Office of Nuclear Reactor Requlation for review and approval.

A schematic view of the scour study area is shown in Figure 4.1.1.4-1.

Pe ortin Re uirements As specified above and in Section 5.4.

Easis Sfter extensive study, a jet diffuser system was developed, with a jet velocity of 13-ft/sec selected on the basis of experimentation with a lydraulic model, to reduce the temperatures in the thermal-affected zone and to minimize the exposure of entrained organisms to heated lake water.

Because of the relatively high velocity of the cooling water at the exit ports of the discharge structure, an extensive scour protective bed has been installed.

The subject scour studies are to verify that there are no scour problems resultina from Plant discharges or implacement of the riprap scour bed in the lake.

4.1.1.5 Groundwater I

~05'ective To monitor the movement of chemicals introduced into the groundwater from the onsite absorption field.

The hydraulic properties of groundwater such as direction and velocity of flow will also be monitored.

ETS 4.1-9 Amendment No.

40 Unit 1

Amendment No.

Unit 2