ML17329A103

Proposed Tech Specs Re Spent Fuel Storage

ML17329A103
Person / Time
Site:	Cook
Issue date:	07/26/1991
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17329A102	List: ML17329A101 ML17329A103 ML20091C015
References
NUDOCS 9108050008
Download: ML17329A103 (89)

Text

ATTACHMENT 1 TO AEP:NRC: 1146 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C.

COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS 9108050008 910726 PDR ADOCK 05000315 P

PDR

0

"ATTACHMENT 1 to AEP:NRC:1146 Page 1

1.0 Sections to be Chan ed A.

Unit 1 1.

License Condition 2.c(5)

- page 4 of 6 2.

T/S 3/4.9.3

- page 3/4 9-3 3.

T/S 3/4.9.15

- page 3/4 9-19 4.

T/S 5.6.1.1.b

- page 5-5 5.

T/S 5.6.1.1.c

- page 5-5 6.

T/S Figure 5.6 page 5-5a 7.

T/S 5.6.1.2

- page 5-6 8.

T/S 5.3.1

- page 5-4 9.

T/S 5.6.4

- page 5-7 B.

Unit 2 1.

License Condition 2.c(3)(S)

- page 6 of ll 2.

T/S 3/4.9.3

- page 3/4 9-3 3.

T/S 3/4.9.15

- page 3/4 9-18 4.

T/S 5.6.1.l.b

- page 5-5 5.

T/S 5.6.1.1.c

- page 5-5 6.

T/S Figure 5.6 page 5-5a 7.

T/S 5.6.1.2

- page 5-5 8.

T/S 5.3.1

- page 5-4 9.

T/S 5.6.4

- page 5-6 The changes requested allow more compact storage of spent fuel (to be accomplished by the reracking),

and achieve consistency with the assumptions of the thermal-hydraulic and criticality analyses performed by Holtec International.

The changes, which are discussed below, accomplish the following:

1.

Increase the authorized storage capacity of the storage pool (changes

¹1 and ¹9, above).

2.

Increase the amount of time the reactor must be subcritical before refueling (changes ¹2, above).

3.

Change the applicability condition for spent fuel pool boron concentration requirements (changes ¹3, above).

4.

Decrease the nominal center-to-center distance between fuel assemblies placed in the storage racks (changes ¹4, above).

5.

Modify the burnup and enrichment storage configuration requirements for fuel assemblies (changes

¹5 and ¹6, above).

ATTACHMENT 1 TO AEP:NRC'1146 Page 2

6.

Increase the maximum nominal fuel assembly enrichment for Exxon/ANF fuel assemblies stored in the spent fuel pool (changes ¹7, above).

7.

Achieve consistency between the maximum enrichment limit of fuel assemblies throughout the T/Ss (changes ¹1 and ¹8, above).

3.0 S ec c Chan es Re uested (The change numbers in the following discussion refer to those in Section 1.0, above.)

¹1,

¹9.

The authorized storage capacity of the spent fuel pool is increased from 2050 to 3613 assemblies.

Additionally, a currently worded the license conditions allow storage of Unit 1 or Unit 2, new or irradiated assemblies,

~i

~an combination.

We are proposing to strike the words "in any combination," to reflect storage configuration restrictions discussed under changes ¹5 and ¹6.

Lastly, we are indicating that the 4.95 wt.

0 U-235 enrichment limit is a nominal value.

¹2

~

The amount of time the reactor must be subcritical before movement of irradiated fuel is increased from 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> to 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.

¹3.

As presently worded, T/S 3.9.15 requires a minimum 2,400 ppm of boron in the spent fuel pool whenever fuel assemblies with enrichment greater than 3.95 weight percent U-235 and with burnup less than,5,550 MWD/MTU are in the spent fuel pool.

We are proposing to change this applicability to "at all times."

The nominal center-to-center distance between fuel assemblies placed in the storage racks is decreased from 10.5 inches to 8.97 inches.

¹5,

¹6.

The current storage configuration restrictions for storage of Westinghouse fuel with nominal enrichment greater than 3.95 weight percent U-235 and burnup less than 5,550 MWD/MTU are superseded.

The present 2 regions are replaced with 3 regions.

The definitions of the regions are no longer dependent on fuel vendor (Westinghouse vs.

Exxon/ANF.)

Two options for storage patterns are provided as Figures 5.6-1 and 5.6-2 of the proposed T/S.

A graphical representation, of the regional definitions is provided as Figure 5.6-3 of the proposed T/S.

¹7.

The maximum nominal fuel assembly enrichment for fuel

ATTACHMENT 1 TO AEP:NRC:1146 Page 3

. stored in the..spent fuel pool racks is increased from 3.50 to 4.95 wt.

0 U-235 for Exxon/ANF 15 X 15 assemblies, and from 4.23 to 4.95 wt.S U-235 for Exxon/ANF 17 X 17'ssemblies.

¹8.

The enrichment limit for Unit 2 fuel assemblies is modified to indicate that the 4.95 wt.

0 value is a nominal value.

The Unit 1 enrichment is modified from 4.0 wt.

0 U-235 to a nominal value of 4.95 wt.

0 U-235.

The present spent fuel pool racks allow storage of up to 2050 assemblies.

This includes 193 storage locations designated for a full core off-load, should this become necessary.

With the anticipated refueling outage

schedule, the full core off-load capability will be lost in early 1995 and nominal refueling discharge capability (80 assemblies) willbe lost in 1996.

The"full core off-load capability could, however, be lost as early as 1994 depending upon unit operation and the necessity to store miscellaneous

items, such as old thimble

tubes, in storage cells in the spent fuel pool.

Our review of the various options available led to the conclusion that increasing the storage capacity of'the existing storage pool represents the least cost option.

As discussed in the cover letter, the NRC has determined, in NUREG 0575, that this option involves minimal environmental impact.

\\

We are proposing to.increase the storage capacity of the pool from 2050 assemblies to 3613 assemblies.

The existing racks will be replaced with 23 free-standing poisoned rack modules.

These modules contain a total of 3616 storage cells, including

,3 triangular cells located in corners of the pool.

The reracking will extend the date until loss of full core discharge capability through the year 2008. contains a licensing report on the reracking prepared by our contractor, Holtec International.

The report contains the following chapters:

1.

Introduction 2.

Module Data 3.

Construction of Rack Modules 4.

Criticality Safety Analyses 5.

Thermal-Hydraulic Considerations 6.

Rack Structural Considerations 7.

Accident Analysis and Miscellaneous Structural Evaluations 8.

Static and Dynamic Analyses of Fuel Pool Structure Radiological Evaluation 10.

In-service Surveillance Program

ATTACHMENT 1 TO AEP:NRC:1146 Page 4

Cost/Benefit Analysis Justi cation for Chan es (The change numbers in the following discussion refer to those in Section 1.0, above.)

¹1,

¹9.

The increase in the storage capacity from 2050 to 3613 assemblies is the purpose of the reracking effort and is supported by the Holtec Licensing Report.

The spent fuel pool will contain 3616 storage locations after reracking.

Three of these locations are triangular in shape and therefore will not hold a complete assembly.

Thus, the total complete assembly storage capacity is 3613 assemblies.

Ve have also proposed to modify the wording of the license conditions such that the conditions no longer permit storage of fuel "in any combination."

As discussed in changes'¹5 and ¹6, there are limits to placement of fuel in the new racks based on initial assembly enrichment and burnup.

" The change to indicate that the 4.95 wt.

8 U-235 enrichment limit is a nominal value is an editorial

change, to more accurately describe the limit and be consistent with T/S 5.6.2.2.

¹2.

The amount of time the reactor must be subcritical before movement of irradiated fuel is conservatively increased from 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> to 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.

This is to achieve consis-tency with the thermal-hydraulic analyses performed by Holtec, discussed in Chapter 5 of the licensing report.

(The fuel handling accident analysis, presented in Chapter 9 of the Holtec report, assumed 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of decay time.

This is conservative with respect to the proposed change.)

¹3

~

The applicability for the requirement to maintain 2,400 ppm of boron in the spent fuel pool is modified from "whenever fuel assemblies with enrichment greater than 3.95 wt.

0 U-235 and enrichment greater than 5,550 MWD/MTU are in the fuel storage pool" to "at all times."

The criticality analyses demonstrate k ~g less than 0.95 in the racks with no boron in the spent fuel pool.

Credit for soluble boron is necessary only for abnormal events such as mislocation of a fuel assembly.

The previous criticality analyses, approved by T/S Amendments 136 (Unit 1) and 121 (Unit 2), determined that no soluble boron was necessary to maintain k gg below 0,95 for the case of a misloaded fuel assembly, provided the initial

ATTACHMENT 1 TO AEP:NRC:1146 Page 5

assembly enrichment was below 3.95 wt.

0 U-235 and the assembly burnup was greater than 5,550 MWD/MTU.

The applicable criticality analyses presented in Chapter 4 of the Holtec report conservatively assumed all assemblies were enriched to 4.95 wt.

8 U-235, and did not establish a burnup beyond which soluble boron was unnecessary.

Therefore, we are conservatively changing the applicability requirement of the soluble boron T/S to "at all times."

The nominal center-to-center spacing between fuel assemblies placed in the storage racks is decreased from 10.5 to 8.97 inches.

This is consistent with the design of the new racks and has been used in the various Holtec analyses.

¹5, The present T/S establishes limits on acceptable storage

¹6.

locations for Westinghouse fuel with nominal enrichment above 3.95 wt% U-235 and with burnup less than 5,550 MWD/MTU.

Storage of assemblies meeting these require-ments must be in a checkerboard configuration.

We are proposing to supersede these requirements with new requirements that are consistent with the criticality analyses presented in Chapter 4 of the Holtec report.

Three "regions" of fuel are defined.

The regions are determined on the basis of burnup and initial assembly enrichment.

(Ref: Section 4.2 of the Holtec report.)

Proposed T/S Figure 5.6-3 includes a graphical depiction of the 3 regions.

Two fuel assembly layout schemes are included in the proposed T/Ss, as Figures 5.6-1 and 5.6-2.

The first is a scheme whereby all cells can be filled. A second scheme is included which more easily facilitates a full core 'off-load.

This scheme is considered an "interim" scheme, which may be used before the pool is approaching its full capacity.

These two loading, schemes are discussed in Section 4.2 of the Holtec report.

Loading of assemblies into either scheme

,. willbe administratively controlled by Cook Nuclear Plant Procedures.

¹7.

The maximum nominal fuel assembly enrichment for fuel stored in the spent fuel pool racks is increased from 3.50 to 4.95 wt.

0 U-235 for Exxon/ANF 15 X 15 assemblies, and from 4.23 to 4.95 wt.

0 U-235 for Exxon/ANF 17 X 17 assemblies.

Holtec determined that the Westinghouse 15 X 15 assemblies with initial enrichment of 4.95 Wt 0 U-235 was the most reactive fuel type.

This assembly was therefore used as the "design basis" fuel assembly for the criticality analyses in Section 4 of the Holtec report.

In making this

k

ATTACHMENT 1 TO AEP:NRC:1146 Page 6

conservative determination, Holtec considered all fuel types listed in the present T/S 5.6.1.2, assuming nominal enrichments of 4.95 wt.

0 U-235.

Therefore, the criticality analyses bound the Exxon/ANF fuel assemblies for enrichments up to 4.95 wt.

0 U-235*.

The nominal enrichment of 4.95 wt.

8 U-235 is also consistent with the fuel handling accident evaluation assumptions, documented in Section 9.1 of the Holtec report.

¹8.

The enrichment limit is expressed as a nominal value to achieve consistency throughout the T/Ss (see the justification for change ¹2, above).

The change in the

'Unit 1 T/S 5.3.1 enrichment limit from 4.0 to 4.95 wt.

U-235 is intended to achieve consistency with Unit 2 T/S 5.3.1.

The limit on fuel assembly enrichment has historically been maintained consistent with the T/S 5.6.1.2 spent fuel pool limits.

In Unit 2, for example, the highest enrichment for 17 X 17 assemblies in T/S 5.6.1.2 is 4.95 wt. 0, which matches the Unit 2 T/S 5.3.1 value.

(Currently, the highest enriched Unit 2 assemblies are only 4.13 nominal wt.

8 U-235.

Assemblies with nominal 4.4 wt.

0 U-235 enrichment are,

however, planned to be loaded in 1992).

In Unit 1, however, the highest enrichment for 15 X 15 assemblies is 4.95 wt.

0 U-235 in T/S 5.6.1.2, but T/S 5.3.1 has an enrichment limit of 4.0 wt.

0 U-235.

(Currently, the highest enriched Unit 1 assemblies are only 3.6 nominal wt.

8 U-235.)

This administrative change corrects an oversight in our letter AEP:NRC:1071F, dated December 8, 1989, which proposed the T/S changes that were approved as Amendment 136 for Unit 1 and 121 for Unit 2.

5.0 No Si i icant Hazards Determinat'o We have evaluated the proposed T/S changes and have determined that the changes should not involve a significant hazards consideration based on the criteria established in 10 CFR 50.92(c).

Operation of the Cook Nuclear Plant in accordance with the proposed amendment will not:

• We are currently purchasing fuel assemblies from Westinghouse.

There are currently no Exxon/ANF assemblies in either the spent fuel pool or the reactors with nominal enrichments greater than 4.1

4 l

ATTACHMENT 1 TO AEP'NRC'1146 wt 8 U-235.

Page 7

(1) vo ve a S

ca t c ease t e P obabi Conse uences of an Accident Previousl Eve uated.

The analyses performed by Holtec have demonstrated the acceptability of the proposed reracking from a variety of perspectives.

For example, the analyses demonstrate that g~~ will remain within acceptable limits even if an abnormal event, such as a fuel assembly misloading or assembly drop, should occur.

Xt has also been demonstrated that the spent fuel pool cooling system is adequate to maintain acceptable cooling of the stored assemblies, and that adequate time would exist to take appropriate corrective action should all cooling be inadvertently lost.

The racks are designed to seismic Class l requirements.

An assembly dropped on the racks would not distort the racks such that they would not perform their function.

The radiological consequences of a fuel handling accident remain within previously established limits.

During the reracking effort, all movement of fuel assemblies and racks willbe performed in accordance with our commitments to NUREG 0612, entitled "Control of Heavy Loads At Nuclear Power Plants."

Thus, the probability of an accident involving assembly damage will not significantly be increased.

Based on these considerations, it is concluded that the probability or consequences of a'previously evaluated accident is not significantly increased.

(2)

C cate the Poss b i o

a New or Di ere t Kind o Acc dent rom An Prey ousl Anal zed.

No unproven technology is involved either in the installation process or in the analytical techniques necessary to justify the planned fuel storage expansion.

Zn fact, the basic reracking technology has been developed and demonstrated in over 80 applications for fuel pool capacity increases which have already received NRC approval.

The change to a mixed zone storage in the spent fuel pool requires the performance of additional evaluations to ensure that the criticality criteria is maintained.

These include the evaluation for the limitingcriticality condition, i.e., misplacement of an unirradiated (fresh) fuel assembly into a burned fuel storage cell.

The

ATTACHMENT 1 TO AEP:NRC:1146 Page 8

evaluation for this case shows that when the boron concentration is at least 550 ppm, the criticality criterion is satisfied.

We have proposed a T/S change to require 2,400 ppm boron, at all times, in the spent fuel pool.

Therefore, protection against inadvertent mispositioning will be ensured.

During installation all movement of spent fuel pool

'assemblies and racks will be in accordance with our commitments to NUREG 0612, to prevent any damage to fuel assemblies stored in the spent fuel pool.

Based on the foregoing discussion, it is concluded that the reracking does not create the possibility of a new or different accident from any previously evaluated.

(3)

Involve a Si nificant Reduction in a Ma n o Safet The Holtec report demonstrates the acceptability of the reracking from a variety of perspectives, including criticality, thermal-hydraulic, radiological,

seismic, and structural considerations.

The results of these analyses provide the basis for our conclusion that the changes do not involve a significant reduction in a margin of safety.

We note that the NRC has published examples of amendments considered not likely to involve significant hazards considera-tion in the Federal Register (Volume 51, No. 44, March 6, 1986).

The tenth example concerns an expansion of the storage capacity of a spent fuel pool, and specifies criteria that must be satisfied.

The storage expansion method consists of either replacing existing racks with a design which allows closer spacing between stored spent fuel assemblies or placing additional racks of the original design on the pool floor if space permits.

~Res ense:

The Cook Nuclear Plant fuel pool reracking involves both replacing existing and adding new racks where space permits.

C te o

The storage expansion method does not involve rod consolidation or'ouble-tiering.

~Res o se:

The Cook Nuclear Plant racks are not double-tiered and all racks willsit on the spent fuel pool floor. Additionally, the amendment

ATTACHMENT 1 TO AEP:NRC:1146 Page 9

application does not involve consolidation of spent fuel.

The k gg of the pool is maintained less than or equal to 0,95.

~Rs onse:

The design of the new spent fuel racks contains a neutron absorber,

Boral, to allow close storage of spent fuel assemblies while ensuring that the k fg remains less than 0.95 under normal conditions with pure water in the pool, and less than 0.95 under abnormal conditions with soluble boron.

No new technology or unproven technology is utilized in either the construction process or the analytical techniques necessary to justify the expansion.

~Res onse:

The rack designer, Holtec International, has licensed at least 10 other racks of the same design.

The construction processes and analytical techniques remain substantially the same as these other 10 rack installations.

Thus, no new or unproven technology is utilized in the construction or analysis of the high density Cook Nuclear Plant spent fuel racks.

Thus, it is concluded that the example cited is relevant and that the proposed amendment does not involve significant hazards considerations.

6.0 Pe d n S

o osals Im acti This Submitta The changes proposed in this letter will supersede those proposed in our letter AEP:NRC:1071N, dated February 15, 1991.

ATTACHMENT 2 to AEP:NRC:

1146 EXISTING TECHNICAL SPECIFICATIONS PAGES MARKED TO REFLECT PROPOSED CHANGES

Docket No.

315 page 4 af 6 Amendmenc No.

31 2.C(4)

Licensee may proceed Mich and is required to complete the madificacians identified in TabLe 1 of the Fire Protection Safety evaluation Rcpor-for the Donald C.

Cook Nuclear Pl.anc dated June 4,

1979

~

These modifications shalL be compl.eccd in accordance vith the dates contained 'in TabLe 1 of that SER or Supplements thereto.

Administrative controls for fire protection as described in the l.icensee's submittals dated January 31, 1977 and October 27, I,977 shall be implemented and maintained.

Amendmenc No.

118,136 (5)

Spent Pucl'ool. Stora e

34 t'X The Licensee is autho

@ed co store D. C. Cook, Unit 1 and Unit 2 fuel assembL s,

nev or ir adiaced up to a total of "

fuel assemblies in the shared spenc fuel. pool at the Donald C.

Cook Nuclear Plant sub]ect to the follo~ing conditions:

a. nominal

.<<L savored in the spent fuel pool shall noc have cnrc."=cnt greater than 4.95X Uranium-,235

~

(6)

Deleted by Amendment 80.

D Phys'ca'rotection Amerd=ent Na.

122

he 1'censee shaLL fuLly implement and maintain in effect all provisions af the Commission-approved physical security, guard train'ng and qualification, and safcguards concingency p'ans including amendments maCe pursuant to provisions of thc

.". sccll.aneous Amend ents and, Searcn Rcquircmencs revisions to 1.0 CiR.73.55 (51 cR 278l.7 and 27822) and to the authority of 10 CcR 50.90 and 10 CrR 50.54(p).

The, plans, Mhich contain Safcguards Tnformation protected under 10 CFR 73.2l.,

are cnc'cled:

"Donald C.

Cook Nuclear Plant Security Plan," '<<f.th revisions submictcd through JuLy 21, 1988; "Donald C.

Cook Nuclear Plant Training and Qualification Plan," arith revisions submictcd through December 18, l.986; and "Donald C.

Cook Nuclear Plane Safeguards Contingency Pl.an," erich revisions submitted through June 10, 1988.

Changes made in accordance arith 10 CcR 73.55 shall be implemented in accordance Mich thc schedule sct forth therein.

8

REFUELING OPERATIONS OECAY TIi4IE LIHITING CONG ITION FOR OPERATION u8 3.9.3 The reactor shall be subcritica1 for at 1east &hours APPLICABILITY: Ouring movement of irradiated fuel in the reactor pressure vessel.

ACTION:

tGS Mith the reactor subscriticaI for less than Ahours, suspend all operations involving movement, of irradiated fuel in the reactor pressure vessel.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREHENTS 4.9.3 reactor shall be determined to have been subcritical for at least hours by ver ification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.

0.

C.

COOK - UNIT I 3/4 9-3

0

REFUE~lO OPERATZOHg gTORACE POOL SOROH COHCEFI'RATXON+

~ZHC CoanXTXOH ZOR OPmaTXON 3 9,].5 A boron concentration of greater than or equal to '2 ~ 4dd Ppm shall be maintained in the fuel storage pool.

APPLZCAB ZLZZ:

ACTZOH:

~ kt n.l l +i~

lith the requirements of the specification not satisfied.

suspend all movement of fuel assemblies in the fuel storage pool and restore the boron concentration to vithin its limit prior to resuming fuel movement.

The provisions of Specification 3.0.3 are not applicable.

SURVEXLLANCE RE UIREKNTS 4.9.15 The boron concentration in the fuel storage pool shall be determined to be at least at its minimum required at least once per 7 days.whoa-&ask

• Shared system vt.th Cook Nuclear Plant

- Unit, 2 COOK NUC~ PLANT - UNIT l-3/4 9-1,9 ANENMENT NO. 136

DES1GVi ES AND TEHPERATURE 5.2.2 The reactor containment building is desi.gned and shall be maintained in accordance with the original design provisi.ons contained in Section 5.2 '

of the FSAR.

NS 5.2.3 penetzations through the reactor containment building are designed and shall be maintained in accordance with the ori.ginal design provisions contained in Section 5.4 of the FSAR with allowance for normal degradati.on pursuant to the applicable Surveillance Requirements.

3 REACTOR CORE ASSEHBL S

5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 204 fuel rods clad with Zircaloy -4.

Each fuel rod shall have a nominal active fuel length of 144 inches.

The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235.

Reload fuel shall be similar in physical design to the initi.al core loading and shall have a maximum enrichment of weight percent U-235.

nocn<~I H.9'5 CO 0

OD ASS B

ES 5.3.2 The reactor core shall contain 53 full length and no. part length control rod assemblies.

The full 1ength control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5

percent cadmium.

All controL rods shall be clad with stainless steel tubing.

COO SYS GV ESS E

5.4'.1 The reactor coolant system i.s designed and shall be maintained:

D.

C.

COOK -

UNZT 1 5-4 Amendment No.

102

wl gESlgg FKLTVRES ao accordance vith the code requirements specif ied in Section

4. 1. 6 of the CESAR vith allovance for normal degradation pursuant to the any].italy] e Surveillance Requirements f

b.

for a pressure of 2445 Paig, and

'For a temperature of 650 7 ~ except for the pressuriser vhich is 680 F.

0 o

S. 4.2 5.5 The total contained volume of the reactor coolant system is 12,612

+ 100 cubic feet at a nominal.T of 70 F.

0 avg

~CEHCY CORE COOLINC SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance vith the otiginal design provisions contained in Section 6.2 of the FSAR vith allovance for normal.

degradation pursuant to the applicable 'Surveillance Requirements.

5.6 FUEL STORACZ CRETTCALZTY -

SPEHT FUEL 5.6.1.1:

The spent fuel storage racks are designed and shall be maintained vith:

b.

7 h k <<equivalent to less than 0. =.5 vhen flooded vith unborated vater",

88 I

h nominal inch center-to-center distance betveen fuel assemblies placed fn the storage racks.

~44

~ 4 as Regio

1) shall be established or storage o

$4stinghouse fuel v h nominal e

ich=ent abo e 3.95 veigh percent U-23 and th bunup 1

s than 5,55 HVQ/NTU. 'I Region 1, fu sh 3.'e stored n a three-o

-of-four ce configurati vith o

e symmetric ell locatio of each 2 x cell ar ay v cant.

The bound betveen t Region 1 =e ioned above nd the resc of e 'spenc Eu storage rac (defined as egion 2) shall e such that e three-out f-four stor e requireme shal be carried to Region 2

y, ac least one rov as COOK NUC~ PLABT -

UNZT 1 5-5 amanmwt HO

z~i Z.

gs~

P l.

)

0

)

~

A<<tea

'e k~l lng eppI

'I Region g is designed to accommodate new fuel with a maximum )enrichment of 4.95 wt% U-235, or spent fuel regardless of the discharge fuel burnup.

Region I2 is designed to accommodate fuel of 4.954 initialI,enrichment burned to at least 50,000 MWD/MtU, or fuel of other'enrichments with equivalent reacti-n

~Wa4 Region, 3 is designed to accommodate fuel of 4.954 initial enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with equivalent reacti ity.

mo ~ "~

~4$ gage or Re ion 2

Stora e

td.nimumgmurn pPP tag)/SBJ 22,670

+ 22,220 E - 2,260 E

+ 149 E

For Re ion 3 Stora e

Rs Mg Minimum~murnup in MWn~

26,745

+ 18,746 E

E

+ 98 '

7"iY

~hC"<4~

1631

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NORMAL STORAGE PATTERN (MIXED THREE ZONE ~

g 504 REGION I CELLS P 1415 REGION 2 CELLS gg 1694 REGION 3 CELLS

l I

'L V Ai r

~

J r

) 'i r V '

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'p r r

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&I~M INTERIM STORAGE PATTERN {CHECKERBOARD)

H 15b EllPD LOCATIOHS g 6&1 REGIOH 1 CELLS Q

1415 REGIOH 2 CELLS g

1379 REGIOH 5 CELLS

maaa 45000

~ amaa a

> 30000 Q

g z~aaa AC BUR EPTA UP 0 MAIN

~~ zaaaa 1 000 (Requ NACC PTABL RNUP OOMAI t'cs Stol' th 1dn 1) 0 1.5 Z.a M

3.0 3D 4.0 t4 5.0 INITIAL ENRICHMENT, sU-235 1g.

3 ACCEPTABLE BURNUP DOMAIN IN REGIONS 2 8c 3 4-30

DESXCÃ FEATURES

~l stozed in the spent fuel storage zacks.shall have a aaximum

~~1 fuel assembly enrichment as follovs:

Descziotion

1) Vestinghouse 15 x 15 STD 15 x 15 OFh

2) Exxon/hNY 15 x 15 Kaximum Nominal Fuel Assembly Enrichment Vt. '0 235 4.95 WAS

3) Vestinghouse 17 x 17 STD 17 x 17 OFh 17 x 1,7 V5 4.95

4) Exxon/hNY CRZTZChLITY-HEV FUEL 17 x 17

~m MRS 5.6,2.1 The nev fuel pit stozage racks are designed and shall be maintained vith a nominal 21 inch center-co-center distance betveen nev fuel assemblies such that k <<viLL not exceed 0.98 vhen fuel assemblies aze placed in the pit and aqueous Yoam moderat'on is assumed.

5.6.2.2 Fuel stored 'n -he nev fueL sto age ra-'::s shall have a maximum nominal uel assembly enrich=cnt as follovs; Description Maximum Nominal Fuel hssembly Enr'ch ent 235.

L) Vestinghouse 15 x L5 STD 15 x 15 OFh

4. 55

2) Exxon/hNY L5 x 15 3.50

3) Vestinghouse 17 x 17 STD 17 x 17 OFh L7 x L7 V5 4.55

4) Exxon/hNF 17 x 17 4.23 ORAZNhGE The spent fuel storage peal.

Ls designed and shall be maintained to prevent inadvertent draining of the pool belov elevation 629'4".

COOK PIC~~

PLhBT -

UNL'T 1 5-6 hNENDMEÃT NO. 57,136

gESZCg TKATURES 5,6.4 Th+ fuel storage pool is designed and shall be maintained vith a storage capacity United to no more than fuel assembliea.

5.1 SEZSXZC CLASSZPZCATZON Thoae structures, systems and components identified aa Category Z Ztems the tSAR shall be designed and maintained to the original design provisions contained in the TSAR vith allovance for normal de8radation pursuant to the applicant Surreillance Requirements.

5. 8 METZOROLOCZCAL TOVER LOCATZON 5.8.1 The meteorological tover shall be located as shovn in Pigure 5.1 1.

5.9 COMPONENT CTCLZC OR TRhNSZENT LZMZT 5.9.1 The components identified in Table 5.9-1 are designed and shall be maintained vithin. the cyclic or transient limits of Table 5.9-1.

COOK RJC~~

PLANT - PiiZT L

5-Sa A~'HDMBlT NO. 136 f

Docket No.

316

~

Pag>>

6 of Ll (q)

Del.aced by Amendment 2.

(-)

Deleced by Amendmenc 68.

(s)

Spent Fuei.oaL Scara e

Z4 l3 Amendment No.

104>tZL

o. no~i~

ihe licensee is authorised co sco e

D.

C.

Cook, Unit L

and Uni" 2 fuel assemblies, new r ir adi.aced ~y fuel assemblies in che shared spent fuel pool ac th>> Donald C.

Cook Nuclear Plant subject co che follaving conditions:

Fuel scored in che spent fuel pool shall not hav>> ~

enr'chmenc greater chan 4.95X Uranium-235.

+Amendmen 3 deleted Paragraph (s).

Amendment l,3 added a

new Pa agraph (s).

2 C.(:)

Geieced by Amendmenc 63.

i.i Secandarv "acct "he. 'strv.".onitorin Pro ram he L'censee shaiL

'mplemenc a secondary vacer chemistry onicoring program ca i."'".'bic steam generator cube deg adac'on.

This progra= shall be described 'n che

=a= on cher'c g manual and shall include:

I

'dent'= cac'on of a -ampL'ng schedule for che cr

= cai parar<<ecers and cont oL points for c..ese paramece s:

2.

identification of che procedures used co measure che vai es of che cr" cal paramecers; Amendmenr No.

LS 3.

ldencificacion of process sampling points:

Procedure, for che record'ng and management of daca; Procedures def'ning car"eccve ac 'ons for off concrol point chemistry conditions; and A procedu e

'denci "ying (a) che auchar:

responsibie

=or che.ncerprecacion of =he data.

(b) che sequence and timing of admin'serac"e events required co !nace correc=i;e actions.

and

s REELING OPERATIONS OECAY TIME LIMITING.CQNOITION FOR OPERATION 148 3.9.3 The reactar shall be subcriticaI Scr atleast Whaurs.

APPLICABILITY:

Our fng mavenent of frradfated fuel in the reactor pressure vessel.

ACTION:

168 Nth the reactor subcrftfcal for less than

hours, suspend all oqora-tfans fnvalvfng movement of irradiated fue1 in the reactor pressure vessel.

The provisions of Specfffcatfon 3.0e3 are nat applicable.

SURVEILLANCE REGUIREMEHTS lC,Q I

4.9.3 e reactor'ha11 be determined ta have been subcrftical for at least.

hours by verfffcatfon of the date and tfae of subcrftfcality prfar ta movement of irradiated fuel in the reactar pressure vessel.

O.

C.

COOK - UNIT 2 3/4 g~ 3

Ib

0 anrUZLI84 OPXRATZOSS SToaaaZ ~ maes COSCZ~TZOS

~TX50 CMDZTZQI yap ap~TXON 3, j,D l Mroa conc<<tration of greater than or equal to to 2 o <t30 gpss

shaU, be aaintaMd Q the fuel storaSe pool.

~~~ZLZTT:

kozznn:

Vith the requirements of the specification not satisfied.

suspend all aoraoanr of frai assaoniias in ma irai srozaga pool. snf za@za ma boron concentration to ~ithin its Limit prior to resuming fuel ~ement.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RL UIRBKHTS 4.9. 15 The boron concentration in the fuel storage pool shall be determined to be at least at its minimum required at least once'per T da7s

~vh4tW~

assemblies

~Shared svstcn vi=h Cook Nuclear Plant

- t:nic 3/4 9-18

E I

5. 3 RXkC&k CORD

~ iSS~IMS

@OWING&

h p 5.3.1 The reactor coze shall contain 193 fuel assemblies vith each fuel assembly containing 264 fuel rods clad vith Xircaloy-4.

Each fuel rod shall, have a nominal active fueL lengch of 144 inches.

The initial core Loading shaLL have a maximum enrichment of 3.3 veight percent U-235.

Reload fuel'hall be similar in physical design co the initiaL core loading and nay be

~nriched up to 4.95 veight percenc U-235.

CONTROL ROD ASSEMBLIES 5, 3.2 The reactor core shall contain 53 full length and no part length control rod assemblies.

The full length control rod assemblies shall.

contain a nominaL 142 inches of absozbez matezial.

The nominaL values of absorber materiaL shall be 80 percent silver, 15 percent indium and 5 percent cadmium.

All control rods shall be cl.ad vith stainless steel cubing.

5.4

~~

CTOR COOLANT SYSTE.f DESICN PRESSURE AND T NPERATURZ 5.4.1 The reactor coolanc system is designed and shall be maintained:

a.

Zn accordance vich che code requireme"..cs specified in Sect'on 4.1.6 oi che FSAR, vich allova.".ce for normal degradation pursuant co che applicable Surveillanc~

Requirements.

b.

Por a pressure oi 2485 psig, and c.."-or a ce=perat rc oi 650

":; except ior che prassuriser vhich is 6aO'P.'OOK NUC~+

PLANT. g~gT,Z 5-4

VOLUME

~

~

5.5 5.4.2 Th total vater and steam volume of the reactor coolant syat4a ia L2o<L2 + 100 cubic feec a] a nominal T

of 70 7.

aTg ROCTOh7. TOVZX mmTXON 5.5.1 Tha $4taorologicaL cover shall be located as shovn on Figure 5.L-L.

5, 6 FUEL STORACE CarrZC~TT -

SPENT FUZED 5.6.1.1 The spent fuel storage racW are designed and shall be maintained vith:

b.

h X ff equivalent to less than 0.95 vhen flooded vith off unboraced vacer,e.'t'I h naminal

%04k-fach censer eo -can-car distance baaresn hei assemblies, placed in the storage racks'R p~dA" c ~

as Region L

shall be e

ablished r scorag of Western ouse fuel vith ominal <<nr hment abov 3,95 ve hc percen 1-235 and vit. burnup Les than 5,550

/8TU.

Xn Region, fuel shall e stored a three-ou -of-four ell confi ation vit one etr'c ce Locac'on f each.

2 2 cell a ay vacant.

e boundary ecveen the egion 'ntioned ove and th rest of th spent f el storage

.".ks (defin d as Region 2) shall be uch that t three-o.-:=-four rage requ ament shall b

carr'ed

'.." o,Reg'on by at L

st, one ro as shovn 5.5.L.2

.=uel stored in the spent : e'torage racks shall have a maxim nominaL =uel assemb'y enr'chment as foL'avs:

Descriotion

!faxi um Nominal ":ueL hsse bly Enrichment

't.

0 235.

L) Vestinghouse L5 x L5 STD L5 x 15 OFh 2)- Exxon/ANF L5 x L5

3) Vestinghouse L7 x L7 STD L7 x L7 OFh L7 x L7 VS mm 4.9S 4.95

4) Exxon/hN7 L7 x L7 9.'tS OOOO NUCLEI@ Pm~T

- tVZT 2 5-5

~~ZNmZNT NO. 55,>04.>21

E

P t.

Region is designed to accommodate new fuel with a maximum enrichment of 4.95 wt4 U-235, or spent fuel regardless of the discharge fuel burnup.

Region 2 is designed to accommodate fuel of 4.954'nitial enrichment burned to at least 50,000 MWD/MtU, or fuel of other enrichments with ecpxivalent reacti-ity.

n

~lgg gS.

Region 3 is designed to accommodate fuel of 4.954 initial enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with ecpxivalent reacti ity.

~ A CACL UL

~ ~

g

~

o e ion 2

Sto a e 4v~

minimum]mum p ih mmD/KzU 22,670

+ 22,220 E 2~260 E

+ 149 E

For Re ion 3 Stora e

Minimum~Burnup in MWD/MTU 26 I745 + 18 i746 E 3,268 E

+ 98.4 E

Q - z< fig)Cnri4ny~

~ ~

V P

3

~ C

~ ~

M ~

s +QV't'0

~ 110 e

3ec sac>>Q't'5 Ritcks

0

ffji',')

NORMA PATTE REE ZONE

. M 504 REGION I CE~

Q 1415 REGIDN 2 CELLS Im 169i REGION 3 CELLS

I I

V

'r

t A, 'f 4tA Vr

~

~

V r

V A

~

V 4

V 1,

'r,

~ r

/

4 C'

~'

F,

/ 7, V.

r.

'1 V

~

~

A r r.'r v r t

t X 4 r4/ r4 V

X rr

~

-FI~I-4 INTERIM STORAGE PATTERN {CHECKERBOARD}

g 156 ELII'Tf lOCATIONS g 661 REGION 1 CELLS Q

l415 REGION 2 CELLS Q

1379 REGION 3 CELLS

\\

55000 5aaaa 45000 Iz 25000 Cl

> waaa Cl 0

25aaa G2

~ 20000 4

15000 10QQO AC BUR HEPTA)LE UP 0 MAIN (Requ NACCE RNUP PTABL OOMAI res S(os o tn R

lan 1) 0 1.5 2.0 LS 5.0 0.5 k.a tS 5,0 INITIAL ENRICHMENT, sV-235 Fig. +r5-ACCEPTABLE BURNUP DOMAIN IN REGIONS 2 8c 3

I

g.g,g.l ~ ne< fuel pic scorage rac~ are deaigned and shell be incai ed Wch a n ml 21 i dL cancer-to-cencat diacmce bec een ner f l aaj~bliaa Ndl th c K rtll noc exceed 0.94 men f l aaaeibliaa ate placed in the yit Nd aqua~ f~ Ndatacim ia <<~d.

off 5.6,2.2 fuel scored in che neo fuel scotage racks shall hem a SaxM noainal fuel aaaeably enrichaenc aa follcwa; Descri cion

Naxilud, Mcnainal fuel Aaaeahly Enx ichlaenc Ve,. \\ 235

1) Westinghouse "l

2) Exxon/Amp

3) Vescinghouse 4)

Exxon/ANF LS x LS STD L5 x 15 OFA L5 x 15 L7 x 17 STD 17 x 1,7 OFA 17 x L7 V5 17 x L7

4. 55 3.50 4.55 4.23 DRAiHACE I

5.6.3 The spenc uel storage pooL is designed a.".d shall be aaincained co p evenc inadver"enc draininr of

=he pooL be'ov e'eva='on 629'4".

Ch?AC TY 5 6.4 The spent.'L scorage pool Ls designed and shaLL be aincained vtch a scorage capac'"y 1'-ed co no -ore chan fuel assemblies.

5. 7 COMPO.tEST C'fCLZC OR TMST,-JT K~X

%613 5

~ 7

~ 1 The conponencs Ldencified in TabLe 5.7-1 are designed and shall be

"-aincained vichin ch>> cyclic or -ransienc Logics of TabLe 5.7-1.

COOK tUC~ PLiQiT. 4NIT 2 1I 5-6

<KHDMEHT NO. 41, 321

IP I

ATTACHMENT 3 TO AEP:NRC:1146 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES

Docket No.

315 Page 4 of 6 Amendment 2.C (4)

The licensee may proceed with and is required to complete the No.

31 modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for the Donald C.

Cook Nuclear Plant dated June 4, 1979.

These modifications shall be completed in accordance with the dates contained Table 1 of that SER or Supplements thereto.

Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.

(5)

S ent Fuel PooL Stora e

Amendment No. 118, 136 The licensee is authorized to store D.

C.

Cook, Unit 1 and Unit fuel assemblies, new or irradiated up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C.

Cook Nuclear Plant subject to the following conditions:

Fuel stored in the spent fuel pool shall not have a

nominal enrichment greater than 4.958 Uranium-235.

(6)

Deleted by Amendment 80.

• 2.D Ph sical Protection Amendment No.

122 The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical

security, guard 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 plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

"Donald C.

Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988; "Donald C.

Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 18, 1986; and "Donald C.

Cook Nuclear Plant Safeguards Contingency Plant," with revisions submitted through June 10, 1988.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subcritical for at least 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.

APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.

ACTION:

With the reactor subcritical for less than 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, suspend all

'perations involving movement of irradiated fuel in the reactor pressure vessel.

The provisions of Specification 3.0.3 are"not applicable.

SURVEILLANCE RE UIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.

COOK NUCLEAR PIANT - UNIT 1 3/4 9-3 AMENDMENT NO..

REFUELING OPERATIONS STORAGE POOL BORON CONCENTRATION*

LIMITING CONDITION FOR OPERATION 3.9.15 A boron concentration of greater than or equal to 2,400 ppm shall be maintained in the fuel storage pool.

APPLICABILITY: At all times.

ACTION:

Pith the requirements of the specification not satisfied, suspend all movement of fuel assemblies in the fuel storage pool and restore the boron concentration to within its limit prior to resuming fuel movement.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9.15 The boron concentration in the fuel storage pool shall be determined to be at least at its minimum required at least once per 7 days.

• Shared system with Cook Nuclear Plant

- Unit 2 COOK NUCLEAR PLANT - UNIT 1 3/4 9-19 AMENDMENT'O.

DESIGiV FEATURES DESIGiV PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained in accordance with the original design provisions contained in Section 5.2.2 of the FSAR.

PENETRATIONS, 5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions contained in Section 5.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 204 fuel rods clad with Zircaloy-4.

Each fuel rod shall have a nominal active fuel length of 144 inches.

The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum nominal enrichmenc of d,95 weight percent U-235.

I CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies.

The full length control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5

percent cadmium.

All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4sl The reactor coolant system is designed and shall be maintained:

COOK NUCLEAR PLANT - UNIT 1 5-4 AMENDMENT NO.

DESIGN FEATURES a.

In accordance with the code requirements specified in Section 4.1.6 of the FSAR, with allowance fox'ormal degradation pursuant to the applicable Surveillance Requirements, b.

For a pressure of 2485 psig, and c.

For a temperature of 650 F, except for the pressurizer which is 0

680 F.

VOLUME 5.4.2 5.5 The total contained volume of the reactor coolant system is 12,612 + 100 cubic feet at a nominal T of 70 F.

avg EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section 6.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requixements.

5. 6 FUEL STORAGE CRITICALITY -

SPENT FUEL 5.6.1.1 The spent fuel storage racks axe designed and shall be maintained with:

a ~

A k ff equivalent to less than 0.95 when flooded with eff unborated water, b.

A nominal 8.97 inch center-to-center distance between fuel assemblies placed in the storage racks.

C.

The fuel assemblies will be classified as acceptable for Region 1, Region 2, ox Region 3 storage based upon their assembly average burnup versus initial nominal enrichment.

Cells acceptable for Region 1, Region 2, and Region 3 assembly storage are indicated in Figures 5.6-1 and 5.6-2.

Assemblies that are acceptable for storage in Region 1, Region 2, and Region 3 must meet the design criteria that define the regions as follows:

COOK NUCLEAR PLANT - UNIT 1 5-5 AMENDMENT NO.

l l

[V l

1.

Region 1 is designed to accommodate new fuel with a maximum nominal enrichment of 4.95 wt% U-235, or spent fuel regardless of the discharge fuel burnup.

2.

Region 2 is designed to accommodate fuel of 4.95%

initial nominal enrichment burned to at least 50,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.

3.

Region 3 is designed to accommodate fuel of 4.95%

initial nominal enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.

The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations and graphically depicted in Figure 5.6-3.

For Re ion '2 Stora e

Minimum Assembly Average Burnup in MWD/MTU 22,670

+

22,220 E

2,260 E

+

149 E

For Re ion 3 Stora e

Minimum Assembly Average Burnup in MWD/MTU 26,745

+

18,746 E

1,631 E

+

98.4 E

Where E

Initial Peak Enrichment COOK NUCLEAR PLANT - UNIT 1 5-5a AMENDMENT NO.

PIGURE 5 6-l: Normal Srorage Pa@tern (M'xed Three Zone)

~

~

V

)

~ I

~

~

~

\\

g 504 REOOH 1

CEUFS Q 'l415 11EGNN 2 CQLS Q 169'KG1ON 3 CQLS COOK NUCLBR PLANT - UNIT l 5-5b

~MENT NO.

Figure 5.6-$ : Interim Scorage Pat"em (Chectcerboard)

~

~

~

~

~p l

~

I l

~

I

~

~

I h

I

~

~

I

'V

~ I g

1$$ tWTf tDCAllOHS g 441 4ECOH 1 CGLS Q

1415 4EQOH 2 CGLS g

IS7'0 SECS S COLS COOK AC~~ PLANT - UNIT L 5-Sc AMENDMENT NO,

Figure 5.6-3: Acceptable Burnup Domain in Re'lions 2 6 3

~4 I

440GQ P

I Q JZCCO C

> mea C

t n

2 CCC m

~

CCCOO r u

r I

ISOCO

!OOOO I

AC"EPTAIIL~

BUR/UP 00hlAIN I

NACC<~A8 RNUP I OOMAI I

I

~s Sterna b P.O

~.O INITIAL ENRICHMENT, sU-235 COOK NUCLEAR PLANT, - UNIT L 5-56 aK2n)MENT NO.

I

DESIGN FEATURES 5.6.1.2:

Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:

Descri tion Maximum Nominal Fuel Assembly Enrichment Wt.

a 235 1)

Westinghouse 15 x 15 STD 15 x 15 OFA 4.95 2)

Exxon/ANF 15 x 15 4.95 3)

Westinghouse 17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.95 4)

Exxon/ANF 17 x 17 4.95 CRITICALITY -

NEW FUEL 5.6.2.1 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that k ff will not exceed 0.98 when fuel assemblies eff are placed in the pit and aqueous foam moderation is assumed.

5.6.2.2 Fuel stored in the new fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:

Descri tion Maximum Nominal Fuel Assembly Enrichment Wt.

0 235 1)

Westinghouse 15 x 15 STD 15 x 15 OFA 4.55 2)

Exxon/ANF 15 x 15 3.50 3)

Westinghouse 17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.55 4)

Exxon/ANF 17 x 17 4.23 DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 629'4".

COOK NUCLEAR PLANT - UNIT 1 5-6 AMENDMENT NO.

d

DESIGN FEATURES CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies.

l 5.7 SEISMIC CLASSIFICATION 5.7.1 Those structures, systems and components identified as Category I Items in the FSAR shall be designed and maintained to the original design provisions contained in the FSAR with allowance for normal degradation pursuant to the applicant Surveillance Requirements.

5.8 METEOROLOGICAL TOWER LOCATION 5.8.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.9 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.9.1 The components identified in Table 5.9-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.9-1.

COOK NUCLEAR PLANT - UNIT 1 5-6a AMENDMENT NO.

1I

Docket No.

316 Page 6 of 11 (q)

Deleted by Amendment 2.

(r)

Deleted by Amendment 68.

(s)

S ent Fuel Pool Stora e

Amendment No. 104, 121 The licensee is authorized to store D.

C. Cook, Unit 1 and Unit 2 fuel assemblies, new or irradiated up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C.

Cook Nuclear Plant subject to the following conditions:

Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95%

Uranium-235.

1

+Amendment 3 deleted Paragraph (s),

Amendment 13 added a new Paragraph (s).

(t)

Seconda Water Chemist Monitorin Pro ram The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.

This program shall be described in the station chemistry manual and shall include:

1'.

Identification of a sampling schedule for the critical parameters and control points for these parameters; 2.

Identification of the'rocedures used to measure the values of the critical parameters; 3.

Identification of process sampling points; Amendment No.

18 Procedure for the recording and management of data; 5.

Procedures defining corrective actions for off control point chemistry conditions; and 6.

A procedure identifying (a) the authority responsible for the interpretation of the

data, and (b) the sequence and timing of administrative events required to initiate corrective actions.

REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subcritical for at least 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.

APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.

ACTION:

With the reactor subcritical for less than 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />, suspend all I

operations involving movement of irradiated fuel in the reactor pressure vessel.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessels COOK NUCLEAR PLANT - UNIT 2 3/4 9-3 AMENDMENT NO.

t

REFUELING OPERATIONS STORAGE POOL BORON CONCENTRATION*

LIMITING CONDITION FOR OPERATION 3.9.15 A boron concentration of greater than or equal to 2,400 ppm shall be maintained in the fuel storage pool.

APPLICABILITY: At all times.

ACTION:

With the requirements of the specification not satisfied, suspend all movement of fuel assemblies in the fuel storage pool and restore the boron concentration to within its limit prior to resuming fuel movement.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9.15 The boron concentration in the fuel storage pool shall be determined to be at least at its minimum required at least once per 7 days.

• Shared system with Cook Nuclear Plant

- Unit 1 COOK NUCLEAR PLANT - UNIT 2 3/4 9-18 AMENDMENT NO.

DESIGN FEATURES 5.3 REACTOR CORE

'UEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4.

Each fuel rod shall have a nominal active fuel length of 144 inches.

The initial core loading shall have a maximum enrichment of 3.3 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and may be nominally enriched up to 4.95 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies.

The full length control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.

All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is. designed and shall be maintained:

a.

In accordance with the code requirements specified in Section 4.1.6 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

b.

For a pressure of 2485 psig, and 0

c.

For a temperature of 650 F, except for the pressurizer which is 680 F.

COOK NUCLEAR PLANT - UNIT 2 5-4 AMENDMENT NO.

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,612 plus or minus 100 cubic feet at a nominal Tavg of 70 F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY -

SPENT FUEL 5.6.1.1 with:

The spent fuel storage racks are designed and shall be maintained a.

A K f equivalent to less than 0.95 when flooded with eff unborated water, b.

A nominal 8.97-inch center-to-center distance between fuel assemblies, placed in the storage racks.

C.

The fuel assemblies will be classified as acceptable for Region 1, Region 2, or Region 3 storage based upon their assembly average burnup versus initial nominal enrichment.

Cells acceptable for Region 1, Region 2, and Region 3 assembly storage are indicated in Figures 5.6-1 and 5.6-2.

Assemblies that are acceptable for storage in Region 1, Region 2, and Region 3 must meet the design criteria that define the regions as follows:

Region 1 is designed to accommodate new fuel with a maximum nominal enrichment of 4.95 wtS U-235, or spent fuel regardless of the discharge fuel burnup.

2.

Region 2 is designed to accommodate fuel of 4.95%

initial nominal enrichment burned to at least 50,000 MWD/MTU, or fuel of other enrichments with equivalent reactivity.

3.

Region 3 is designed to accommodate fuel of 4.95%

initial nominal enrichment burned to at least 38,000 MWD/MTU, or fuel of other enrichments with equivalent reactivity.

COOK NUCLEAR PLANT - UNIT 2 5-5 AMENDMENT NO.

The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations and graphically depicted in Figure 5.6-3.

For Re ion 2 Store e

Minimum Assembly Average Burnup in MWD/MTU 22,670

+

22,220 E

2,260 E

+

149 E

For Re ion 3 Stora e

Minimum Assembly Average Burnup in MWD/MTU 26,745

+

"18,746 E

1,631 E

+

98.4 E

Where E

Initial Peak Enrichment 5.6.1.2 Fuel stored in the spent fuel storage racks shall have a

nominal fuel assembly enrichment as follows:

Maximum Nominal Fuel Assembly Enrichment Wt.

0 235U 1)

Westinghouse 15 x 15 STD 15 x 15 OFA 4.95 2)

Exxon/ANF 15 x 15 3)

Westinghouse 17 x,17 STD 17 x 17 OFA 17 x 17 V5 4.95 4.95 4)

Exxon/ANF 17 x 17 4.95 COOK NUCLEAR PLANT - UNIT 2 5-5a AMENDMENT NO.

1

FIGURE 5.6-1:

Norma1 Storage Pattern (Mixed Three Zone)

C g 504 REGlON 1 CQJS Q 1415 REGlON 2 CGlS Q 1694 REGiON 3 COLS COOK NUCLEAR PLANT - UNIT 2 5-5b AMENDMENT NO.

4

Figure 5.6-2: Interim Storage Pattern (Checkerboard) g IS4 ENPlY IOCAIIONS g 441 RECION I CELS Q

IRIS REQOH 9 CGES g

IS79 RECON S CELS COOK NUCLEAR PLANT - UNIT 2 5-5c AMENDMENT NO.

Figure 5.6-3: Acceptable Burnup Domain in Regions 2 & 3 I~ sscca

> Sacca C.

g 1 caa G1

~ ZCCCO AC aUR LEPTA)

UP 00 Lc MAIN ISOCO lacoo NACC TAB RNUP OOMAI s

res Sbsrss1a In Ion 1) 0 l.

1.0 LS 1.0

+.0 4.S

.0 INITIAL ENRICHMBIT, sU-235 COOK NUCLEAR PL'ANT, - UNIT 2 5-5(L AMENDMENT NO.

~

J'I

DESIGN FEATURES CRITICALITY'EWFUEL 5.6.2. 1 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that K ffwill not exceed 0.98 when fuel assemblies are placed'n tne pit and aqueous eff foam moderation is assumed.

5.6.2.2 Fuel stored in the new fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:

Descri tion Maximum Nominal Fuel Assembly Enrichment Wt.

a 235U 1)

Westinghouse 15 x 15 STD 15 x 15 OFA 4.55 2)

Exxon/ANF 15 x 15 3.50 3)

Westinghouse

. 17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.55 4)

Exxon/ANF 17 x 17 4.23 DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 629'4".

CAPACITY 5.6.4 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than t

3613 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7.1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

COOK NUCLEAR PLANT - UNIT 2 5-6 AMENDMENT NO.

ATTACHMENT 4 TO AEP:NRC: 1146 II LICENSING REPORT FOR STORAGE DENSIFICATION OF D.

C.

COOK SPENT FUEL POOL

0 g 'l I

I