HNP-05-143, Supplement to Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools

Supplement to Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools

ML060040348
Person / Time
Site:	Harris
Issue date:	12/22/2005
From:	Kamilaris C Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-05-143
Download: ML060040348 (20)

Text

Progress Energy Serial: HNP-05-143 DEC 2 2 2005 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT TO CREDIT SOLUBLE BORON FOR FUEL STORAGE POOLS Ladies and Gentlemen:

In a letter dated September 1, 2005 (i.e., Serial: HNP-05-103), Carolina Power and Light Company (CP&L) doing business as Progress Energy Carolinas, Inc., requested a license amendment to the Technical Specifications (TS) of the Harris Nuclear Plant (HNP). The proposed amendment would modify the TS requirements for Pressurized-Water Reactor (PWR) Boraflex fuel storage racks and add TS requirements for fuel storage pool boron concentration.

This letter provides revised Attachments 3 and 4 due to inadvertently omitting unchanged text that had rolled onto another page and associated changes to the index.

For clarity, these attachments replace Attachments 3 and 4 of the original letter in their entirety.

The administrative revision provided by this submittal does not change the intent or the justification for the requested amendment. HNP has determined that this supplement did not result in any change to the No Significant Hazards Consideration contained in the original letter. Therefore, the 10 CFR 50.92 Evaluation provided in the September 1, 2005 submittal and published inthe Federal Register (i.e., 70 FR 67746 dated November 8, 2005) remains valid.

HNP requests that the proposed amendment be issued prior to March 20, 2006 to support HNP Refueling Outage (RFO)-13, which is scheduled for April 8, 2006.

In addition, this document contains no new or revised Regulatory Commitments.

Please refer any question regarding this submittal to Mr. Dave Corlett at (919) 362-3137.

Progress Energy Carolinas, Inc.

Harris Nuclear Plant )

P.O. Box 165 New Hill, NC 27562

HNP-05-1 43 Page 2 I declare, under penalty of perjury, that the attached information is true and correct (Executed on )

DEC 2 2 2005 Sincerely, C.S. WA C. S. Kamilaris Manager, Support Services Harris Nuclear Plant CSK/jpy Attachments:

3. Proposed Technical Specifications (TS) Changes

4. Revised Technical Specifications (TS) Pages c:

Mr. R. A. Musser, NRC Senior Resident Inspector Ms. B. 0. Hall, N.C. DENR Section Chief Mr. C. P. Patel, NRC Project Manager Dr. W. D.Travers, NRC Regional Administrator

Attachment 3 to SERIAL: HNP-05-143 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT PROPOSED TECHNICAL SPECIFICATIONS (TS) CHANGES PROPOSED TECHNICAL SPECIFICATIONS (TS) CHANGES Page A3-1 of 9

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION ..... 3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM ...................... 3/4 7-11 3/4.7.4 EMERGENCY SERVICE WATER SYSTEM ...................... 3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK .................................. 3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM ............ 3/4 7-14 3/4.7.7 REACTOR AUXILIARY BUILDING (RAB) EMERGENCY EXHAUST SYSTEM.............................................. 3/4 7-17 3/4.7.8 SNUBBERS ......................................... 3/4 7-19 FIGURE 4.7-1 (DELETED) ...................... 3/4 7-24 3/4.7.9 SEALED SOURCE CONTAMINATION .3/4 7-25 3/4.7.10 (DELETED).3/4 7-27 TABLE 3.7-3 (DELETED).3/4 7-27 TABLE 3.7-4 (DELETED) ................ 3/4 7-27 TABLE 3.7-5 (DELETED) ................ 3/4 7-27 3/4.7.11 (DELETED).......................................... 3/4 7-27 Da 3/4.7.12 (DELETED)................ 3/4 7-28 (j' TABLE 3.7-6 (DELETED)................ 3/4 7-29 UJ 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating............................................... 3/4 8-1 TABLE 4.8-1 (DELETED) .3/4 8-10 Shutdown................................................ 3/4 8-11 3/4.8.2 D.C. SOURCES Operating............................................... 3/4 8-12 TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS . 3/4 8-14 Shutdown................................................ 3/4 8-15 3/4.8.3 ONSITE POWER DISTRIBUTION Operating............................................... 3/4 8-16 Shutdown................................................ 3/4 8-18 SHEARON HARRIS - UNIT 1

• I x Amendment No.ff xlf

INDEX 5.0 DESIGN FEATURES SECTION PAGE 5.1 SITE 5.1.1 EXCLUSION AREA . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1.2 LOW POPULATION ZONE . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1.3 MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS . . . . . . . . . . 5-1 FIGURE 5.1-1 EXCLUSION AREA . . . . . . . . . . . . . . . . . . . . 5-2 FIGURE 5.1-2 LOW POPULATION ZONE . . . . . . . . . . . . . . . . . . 5-3 FIGURE 5.1-3 SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . 5-4 FIGURE 5.1-4 ROUTINE GASEOUS RADIOACTIVE EFFLUENT RELEASE POINTS . . 5-5 5.2 CONTAINMENT 5.2.1 CONFIGURATION . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE . . . . . . . . . . . . . . . . . . 5-6 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES. . . ............ 5-6 5.3.2 CONTROL ROD ASSEMBLIES . . . . . . . . . . . . . . . . . . . . . . 5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE . . . . . . . . . . . . . . . . . . 5-6 5.4.2 VOLUME . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-6 5.5 METEOROLOGICAL TOWER LOCATION . . . . . . . . . . . . . . . . . . . 5-6a 5.6 FUEL STORAGE 5.6.1 CRITICALITY . . . . . . . ... . . . . . . . . . . . . . . . . . . . 5-7 5.6.2 DRAINAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-7A 5.6.3 CAPACITY . .5-7 FIGURE 5. -Z. BOOURA FRSU' FNRTCHMFNTM FORW FUlE1 ... . . . . ..IuL by 5.7--COmMPONET CMLlC OR TRANSTENT LIMIR~ ~ ~

TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS . . . . . . . . . . . . 5-8 iv, WM SHEARON HARRIS - UNIT 1 xvii Amendment No. +ie6Te

Proposed Text of NEW Technical Specification for spent fuel pool boron.

PLANT SYSTEMS 3/4.7.14 FUEL STORAGE POOL BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.7.14 The boron concentration of spent fuel pools shall be a 2000 ppm.

APPLICABILITY: At ALL TIMES for pools that contain nuclear fuel ACTION:

1. With the spent fuel pool boron concentration not within the limits, immediately suspend movement of fuel assemblies.

2. Immediately initiate action to restore pool boron concentration within the limit.

SURVEILLANCE REQUIRMENTS 4.7.14 At least once every 7 days verify spent fuel pool boron concentration is within the limit by:

1. Sampling the water volume connected to or in applicable pools.

2. In addition to 4.7.14.1, sampling an individual pool containing nuclear fuel if the pool is isolated from other pools.

SiGAP WhVVt1S- i4tr I 3/4 7-- 1 ieI1deAn+ 40.

DESIGN FEATURES 5.6 tUEL STORAGE - tW5 RTA CRITICALITY te eJ 5 6 1 The fuel storaae racks are desi ed and sll be inalpttldeowithI 6 n less an-or equal to .95 when floe with unborated water, marin gin is CAM s r 105 yHf noninalr I0nch crntcr- to 49nterP di-Sanse between fuc1

-as4blie plcod in thc flux trap stye 'WAstzragc rack3 r;'l-aff 6,25 inch center-to-center distance in the BWR storage V9 racks.

b.. .The-mae4 um core eometry- or PWFfucil asscmbllet lczz 4pa -o.. qual:to 1.170 at 68F The reactivity margin isassured for pools TC and "O^ by a nominal 9.017 inch center-to-center distance between fuel assemblies placed in the non-flux trap style PWR storage racks 6.25 Inch center to center distance inthe BWR storage racks he followtig restrictions are also inposed through ad niinstrative controls:

MPWRassemblies must be within the tacceptable rangef of the burnup restrictions shown in.Figure 5.6- prior to storage inPools 'C or 'T.

BWR assemblies are acceptable for storage inPool "C.

provided the maximum planar average enrichments are less than 4.6 wtX U235 and Kh, is less than or equal to 1.32 for nd dtcold core geometry l$CCG).

5.6.2 The pools WA.. RB". "C'and "0"are designed aond shall be maintained to prevent inadvertent draining of the pools below elevation 277.

CAPACITY 5.6.3.a Pool 'A' contains six (6 x 10 Cell) flux trap type PWR ratks and three (11 x 11 cell) BWR racks for a total storage capacity of 723 assemblies, Pool 'S' contains six (7 x 10 cell), five (6 x 10 cell). and one (6 xB cell) flux trap style PWR racks and seventeen (11 x 11 ceil).8WR racks and is licensed for one additional (11 x 11-cell) BWR rack that will be installed as needed. The combined pool "A' and, " litensed storage capacity is3669 assemblies. .

- SHEARON HARRIS UNIT 1 547 Amendment No

Technical Specification 5.6.1 INSERT A:

1 PWR storage racks in pools "A"and "B"

a. keff less than or equal to 0.95 if fully flooded with water borated to 2000 ppm.

b. keff less than 1.0 if flooded with unborated water.

c. A nominal 10.5 inch center-to-center distance between fuel assemblies.

d. Assemblies must be within the "acceptable range" of the burnup restrictions shown in Figure 5.6-2 prior to storage in unrestricted storage.

e. Assemblies that do not meet the requirements of 5.6.1.1 .d shall be stored in a 2-of-4 checkerboard within and across rack module boundaries. Less dense storage pattern (e.g. 1-of-4 or 1-of-5) are acceptable in place of 2-of-4.

f. The empty spaces (water holes) in the 5.6.1.1.e checkerboard may be occupied by non-fuel items (e.g., containment specimen and trash baskets, mock fuel assemblies etc.) up to a limit of one per every 6 storage spaces.

g. If fuel that meets the requirement of 5.6.1.1.d and fuel that does not meet 5.6.1.1.d are stored in the same rack module, an interface region must exist between the two regions. The interface region shall either be an empty row/column or a row

/column of fuel that meets the requirements of 5.6.1.1.d in a checkerboard pattern with the restricted 2-of-4 (5.6.1.1.e) region.

2. Dry New Fuel PWR Storage Racks

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent.

b. keff s 0.95 if fully flooded with unborated water without credit for Boraflex in the rack module.

c. keff : 0.98 in an optimum moderation event,

d. A nominal 10.5 inch center to center distance between storage cells with alternating rows and columns blocked such that fuel is stored in a 1-of-4 pattern.

3. BWR Storage Racks in Pools "A"and "B" Technical Specification Insert B:

4. PWR and BWR storage racks in Pools "C"and "D"

a. keffS 0.95 with unborated water.

Technical Specification Insert C:

5. Ineach case, keff includes allowances for uncertainties as described in Section 4.3.2.6 of the FSAR.

DESIGN FEATURES 6

0 x

z0.

E 0

2 2.5 3 3.5 4 4.5 5 Eurkic; ieut (w % 1 3W5)

FIGURE 5.6-1 AIBURNUP VERSUS ENRICHMENT FOR:WR FUEL SHEARON HARRIS - UNIT 1 5 3 i Amendment No."

New Technical Specification Figure DESIGN FEATURES 45,000 40,000 35,000 30,000 Z 25,000 a.

3, 20,000 15,000 10,000 5,000 0

1.5 2 2.5 3 3.5 4 4.5 5 Enrichment (wt% U-235)

Figure 5.6-2 Pools "A"and "B"BURNUP VERSUS ENRICHMENT FOR PWR FUEL SHEARON HARRIS - UNIT 1 5 -67 j kvleImeri* to.

Attachment 4 to SERIAL: HNP-05-143 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT REVISED TECHNICAL SPECIFICATIONS (TS) PAGES REVISED TECHNICAL SPECIFICATIONS (TS) PAGES Page A4-1 of 9

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION......... 3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM.......................... 3/4 7-11 3/4.7.4 EMERGENCY SERVICE WATER SYSTEM.......................... 3/47-12 3/4.7.5 ULTIMATE HEAT SINK...................................... 3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM................ 3/4 7-14 3/4.7.7 REACTOR AUXILIARY BUILDING (RAB) EMERGENCY EXHAUST SYSTEM 3/4 7-17 3/4.7.8 SNUBBERS................................................ 3/4 7-19 FIGURE 4.7-1 (DELETED).......................................... 3/4 7-24 3/4.7.9 SEALED SOURCE CONTAMINATION............................. 3/4 7-25 3/4.7.10 (DELETED)........................................... 3/4 7-27 TABLE 3.7 '-3 (DELETED)........................................... 3/4 7-27 TABLE 3.7 '-4 (DELETED)........................................... 3/4 7-27 TABLE 3.7 '-5 (DELETED)........................................... 3/4 7-27 3/4.7.11 (DELETED).......................................... 3/4 7-27 3/4.7.12 (DELETED)........................................... 3/4 7-28 TABLE 3.7-6 (DELETED)........................................... 3/4 7-29 3/4.7.13 ESSENTIAL SERVICES CHILLED WATER SYSTEM................. 3/4 7-30 3/4.7.14 FUEL STORAGE POOL BORON CONCENTRATION................... 3/4 7-31 I 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating...................................................... 3/4 8-1 TABLE 4.8-1 (DELETED)........................................... 3/4 8-10 Shutdown....................................................... 3/4 8-11 3/4.8.2 D.C. SOURCES Operating...................................................... 3/4 8-12 TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS................... 3/4 8-14 Shutdown ............................ 3/4 8-15 3/4.8.3 ONSITE POWER DISTRIBUTION Operating...................................................... 3/4 8-16 Shutdown....................................................... 3/4 8-18 SHEARON HARRIS - UNIT 1 x Amendment No.

INDEX 5.0 DESIGN FEATURES SECTIO\ PAGE 5.1 Si'TE 5.1.1 EXCLUSION AREA .................... 5-1 5.1.2 LOW POPULATION ZONE . . ... . . . . . . . . . . . . . . 5-1 5.1.3 MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS . . . . . . . 5-1 FIGURE 5.1-1 EXCLUSION AREA ................... 5-2 FIGURE 5.1-2 LOW POPULATION ZONE ................ 5-3 FIGURE 5.1-3 SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-4 FIGURE 5.1-4 ROUTINE GASEOUS RADIOACTIVE EFFLUENT RELEASE POINTS . . . . 5-5 5.2 CONTAINMENT 5.2.1 CONFIGURATION . . . . . . . . . . . . . . 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE . . . . . 5-6 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES . . . . . . . . . . . . . 5-6 5.3.2 CONTROL ROD ASSEMBLIES . ... . . . . . 5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE . . . . . . . . . . . . . . .. 5-6 5.4.2 VOLUME . . . . . . . . . . . . . . .. 5-6 5.5 METEOROLOGICAL TOWER LOCATION . . . . . . . . . . . . . . . . . . 5-6a 5.6 FUEL STORAGE 5.6.1 CRITICALITY . . . . . . . I . . . . . . . . . . . . 5-7 5.6.2 DRAINAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-7a 5.6.3 CAPACITY . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-7a 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT . . . . . . . . . . . . . . . . 5-7b FIGURE 5.6-1 POOLS "C"and "D"BURNUP VERS US ENRICHMENT FOR PWR FUEL . 5-7c FIGURE 5.6-2 POOLS "A"and "B"BURNUP VERS US ENRICHMENT FOR PWR FUEL . 5-7d TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS . . . . . . . . . . . . 5-8 SHEARON HARRIS - UNIT 1 xvi 1 Amendment No.

PLANT SYSTEMS 3/4.7.14 FUEL STORAGE POOL BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.7.14 The boron concentration of spent fuel pools shall be 2 2000 ppm.

APPLICABILITY: At ALL TIMES for pools that contain nuclear fuel.

ACTION:

a. With the spent fuel pool boron concentration not within the limits, immediatley suspend movement of fuel assemblies.

b. Immediately initiate action to restore pool boron concentration within the limit.

SURVEILLANCE REQUIREMENTS 4.7.14 At least once every 7 days verify spent fuel pool boron concentration is within the limit by:

a. Sampling the water volume connected to or in applicable pools.

b. In addition to 4.7.14.1, sampling an individual pool containing nuclear fuel if the pool is isolated from other pools.

SHEARON HARRIS - UNIT 1 3/4 7-31 Amendment No. I

DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1 The fuel storage racks are designed and shall be maintained with:

1. PWR storage racks in pools "A" and "B"

a. keff less than or equal to 0.95 if fully flooded with water borated to 2000ppm.

b. keff less than 1.0 if flooded with unborated water.

c. A nominal 10.5 inch center-to-center distance between fuel assemblies.

d. Assemblies must be within the "acceptable range" of the burnup restrictions shown in Figure 5.6-2 prior to storage in unrestricted storage.

e. Assemblies that do not meet the requirements of 5.6.1.1.d shall be stored in a 2-of-4 checkerboard within and across rack module boundaries. Less dense storage patterns (e.g. 1-of-4 or 1-of-5) are acceptable in place of 2-of-4.

f. The empty spaces (water holes) in the 5.6.1.1.e checkerboard may be occupied by non-fuel items (e.g.. containment specimen and trash baskets, mock fuel assemblies etc.) up to a imit of one per every 6 storage spaces.

g. If fuel that meets the requirement of 5.6.1.1.d and fuel that does not meet 5.6.1.1.d are stored in the same rack module.an interface region must exist between the two regions. The interface region shall either be an empty row/column or a row/column of fuel that meets the requirements of 5.6.1.1.d in a checkerboard pattern with the restricted (5.6.1.1.e) region.

2. Dry New Fuel PWR Storage Racks

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent.

b. keff "0.95 if fully flooded with unborated water without credit for Boraflex in the rack module.

c. keff < 0.98 in an optimum moderation event.

d. A nominal 10.5 inch center to center distance between storage cells with alternating rows and columns blocked such that fuel is stored in a 1-of-4 pattern.

SHEARON HARRIS - UNIT 1 5-7 Amendment No.

DESIGN FEATURES

3. BWR Storage Racks in Pools "A" and "B"

a. keff less than or equal to 0.95 when flooded with unborated water. I

b. The reactivity margin is assured for BWR racks in pools "A"and "B"by maintaining a nominal 6.25 inch center-to-center distance in the BWR storage racks.

4. PWR and BWR racks in pools "C"and "D"

a. keff less than or equal to 0.95 when flooded with unborated water.

b. The reactivity margin is assured for pools "C"and "D"by maintaining a nominal 9.017 inch center-to-center distance between fuel assemblies placed in the non-flux trap style PWR storage racks and 6.25 inch center-to-center distance in the BWR storage racks.

c. The following restrictions are also imposed through administrative controls:

1. PWR assemblies must be within the "acceptable range" of the burnup restrictions shown in Figure 5.6-1 prior to storage in pools "C"and "D".

2. BWR assemblies are acceptable for storage in pool "C" provided the maximum planar average enrichments are less than 4.6 wt.% U235 and Kinf is less than or equal to 1.32 for the standard cold core geometry (SCCG).

5. In each case, keff includes allowances for uncertainties as described in Section 4.3.2.6 of the FSAR.

DRAINAGE 5.6.2 The pools "A". "B". "C"and "D"are designed and shall be maintained to prevent inadvertent draining of the pools below elevation 277.

CAPACITY 5.6.3.a Pool "A" contains six (6 x 10 cell) flux trap type PWR racks and three (11 x 11 cell) BWR racks for a total storage capacity of 723 assemblies.

Pool "B"contains six (7 x 10 cell). five (6 x 10 cell), and one (6 x 8 cell) flux trap style PWR racks and seventeen (11 x 11 cell) BWR racks and is licensed for one additional (11 x 11 cell) BWR rack that will be installed as needed. The combined pool "A"and "B" licensed storage capacity is 3669 assemblies.

SHEARON HARRIS - UNIT 1 5-7a Amendment No.

DESIGN FEATURES 5.6.3.b Pool "C"is designed to contain a combination of PWR and BWR assemblies. Pool "C"can contain two (11 x 9 cell) and nine (9 X 9 cell) PWR racks for storage of 927 PWR.assemblies. Pool "C"! can contain two (8 x 13 cell), two (8 x 11 cell), six (13 x 11 cell), and hine (13 x 13 cell) BWR racks for storage of 2763 BWR assemblies. The (9 x 9 cell) PWR racks and the (13 x 13 cell) BWR racks are dimensioned to allow interchangeability between PWR or BWR storage rack styles as required. The racks in pool "C"will be installed as needed.

5.6.3.c Pool "D"contains a variable number of PWR storage spaces. These racks will be installed as needed. Pool "D"is designed for a maximum storage capacity of 1025 PWR assemblies.

5.6.3.d The heat load from fuel stored in Pools "C"and "D"shall not exceed 7.0 MBtu/hr.

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.

SHEARON HARRIS - UNIT 1 5-7b Amendment No. I

i - I- af il -

DESIGN FEATURES 45000 -

40000 Acceptable Bumup Domain 35000 -

Bumup = 12114 x Enrichment -19123 30000

\ .

c 25000-

=

C 20000 -

15000 -

10000 -

Unacceptable Bumup Domain 5000 ,

0 --- s'-

2.0 2.5 3.0 3.5 4.0 4.5 5.0 Enrichment (wvt/' U-235)

FIGURE 5.6-1 POOLS "C" and "D"BURNUP VERSUS ENRICHMENT FOR PWR FUEL SHEARON HARRIS - UNIT 1 5-7c Amendment No.

DESIGN FEATURES 45000 40000 35000 30000 M 25000 0

a-

= 20000 as 15000 10000 5000 0

1.5 2 2.5 3 3.5 4 4.5 5 Enrichment (wt% U-235)

FIGURE 5.6-2 POOLS "A" and "B"BURNUP VERSUS ENRICHMENT FOR PWR FUEL SHEARON HARRIS - UNIT 1 5-7d Amendment No. I