ML20094J634
| ML20094J634 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/06/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094J638 | List: |
| References | |
| NUDOCS 9511150395 | |
| Download: ML20094J634 (23) | |
Text
._.
. _ _ - =
p54%
y 4
UNITED STATES 2
B NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2066H001 s,
/
- .+
DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 159 License No. NPF-9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated June 13, 1994, as supplemented August 15,1994, March 23, April 18, July 21, and September 22, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i 9511150395 951106 PDR ADOCK 05000369 P
l
. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.159
. are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection P1an.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION H rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 6, 1995 i
1 suag$
o t
UNITED STATES g
3 j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 2006M001
'+9.....,o DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 141 1
License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated June 13, 1994, as supplemented August 15, 1994, March 23, April 18, July 21, and September 22, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the l
Commission's rules and regulations as set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license 1
amendment, and Paragraph 2.C.(2) of Facility Operating License No.
1 NPF-17 is hereby amended to read as follows-Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 141, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Pl an.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Hr rt N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 6, 1995
I ATTACHMENT TO LICENSE AMENDMENT NO.159 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 A!Q TO LICENSE AMENDMENT NO. 141 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 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 areas of change.
Remove Paaes Insert Paaes XV XV XIX XIX XX XX 3/4 9-16 3/4 9-16 3/4 9-17 3/4 9-17 3/4 9-18 3/4 9-19 3/4 9-20 3/4 9-21 3/4 9-22 3/4 9-23 3/4 9-24 3/4 9-25 B 3/4 9-3 B 3/4 9-3 B 3/4 9-4 B 3/4 9-5 5-7 5-7 g,'
5-7a 5-7a
't..,
5 9 g f
_~
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0UIREMENTS SECTION PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level.........................................
3/4 9-10 Low Water Level..........................................
3/4 9-11 3/4.9.9 WATER LEVEL - REACTOR VESSEL.............................
3/4 9-12 3/4.9.10 WATER LEVEL - STORAGE P00L...............................
3/4 9-13 I
3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM.................
3/4 9-14 3/4.9.12 SPENT FUEL POOL BORON CONCENTRATION.......................
3/4 9-16 3/4.9.13 SPENT FUEL ASSEMBLY ST0 RAGE...............................
3/4 9-17 TABLE 3.9-1 MINIMUM QUALIFYING BURNUP VERSUS INITIAL ENRICHMENT FOR UNRESTRICTED REGION 1 STORAGE................... 3/4 9-18 TABLE 3.9-2 MINIMUM QUALIFYING BURNUP VERSUS INITIAL ENRICHMENT FOR REGION 1 FILLER ASSEMBLIES.......................
3/4 9-19 TABLE 3.9-3 MINIMUM QUALIFYING BURNUP VERSUS INITIAL ENRICHMENT FOR UNRESTRICTED REGION 2 STORAGE.................. 3/4 9-20 TABLE 3.9-4 MINIMUM QUALIFYING BURNUP VERSUS INITIAL ENRICHMENT FOR RESTRICTED 2 STORAGE WITH FILLERS................
3/4 9-21 TABLE 3.9-5 MINIMUM QUALIFYING BURNUP VERSUS INITIAL ENRICHMENT FOR REGION 2 FILLER ASSEMBLIES.......................
3/4 9-22 FIGURE 3.9-1 REQUIRED 3 OUT OF 4 LOADING PATTERN FOR RESTRICTED REGION 1 ST0 RAGE...............................
3/4/9-23 FIGURE 3.9-2 REQUIRED 2 OUT OF 4 LOADING PATTERN FOR RESTRICTED REGION 2 ST0 RAGE...............................
3/4/9-24 FIGURE 3.9-3 REQUIRED 2 OUT OF 4 LOADING PATTERN FOR CHECKERB0ARD REGION 2 STORAGE..................
3/4/9-25 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..........................................
3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS...
3/4 10-2 3/4.10.3 PHYSICS TESTS............................................
3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS...................................
3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN....................
3/4 10-5 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4 11.1 LIQUID EFFLUENTS Liquid Holdup Tanks.......................................
3/4 11-7 3/4 11.2 GASE0US EFFLUENTS Explosive Gas Mixture.....................................
3/4 11-16 Gas Storage Tanks.........................................
3/4 11-17 McGUIRE - UNITS 1 and 2 XV Amendment No. 159 (Unit 1)
Amendment No. 141 (Unit 2)
INDEX BASES SECTION PAGE-3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.............
B 3/4 9-2 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and STORAGE P00L............................................
B 3/4 9-3 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM..................
B 3/4 9-3 3/4.9.12 and 3/4 9.13 SPENT FUEL POOL BORON CONCENTRATION and SPENT FUEL ASSEMBLY STORAGE...............
B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS....
B 3/4 10-1 3/4.10.3 PHYSICS TESTS.............................................
B 3/4 10-1 3/4.10.4 R EACTOR COO LAN T L00 PS.....................................
B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN.....................
B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.........................................
B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS........................................
B 3/4 11-3 3/4.11.3 SOLID RADI0 ACTIVE WASTE..................................
B 3/4 11-7 3/4.11.4 TOTAL D0SE...............................................
B 3/4 11-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.......................................
B 3/4 12-1 3/4.12.2 LAND USE CENSUS..........................................
B 3/4 12-2 3/4.12.3 INTERLABORATORY COMPARIS0N PR0 GRAM.......................
B 3/4 12-2 McGUIRE - UNITS 1 and 2 XIX Amendment No.159 (Unit 1)
Amendment No.141 (Unit 2)
~
INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE 5.1.1 EXCLUSION AREA...............................................
5-1 5.1.2 LOW POPULATION Z0NE..........................................
5-1 5.1.3 MAP DEFINING UNRESTRICTED AREAS FOR RADI0 ACTIVE GASE0US AND LIQUID EFFLUENTS...............................
5-1 FIGURE 5.1-1 EXCLUSION AREA.......................................
5-2 FIGURE 5.1-2 LOW POPULATION Z0NE..................................
5-3 FIGURE 5.1-3 SITE BOUNDARY FOR GASE0US EFFLUENTS..................
5-4 FIGURE 5.1-4 SITE B0UNDARY FOR LIQUID EFFLUENTS...................
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 R0D ASSEMBLIES.......................................
5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE..............................
5-7 5.4.2 V0LUME.......................................................
5-7 5.5 METEOROLOGICAL TOWER L0 CATION..................................
5-7 5.6 FUEL STORAGE 5.6.1 CRITICALITY..................................................
5-7 5.6.2 DRAINAGE.....................................................
5-7a 5.6.3 CAPACITY.....................................................
5-7a 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT............................
5-7a TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS...................
5-8 McGUIRE - UNITS 1 and 2 XX Amendment No. 159 Unit 1 Amendment No. 141 Unit 2
REFUELING OPERATIONS 3/4.9.12 SPENT FUEL POOL BORON CONCENTRATION LIMITING COMDITION FOR OPERATION 3.9.12 The boron concentration in the spent fuel pool shall be within the limit specified in the COLR.
APPLICABILITY:
During storage of fuel in the spent fuel pool.
ACTION:
a.
Immediately suspend movement of fuel assemblies in the spent fuel pool and initiate action to restore the spent fuel pool boron-concentration to within its limit.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.9.12 Verify at least once per 7 days that the spent fuel pool boron concentration is within its limit.
l I
I i
4 McGUIRE - UNITS 1 and 2 3/4 9-16 Amendment No.159 Amendment No.141
3/4.9.13 SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.13 Storage of new or irradiated fuel is limited to the configurations described in this specification.
a.
New or irradiated fuel may be stored in Region 1 of the Spent Fuel Pool in accordance with these limits:
1)
Unrestricted storage of fuel meeting the criteria of Table 3.9-1; or 2)
Restricted storage in accordance with Figure 3.9-1, of fuel which does not meet the criteria of Table 3.9-1.
b.
New or irradiated fuel which has decayed at least 16 days may be stored in Region 2 of the Spent Fuel Pool in accordance with these limits:
1)
Unrestricted storage of fuel meeting the criteria of Table 3.9-3; or 2)
Restricted storage in accordance with Figure 3.9-2, of fuel which meets the criteria of Table 3.9-4; or 3)
Checkerboard storage in accordance with Figure 3.9-3 of fuel which does not meet the criteria of Table 3.9-4.
APPLICABILITY:
During storage of fuel in the spent fuel pool.
ACTION:
a.
Immediately initiate action to move the noncomplying fuel assembly to the correct location.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.9.13 Prior to storing a fuel assembly in the spent fuel storage pool, verify by administrative means the initial enrichment and burnup of the fuel assembly are in accordance with Specification 3.9.13.
McGUIRE - UNITS 1 and 2 3/4 9-17 Amendment No.159 Amendment No.141
Table 3.9-1 Minimum Qualifyino Burnup Versus initial Enrichment for Unrestricted Region 1 Storace Initial Nominal Enrichment Assembly Burnup (Weicht% U-235)
(GWD/MTU) 4.19(or less) 0 4.20 0.04 4.50 1.92 l
4.75 3.40 1
'l 5-
-R4 3
ACCEPTABLE T
For Unrestricted Storage c5 2--
5 l
EN i UNACCEPTABLE M
For Unrestricted Storage 0
4.00 4.25 4.50 4.75 initial Nominal Enrichment (Weight % U-235) i l
Fuel which differs from those designs used to determine the requirements of Table 3.9-1 may be qualified for Unrestricted Region 1 storage by means of an analysis using NRC approved methodology to assure that k,,, is less than or equal to 0.95.
Likewise, previously unanalyzed fuel up to 4.75 weight % U-235 may be qualified for Restricted Region 1 storage by means of an analysis using NRC approved methodology to assure that k,,, is less than or equal to 0.95.
McGUIRE - UNITS 1 and 2 3/4 9-18 Amendment No.159 Amendment No.141
Table 3.9-2 Minimum Oualifyina Burnuo Versus Initial Enrichment for Reaion 1 Filler Assemblies Initial Nominal Enrichment Assembly Burnup (Weicht% U-235)
(GWD/MTU) 2.92(orless) 0 3.00 1.57 3.50 13.30 4.00 18.32 4.50 23.36 4.75 25.84 30 -
p 25 -
ACCEPTABLE g 20 -
For Use As Filler Assembly a.
i! 15 -
c5
& 10 -
UNACCEPTABLE For Use As Filler Assembly k
5-0 2.5 3
3.5 4
4.5 4.75 Initial Nominal Enrichment (Weight % U-235)
Fuel which differs from those designs used to determine the requirements of Table 3.9-2 may be qualified for use as a Region 1 Filler Assembly by means of an analysis using NRC approved methodology to assure that k,,, is less than or equal to 0.95.
McGUIRE - UNITS 1 and 2 3/4 9-19 Amendment No. 159 Amendment No. 141
Table 3.9-3 Minimum Oualifyina Burnuo Versus Initial Enrichment for Unrestricted Reaion 2 Storace Initial Nominal Enrichment Assembly Burnup (Weiaht% U-235)
(GWD/MTU) 2.00(or less) 10.54 2.50 17.96 3.00-24.64' 3.50 30.86 4.00 36.75 4.50 42.38 4.75 45.10 60 - -
g 50 -
ACCEPTABLE N
For Unrestricted Storage 40 v
$30 5
s 20 -
UNACCEPTABLE y
For Unrestricted Strage l
4 10 -
I 0
2 2.5 3
3.5 4
4.5 4.75 l
Initial Nominal Enrichment (Weight % U-235) l Fuel which differs from those designs used to determine the requirements of Table 3.9-3 may be qualified for Unrestricted Region 2 storage by means of an analysis using NRC approved methodology to assure that k,,, is less than or equal to 0.95.
i McGUIRE - UNITS 1 and 2 3/4 9-20 Amendment No. 159 Amendment No. 141
Table 3.9-4 Minimum Oualifyina Burnuo Versus Initial Enrichment for Restricted Reaion 2 Storace with Fillers Initial Nominal Enrichment Assembly Burnup (Weiaht% U-235)
(GWD/MTU) 2.00(orless) 4.22 2.50 10.75 3.00 16.80 3.50 22.41 4.00 27.92 4.50 33.14 4.75 35.65 60 50 -
N g 40 ACCEPTABLE For Restricted Storage v
h 30 --
cB g 20 --
5 UNACCEPTABLE M 10 -
For Restricted Storage 0
2 2.5 3
3.5 4
4.5 4.75 Initial Nominal Enrichment (Weight % U-235)
Fuel which differs from those designs used to determine the requirements of Table 3.9-4 may be qualified for Restricted Region 2 Storage by means of an analysis using NRC approved methodology to assure that k,,, is less than or equal to 0.95.
McGUIRE - UNITS 1 and 2 3/4 9-21 Amendment No. 159 Amendment No. 141
. ~. -...
Table 3.9-5 l
.M_,inimum Oualifyino Burnup Versus Initial Enrichment for Reaion 2 Filler Assemblies I
Initial Nominal Enrichment Assembly Burnup (Weiaht% U-235)
(GWD/MTU) 2.00(or less) 18.03 l
2.50 26.71 3.00 33.79 t
3.50 40.56 l
4.00 46.83 4.50 52.86 4.75 55.78 i
i t
i 60 -
ACCEPTABLE
^ 50 For Use As Frier Assembly i
40 -
v 80 '
UNACCEPTABLE f 20 "
For Use As FHier Assembly 8
.E 10 -
0 2
2.5 3
3.5 4
4.5 4.75 initial Nominal Enrichment (Weight % U-235)
Fuel which differs from those designs used to determine the requirements of Table 3.9-5 may be qualified for use as a Region 2 Filler Assembly by means of an analysis using NRC approved methodology to assure that k,,, is less than or equal to 0.95.
j McGUIRE - UNITS 1 and 2 3/4 9-22 Amendment No. 159 Amendment No. 141
Fiqure 3.9-1 Reauired 3 out of 4 Loadina Pattern for Restricted Reaion 1 Storace m-
.a.s.Nk
$!$0!
'!!N"N
'I REmmEn RESTRerEn RE m eTEo PUEL PUBL PUEL PUEL dih-.m.,~ m,m. m.=_==.. -
_.. -. m
_=x.,-
m _,3_=........==
m
=,==.=.=_.,L
=
=
=
.y__
i I
3Hidibunns iiHn6MnHdii mamem ~
w=m me -
RESTRCTEo PLLER RESTRCTEo PE.LER PUEL LOCATION PUEL LOCATION
=n== =n
====5=n:
=
u==n
~.m =w
.gn=g; m..
2.;m. mg=
Bl!!Blii b = n:
BilHn== =:
- = = = ===
RESTRcTEo RESTmcTEo cTEo PUEL PUEL PUEL PUEL wiggrgg nasa
- s enteen!med
... ~...
._.L.
- ..._na.."ne.,
a.ug.*wi.
5.., =.n g =.. a.. =...
- =
=.-
- ...m.... m...
l I
I RESTRCTEo PILLER RESTRCTEo PILLER PUEL LOCATION PUEL LOCATION l
m.......,..
=====.
=_=..=~c=.. n. n.
]
Restricted Fuel:
Fuel which does not meet the minimum burnup requirements of Table 3.9-1.
(Fuel which does meet the requirements of Table 3.9-1, or non-fuel components, or an empty location may be placed in restricted fuel locations as needed)
Filler Location:
Eith'er fuel which meets the minimum burnup requirements of Table 3.9-2, or an empty cell.
Boundary Condition: Any row bounded by a Region 1 Unrestricted Storage Area shall contain a combination of restricted fuel assemblies and filler locations arranged such that no restricted fuel assemblies are adjacent to each other.
Example:
In the figure above, row 1 or column 1 can not be adjacent to a Region i Unrestricted Storage Area, but row 4 or column 4 can be.
McGUIRE - UNITS 1 and 2 3/4 9-23 Amendment No. 159 Amendment No. 141
1 1
I I
Fiaure 3.9-2 Reauired 2 out of 4 Loadina Pattern for Restricted Reaion 2 Storace i
I osmannuun unte===
l Maccts;=;ntu
=mnMMunt.
RESTRcrEn ruBR RESTRcrED PuMR PUEL LOCATION PUBL LOCATION
\\
auisilfanan:
=unnmunsi n nwuw nunntunut
- a i
r ngg:
l Mutagemum:
J PEAER RESTRICTED PE1ER RESTRICTED LOCATION PUEL LOCATIC?l PUEL i
M j
iM.r" '"'inG=li.
j n
EM=9 m========
1 e
- ~"~~~
UIE*h"MME11 M E "M C)"d"8
'g$"id 3
l "M:FdM '
s j
RESTRICTED PE.LER RESTRICTED PE1ER 1
PUEL LOCATION PUEL LOCATION uwAk222n5Ihhirhh!
dh555khhS AEhEhh' h i
^
t i
s?nins = = = ;
"=ns=?m!!:
i e
t i
i indHnunn:e nnsnanci' 4comunrmin==!i n:mme-mne a
F11ER RESTRICTED PE.LER RESTRICTED LOCATION PUEL LOCATION PUEL in
== =:
mgspw vm jg_g_gggggggj; e.
.~... _...
1 4
I Restricted Fuel:
Fuel which meets the minimum burnup requirements of Table j
3.9-4, or non-fuel components, or an empty location.
4 i
Filler Location:
Eith.er fuel which meets the minimum burnup requirements of Table 3.9-5, or an empty cell.
Boundary Condition: No restrictions on boundary assemblies.
a
?
iii I
i j
1 4
1 1
McGUIRE - UNITS 1 and 2 3/4 9-24 Amendment No. 159 i
Amendment No. 141 1
i
M Fiqure 3.9-3 Recuired 2 out of 4 Loadina Pattern for Checkerboard Reaion 2 Storace i
- E NIN35!EEl
~
i CHEC0GR50ARIl EarTY CHECKER 50ARIl ERrTY j
FUEL CELL FUEL CELL yg
!MHrm aua m,
4
$EH$teme i
I EEiMiEEl!l a
EIFTY CHECKERSOARIl ERrTY CELL FUEL CELL FUEL isi i ly,i.i.ni.iH.e. o p1..
m m
j f
1 t
..#y.... &, _,. _
.......m.....
H5!MH!H! Ens RH!!E!N!HE!i CHECKERSOARIl EarTY CHECKERSOARIl ERWTY FUEL CEu.
FUEL CELL M EE
!!!EliE!EEll 4
5 I
M 3..N. jj 1
EarTY CHanw-- u Ril marTY CELL PUEL CELL FUEL
ER4.
---MFKK
.m.
9
=
1 1
i j
Checkerboard Fuel:
Fuel which does not meet the minimum burnup requirements of Table 3.9-4.
(Fuel which does meet the requirements of i
Table 3.9-4, or non-fuel components, or an empty location j
may.be placed in restricted fuel locations as needed) l Boundary Condition: At least two opposite sides shall be bounded by either an empty row of cells, or a spent fuel pool wall.
i i
.i i
a 4
i McGUIRE - UNITS 1 and 2 3/4 9-25 Amendment No.159 j
Amendment No.141'
~ _ _ _.
BASES -
2 3
i c
3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and STORAGE POOL 1
-i The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity l
released from the rupture of an irradiated fuel assembly.
The minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM The limitations on the Fuel Handling Ventilation Exhaust System ensure that all radioactive material released from an irradiated fuel assembly will I
I be filtered through the HEPA filters and charcoal adsorbers. prior. to discharge to the atmosphere.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
j The methyl iodide penetration test criteria for the carbon samples have been made more restrictive than required for the assumed iodine removal in.the l
accident analysis because the humidity to be seen by the charcoal adsorbers may be greater than 70% under normal operating conditions.
j 3/4.9.12 and 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION and SPENT FUEL i
ASSEMBLY STORAGE The requirements for spent fuel pool boron concentration specified in Specification 3.9.12 ensure that a minimum boron concentration is maintained in the pool.
The requirements for spent fuel assembly storage specified in l
Specification 3.9.13 ensure that the pool remains subcritical. The water in the spent fuel storage pool normally contains soluble boron, which results in
.large subcriticality margins under actual operating conditions. However, the NRC guidelines based upon the accident condition in which all soluble poison is assumed to have been lost, specify that the limiting k,,, of 0.95 be evaluated in the absence of soluble boron. Hence the design of the spent fuel storage racks is based on the use of unborated water, which maintains each region in a subcritical condition during normal operation with the spent fuel pool fully loaded.
The double contingency 1975 and the April 1978 NRC letter (Ref. 4) principle discussed in ANSI N-16.1-allows credit for soluble boron under other abnormal or accident conditions, since only a single accident need be considered at one time.
For example, the most severe accident scenario is associated with the movement of fuel from Region 1 to Region 2, and accidental misloading of a fuel assembly in Region 1 or Region 2.
This could increase the reactivity of the spent fuel pool. To mitigate these postulated criticality related accidents, boron is dissolved in the pool water.
. Tables 3.9-1 through 3.9-5 allow for specific criticality analyses for fuel which does not meet the requirements for storage defined in these tables.
These analyses would require using NRC approved methodology to ensure that k,,,
s 0.95 with a 95 percent probability at a 95 percent confidence level as described in Section 9.1 of the FSAR.
This option is intended to be used for fuel not included in previous criticality analyses.
Fuel storage is still limited to the configurations defined in TS 3.9-13.
The use of specific analyses for qualification of previously unanalyzed fuel includes, but is not McGUIRE - UNITS 1 and 2 B 3/4 9-3 Amendment No.159 Amendment No.141
3/4.9 REFUELING OPERATIONS BASES 3/4.9.12 and 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION and SPENT FUEL ASSEMBLY STORAGE (Continued) limited to, fuel assembly designs not previously analyzed which may be as a result of new fuel designs or fuel shipments from another facility. Another more likely, and expected use of this specific analysis provision would be to analyze movement and storage of. individual fuel pins as t result of reconstitution activities.
In verifying the design criteria of k,,,5 0.95, the criticality analysis assumed the most conservative conditions, i.e. fuel of the maximum permissible reactivity for a given configuration. Since the data presented in Specification 3.9.13.a and 3.9.13.b represents the maximum reactivity requirements for acceptable storage, substitutions of less reactive components would also meet the k,,, 5 0.95 criteria. Hence, any non-fuel component may be placed in a designated empty cell location.
Likewise, an empty cell, or a non-fuel component may be substituted for any designated fuel assembly location.
These, or other substitutions which will decrease the reactivity of a particular storage cell will only decrease the overall reactivity of the spent fuel storage pool.
If both restricted and unrestricted storage is used in Region 1, an additional criteria has been imposed to ensure that the boundary row between these two configurations would not locally increase the reactivity above the required limit.
Likewise if checkerboard storage is used in Region 2, an additional restriction has been imposed on the boundaries of the checkerboard storage region to ensure that the reactivity would not increase above the required limit. No other restrictions on region interfaces are necessary.
Specifications 3.9.13.b.2 or 3.9.13.b.3)g pattern restrictions, (per For storage in Region 2 requiring loadin fuel may be stored in either the
" cell" or "non-cell" locations.
" Cell" locations are the areas inside the fabricated storage cells and "non-cell" locations are the storage locations created by arranging the fabricated storage cells in a checkerboard configuration. Hence the "non-cell" locations are the areas defined by the outside walls of the 4 adjacent " cell" locations.
The action statement applicable to fuel stcrage in the spent fuel pool requires that action must be taken to preclude the occurrence of an accident or to mitigate the consequences of an accident in progress.
This is most efficiently achieved by immediately suspending the movement of fuel assemblies.
Prior to the resumption of fuel movement, the requirements of the LCOs must be met.
This requires restoring the soluble boron concentration and the correct fuel storage configuration to within the corresponding limits.
This does not preclude movement of a fuel assembly to a safe position.
The surveillance requirements ensure that the requirements of the two LCOs are satisfied, namely boron concentration and fuel placement.
The boron concentration in the sperit fuel pool is verified to be greater than or equal to the minimum limit. The fuel assemblies are verified to meet the subcriticality requirement by meeting either the initial enrichment and burnup McGUIRE - UNITS 1 and 2 B 3/4 9-4 Amendment No. 159 Amendment No. 141
3/4.9 REFUELING OPERATIONS BASES j
3/4.9.12 and 3/4.9.13 SPENT FUEL P0OL BORON CONCENTRATION and SPENT FUEL ASSEMBLY STORAGE (Continued) requirements of Table 3.9-1 through 3.9-5, or by using NRC approved methodology to ensure that k,, s 0.95.
By meeting either of these requirements, the analyzed accidents are fully addressed.
The fuel storage requirements and restrictions discussed here and applied in i
section 3.9.13 are based on a maximum allowable fuel enrichment of 4.75 weight % U-235. The enrichments listed in Tables 3.9-1 through 3.9-5 are nominal enrichments and include uncertainties to account for the tolerance on the as built enrichment. Hence the as built enrichments may exceed the enrichments listed in the tables by up to 0.05 weight % U-235. Qualifying burnups for enrichments not listed in the tables may be linearly. interpolated between the enrichments provided. This is because the reactivity of an 1
assembly, varies linearly for small ranges of enrichment.
REFERENCES 1.
" Regulatory Guide 1.13: Spent Fuel Storage Facility Design Basis", U.S.
Nuclear-Regulatory Commission, Office of Standards Development, Revision 1, December 1976.
2.
" Design' 0bjectives for Light Water Reactor Spent Fuel Storage Facilities at Nuclear Power Stations", American Nuclear Society, ANSI N210-1976/ANS-57.2, April 1976.
3.
FSAR, Section 9.1.
4.
Double contingency principle of ANSI N16.1-1975, as specified in the April 14,1978 NRC letter (Section 1.2) and implied in the proposed revision to Regulatory Guide 1.13 (Section 1.4, Appendix A).
l j
McGUIRE - UNITS 1 and 2 B 3/4 9-5 Amendment No.159 Amendment No. 141
DESIGN FEATURES 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 5.2 of the FSAR, with allowance for normal 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 680*F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,040 1 100 cubic feet at a nominal T,y, of 525*F.
5.5 METEOROLOGICAL TOWER LOCATION I
5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 a.
The spent fuel storage racks are designed and shall be maintained with:
1) k 5 0.95 if fully flooded with unborated water as d,e,s,cribed in Section 9.1 of the FSAR; and 2)
A nominal 10.4" center to center distance between fuel assemblies placed in Region 1; and 3)
A nominal 9.125" center to center distance between fuel assemblies placed in Region 2.
b.
The new fuel storage racks are designed and shall be maintained with:
k, 5 0.95 if fully flooded with unborated water as 1) d,es,cribed in Section 9.1 of the FSAR; and k,5 0.98 if moderated by aqueous foam as described in 2)
S,,ction 9.1 of the FSAR; and e
3)
A nominal 21" cer,ter to center distance between fuel assemblies placed in the storage racks.
McGUIRE - UNITS 1 and 2 5-7 Amendment No.159 Amendment No.141
DESIGN FEATURES 5.6 FUEL STORAGE (Continued)
DRAIN)GE
{
5.6.2 The spent fuel storage pool is designed and shall be maintained to i
prevent inadvertent draining of the pool below elevation 745 ft. 7 in.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a Jtorage capacity limited to no more than 1463 fuel assemblies (286 spaces in i
Region 1 and 1177 spaces in Region 2).
1 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT i
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.
I I
i r
i l
l I
l l
l l
1 l
1 McGUIRE - UNITS I and 2 5-7a Amendment No.159 Amendment No.141