ML20141B026
| ML20141B026 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/12/1997 |
| From: | Wetzel B NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20141B032 | List: |
| References | |
| NUDOCS 9706230246 | |
| Download: ML20141B026 (62) | |
Text
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i UNITED STATES
- s y
NUCLEAR REEULATORY COMMISSION 1
WASHINGTON, D.C. 300MMm01 4 *****,o
)
NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.129 License No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated July 28, 1995, as revised February 21. 1997.
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act). and the Commission's rules and regulations set forth in 10 CFR Chapter I:
B.
The facility will operate in conformity with the application, 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 l
conducted in compliance with the Commission's regulations:
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:
l 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 amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-42 is hereby i
amended to read as follows:
l 9706230246 970612
~
PDR ADOCK 05000282 P
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Technical Soecifications The Technical Specifications contained in Appendix A, as revised l
through Amendment No.129. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, with full implementation within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 0-v l
Beth A. Wetzel, Project Manager l
Project Directorate 111-1 i
i Division of Reactor Projects - III/IV i
Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical Specifications l
l Date of Issuance: June 12, 1997 l
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1 ATTACHMENT TO LICENSE AMENDMENT NO.129 l
FACILITY OPERATING LICENSE NO. DPR-42 DOCKET NO. 50-282 i
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l Revise Appendix A Technical S>ecifications by removing the pages identified l
.below and inserting the attacled pages. The revised pages are-identified by l
amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT TS-vi TS-vi l
TS-xi TS-xi TS-xiii TS-xiii TS.3.8-4 TS.3.8-4 TS.3.8-5 Figure TS.3.8-1 Figure TS.3.8-1 Figure TS.3.8-2 Table TS.4.1-2B (Page 1 of 2)
Table TS.4.1-28 (Page 1 of 2)
Table TS.4.1-2B (Page 2 of 2)
Table TS.4.1-2B (Page 2 of 2)
TS.4.20-1 i
TS.S.6-1 TS.5.6-1 TS.5.6-3 TS.5.6-3 Figure TS.S.6-1 Figure TS.5.6-1 Figure TS.5.6-2 Figure TS.5.6-2 Figure _TS.S.6-3 Figure TS.S.6-4 Figure TS.5.6-5 Figure TS.S.6-6 Figure TS.5.6-7 Figure TS.5.6-8 Figure TS.S.6-9 l
Figure TS.S.6-10 Figure TS.S.6-11
- i Figure TS.5.6-12 B.3.8-2 B.3.8-2 B.3.8-3 B.3.8-3 B.3.8-4 B.3.8-4 B.3.8-5 B.4.20-1
TS-vi TABLE OF CONTENTS fContinued)
TS SECTION M
PAGE 4.12 Steam Generator Tube Surveillance TS.4.12-1 A. Steam Generator Sample Selection and TS.4.12-1 Inspection B. Steam Generator Tube Sample Selection TS.4.12-1 and Inspection C. Inspection Frequencies TS.4.12-3 D. Acceptance Criteria TS.4.12-4 E. Reports TS.4.12-5 4.13 Snubbers TS.4.13-1 4.14 Control Roon Air Treatment System Tests TS.4.14-1 4.15 Spent Fuel Fool Special ventilation System TS.4.15-1 4.16 Deleted 4.17 Deleted 4.18 Reactor Coolant Vent System Paths TS.4.18-1 A. Vent Path Operability TS.4.18-1 B. System Flow Testing TS.4.18-1 4.19 Auxiliary Building Crane Lifting Devices TS.4.19-1 4.20 Spent Fuel Pool Storage Configuration TS.4.20-1 l
Prairie Island Unit 1 Amendment No.,126,.322' 129 Prairie Island Unit 2 Amendment No. Ji&,"J45; 121 u
TS-xi i
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TABLE OF C0ium.nts (continued) l TS BASES SECTION M
PACE l
4.0 BASES FOR SURVEII.1ANCE REQUIREMENTS 4.1 Operational Safety Review B.4.1-1 l
4.2 Inservice Inspection and Testing of Pumps 3.4.2-1 and Valves Requirements
)
4.3 Primary Coolant System Pressure Isolation B.4.3-1 Valves i
4.4 Contairusent Systen Tests 3.4.4-1 4.5 Engineered Safety Features B.4.5-1 4.6 Periodic Testing of Emergency Power Systems B.4.6-1 4.7 Main Steam Isolation Valves B.4.7-1 l
4.8 Steam and Power Conversion Systems B.4.8-1 4.9 Reactivity Anomalies B.4.9-1 4.10 Deleted 4.11 Deleted 4.12 Steam Generator Tube Surveillance B.4.12-1 4.13 Snubberg 3.4.13-1 4.14 Control Room Air Treatment System Tests B.4.14-1 4.15 Spent Fuel Fool Special Ventilation System B.4.15-1 j
4.16 Deleted l
4.17 Deleted 4.18 Reactor Coolant Vent System Paths B.4.18 1 4.19 Auxiliary Building Crane Lifting Devices B.4.19-1 l
4.20 Spent Fuel Fool Storage Configuration B.4.20-1 1
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Prairie Island Unit 1 Amendment No. M M 129 i
Prairie Island Unit 2 Amendment NO. ) FI.,M M 121
.. ~. _
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TS-xiii APPENDIT A TECHNICAL SPECIFICATIONS y.._...._...
LIST OF FIGURES
- T$ FIGURE TITLE 2.1-1 Reactor Core Safety limits
.3.1-1 Unit 1 and Unit 2 Reactor Coolant System Heatup Limitations 3.1-2 Unit I and Unit 2 Reactor Coolant System Cooldown Limitations 3.1-3 DOSE EQUIVALENT I-131 Primary Coolant specific Activity 1.init Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >1.0 uCi/ gram DOSE EQUIVALENT I-131 3.8-1 Spent Fuel Pool Unrestricted Region Burnup and Decay Time 3
Requirements - OFA Fuel j
3.8-2 Spent Fuel Fool Unrestricted Region Burnup and Decay Time Requirements - STD Fuel l
3.10-1 Required Shutdown Margin Vs Reactor Boron Concentration 4.4-1 Shield Building Design In Imakage Rate 5.6-1 Spent Fuel Pool Burned / Fresh Checkerboard Cell Imyout 5.6-2 Spent Fuel Fool Checkerboard Interface Requirements 5.6-3 Spent Fuel Fool checkerboard Region Burnup and Decay Time Requirements - OFA Fuel, Ns CAD 5.6-4 Spent Fuel Fool checkerboard Region Burnup and Decay Time Requirements.STD Fuel, No CAD 5.6-5 Spent Fuel Pool checkerboard Region Durnup and Decay Time m
Requirements - OFA Fuel. 4 GAD l
5.6-6 Spent Fuel Fool Checkerboard Region Burnup and Decay Time l
Requirements - STD Fuel, 4 GAD l
5.6-7 Spent Fuel Fool Checkerboard Region Burnup and Decay Time Requirements - OFA Fuel, 8 GAD 5.6-8 6 pent Fuel Fool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 8 GAD 5.6-9 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - OFA Fuel, 12 GAD 5.6-10 spent Fuel Pool checkerboard Region Burnup and Decay Time l
Requirements - STD Fuel, 12 GAD j
5.6-11 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - OFA Fuel,16 or More GAD 5.6 12 Spent Fuel Fool checkerboard Region Burnup and Dec,ay Time Requirements - STD Fuel, 16 or More GAD 5.2.1-1 Origin of Safety Limit curves at 2235 psig with delta-T Trips and locus of Reactor Conditions at which SG Safety Valves Open i
Prairie Island Unit 1 Amendment No. g g 129 Prairie Island Unit 2
. Amendment No. g K 121'
l.---..
-. -. -..... ~. - -.
-. _..... ~ - _. -
TS.3.8 4 l
3.8.C.
Small Seent Fuel Pool Restrictions No more than 45 recently discharged assemblies shall be located in the
_small pool 4 pool No. 1)..
_r D.
Seent Fuel Pool Soecial Ventilation System l
1.
Both trains of the spent Fuel Pool Special Ventilation System shall be OPERAB12 at all times (except as specified in 3.8.D.2 'and 3.8.D.3 below).
1 j
2.
With one train of the Spent Fuel Pool Special Ventilation System l
inoperable, fuel handling operations and crane operations with loade over spent fuel (inside the spent fuel pool enclosure) are i
l permissible during the following 7 days, provided the redundant i
train is demonstrated OPERABLE prior to proceeding with those operations.
3.
With both trains of the Spent Fuel Pool Special Ventilation System inoperable, suspend all fuel handling operations and crane 1
operations with loads over spent fuel (inside the spent fuel pool enclosure).
l 4.
'The provisions of specification 3.0.C are not applicable.
E.
Soert Fuel Pool Storare l
1.
Fuel Assembly Storage j
a.
The combination of initial enrichment, burnup and decay time of each spent fuel assembly stored in the spent fuel pool shall be l
within.the unrestricted range of Figures TS.3.8-1 or TS.3.8-2, l
as applicable, or fuel assemblies shall be stored in accordance with Specification,5.6.A.1.e.
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b.
If the requirements of 3.8.E.1.s are not met, immediately initiate action to move any noncomplying fuel assembly to an acceptable location.
l The p' ovisions of specification 3.0.C are not applicable.
l c.
r 2.
Spent Fuel Fool Boron Concentration l
s.
The spent fuel pool boron concentration shall be k 1,800 ppa when fuel assemblies are stored.in the spent fuel pool.
I b.
If the spent fuel pool boron concentration is not within limit.
then immedi'ately:
- 1. Suspend movement of fuel assemblies in the spent fuel pool, ed
- 2. Initiate action to restore spent fuel pool boron concentration to within limit.
The provisions of Specification 3.0.C are not applicabl[e. d129 c.
Prairie Island Unit 1 Amendment No.
Prairie Island Unit 2 Amendment No.
,)&!,121
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FIGURE TS.3.3 1 40000 l
,y,,,,
35000
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s rears
/ /, 10 years
///,
gsv.ars
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30000
///Af s
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9 NTRICTED
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n 25000
/ /H/
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/WK h 0000
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10000 A V 2
RESTRICTED 2
[
5000
/
rl O
/
1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)
FIGURE TS.3.8-l' Spent Fuel
- Pool Unrestricted Region Burnup and Decay Time Requiremente - 0FA Fuel Prairie Island Unit 1 Amendment No. 18f, 129, Prairie Island Unit 2 Amendment No. }Or; 321
TIGURE TS.3.8-2 40000 i
a o years j
I
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s rears i
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j 35000
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/- 10 Years i
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/ / // 20 years
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>" 20000
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RESTRICTED D
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5000
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1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)
FIGURE TS.3.8-2 Spent Fuel Fool Unrestricted Region Burnup and Decay Time li Requirements - STD Fuel Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No.121
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Tchlo~ TS.4.1-2B (Pege 1 cf 2) i 1
TABLE TS.4.1-2B
~ -~ ~~EINIMUM TREOUENCIES TOR SAMPLING TESTS
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4 TEST TREOUENCY 1.
RCS cross 5/ week Activity Determination 2.
RCS Isotopic Analysis for DOSE 1/14 days (when at power)
EQUIVALENT I-131 Concentration 3.
RCS Radiochemistry E determination 1./6 months (1) (when at power)
I 4.
RCS Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever i
Including I 131 I-133, and I-135 the specific activity ax-coeds 1.0 uCi/ gram DOSE _
EQUIVALENT I-131 or 100/E uCi/ gram (at or above cold shutdown), and b) One sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period (above hot shutdown) 5.
RCS Radiochemistry (2)
Monthly 6.
- Weekly 7.
RCS Chemistry (Cl*,7", 02) 5/ Week 8.
RCS Boron Concentration *(3) 2/ Wee.k (4) 9.
RWST Boron Concentration Weekly
- 10. Boric Acid Tanks Boron Concentration 2/ Week
- 11. Caustic standpipe NaOH Concentration Monthly
- 12. Accumulator Boron concentration Monthly
- 13. Spent Fuel Pit Boron concentration Weekly
- Required at all times.
Prairie Island Unit 1 Amendment Nos.
, 129 Prairie Island Unit 2 Amendment Nos.
, 121
Tcbis TS.4.1-2B (Pego 2 of 2)
TABLE TS.4.1-2B i
MINIMLH FREOUENCIES FOR SAMPLING TESTS l -
TEST FREOUENCY
- 14. Secondary coolant Cross Weekly Beta-Gamma activity
- 15. Secondary Coolant Isotopic 1/6 months (5)
Analysis for DOSE EQUIVALENT I-131 concentration
- 16. Secondary coolant chemistry pH 5/ week (6) i pH Control Additive 5/ week (6)
Sodium 5/ week (6) l Notes:
i 1.
Sample to be taken after a minimum of 2 ETPD and 20 days of POWER OPERATION have elapsed since reactor was last suberitical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
1 2.
To determine activity of corrosion products having a half-life greater than 30 minutes.
3.
During REFUELING, the boron concentration shall be verified by chemical analysis daily.
l 4.
The maximum interval between analyses shall mot axceed 5 days. -
5.
If activity of the samples is greater than 10% of the limit in Specification 3.4.D the frequency shall be once per month.
6.
The maximum interval b' etween analyses shall not exceed 3 days.
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Prairie Island Unit 1 Amendment No.
, 129 Prairie Island Unit 2 Amendment No.
4, 121
TS.4.20-1 l
4.20 Seent Fuel Pool Storare Confiruration Anolicability
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This surveillance is applicable whenever fuel is stored in the spent fuel pool.
Obiective To verity that fuel as6emblies in the spent fuel pool are' stored in accordance with the requirements of Specification 3.8.E.1.a.
Snecification
.A spent fuel pool inventory verification shall be perfermed within 7 days of the completion of any fuel handling campaign which involves the relocation of fuel l
assemblies within the spent fuel pool or the addition of. fuel assemblies to the spent fuel pool.
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Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
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5.6 FUEL HANDLING A.
Criticality consideration 1.
The spent fuel storage racks are designed (Reference 1) and shall be
. maintained with:
Fuel assemblies having a maximus U-235 enrichment of 5.0 weight s.
percent; b.
Art < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Reference 3;
- c. ber s 0.95 if fully flooded with water borated to 750 ppa, which includes an allowance for uncertainties as described in Reference 3;
I d.
New or spent fuel assemblies with a combination of discharge i
burnup, initial enrichment and dec'ay time in the unrestricted range of Figures TS.3.8-1 or TS.3.8-2, as applicable, may be allowed unrestricted storage in the spent fuel racks; and New or spent fuel assemblies with a combination of discharge e.
burnup, initial enrichment and decay time in the restricted range of Figures TS.3.8-1 or TS.3.8-2, as applicable, will be stored in l
compliance with Figures TS.5.6-1 through TS.5 6-12.
2.
The new fuel storage racks are designed (Reference 1) and shall be maintained with:
a.
Fuel assemblies having a maximum U 235 enrichment of 5.0 wei ht 5
percent; b.
bre s 0.95 if fully flooded with unborated water, which includes an allowance.for uncertainties as described in Reference 2; and
- c. '%rr s 0.98 if' accidentally filled with a low density moderator which resulted in optimum low density. moderation conditions.
3.
Fuel will not'be ' inserted into a spent fuel cask in the pool, unless a minimum boron concentration of 1800 ppa is present. The 1800 ppm will ensure that k er for the spent fuel cask, including statistical e
uncertainties, will be less than or equal to 0.95 for all postulated arrangements of fuel within the cask. The criticality analysis for the TN-40 spent fuel sto' rage cask was based on fresh fuel enriched to 3.85 weight, percent U-235.
B.
Soent Fuel Storare Structure The spent fuel storage pool is enclosed with a reinforced concrete building having 12-to 18-inch thi.ek walls and roof *(Reference 1).
The pool and pool enclosure are Class I (seismic) structures that afford protection against loss of integrity from postulated tornado missiles. The storage compartments and the fuel transfer canal are connected by fuel transfer slots that can be closed off with pneumatically sealed gates..The bottoms of the slots are above the tops of the active fuel in the fuel assemblies which will be stored vertically in specially constructed. racks.
Amendment No. g M, 129 Prairie Island Unit 1 Amendment No.
327}&T,121 Prairie Island Unit 2
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D.
Spent Fuel Storare Canacity The spent fuel storage. facility is.a two compartment pool that, if completely filled with fuel storage racks, provides up to 15P7 storage locations. The southeast corner of the maall pool (pool r.
- 3 also serves as the cask lay down area. During times when the c.s is being used, four racks are removed from the small pool. With the four storage racks in the southeast corner of pool 1 ' removed, a total of 13 M sterage locations are provided. To allow insertion of a spent fuel e sk, tetsi stcrage is limited to 1386 assemblies, not including those assemblies whfch can be returned to the reactor.
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4 Reference 1.
USAR, Section 10.2 2.
" Criticality Analysis of the Prairie Island Units 1 & 2 Fresh and Spent Fuel Racks", Westinghouse Commercial Nuclear Fuel Divisi>n, February 1993.
3.
' Northern States Power Prairie Island Uriits 1 and 2 %ent Fuel Rack Criticality Analysis Using' Soluble Boron. Credit *, Westinghouse Commercial Nuclear Fuel Division, February 1997.
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AmendmentNo.[pfMI,1 Prairie Island Unit 1 Prairie Island Unit 2 Amendment No.
FIGURE TS.5.6 1 f
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E E
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Fresh Fuel:
Must be less than or equal to nominal 4.95 w/o zasU No restrictions on burnup Burned Fuel: Must satisfy minimum burnup requirements of Figures TS.5.6-3 through TS.6.6-12 depending on number of GAD rods in fresh fuel FIGURE TS.5.6-1 spent Fuel Fool Burned / Fresh Checkerboard Cell layout i
1 Prairie Island Unit 1 Amendment No. I 129 Prairie Island Unit 2 Amendment No.
, 121
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ncURE T5.5.6 2 i
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MMMMME i
MEEEEE interface E
ME ME I
8 i
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e Fresh Fuel:
Must be less than or equal to i
nominal 4.95 w/o ***U No restrictions on bumup t
Bumed Fuel:
3x3 Checkerboard Region I
Must satisfy minimum bumup requirements l
of Figures TS.5.6-3 through TS.6.6-12 i
4 l
Burned Fuel:
All Cell Unrestricted Region j
Must satisfy minimum bumup requirements j
of Figures TS.3.8-1 orts.3.8-2
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j TIcURE 7S.5.6-2 Spent Fuel Pool Checkerboard Interface Requirements i
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i Prairie Island Unit 1 Amendment No. g. 129 j
Prairie Island Unit 2 Amendment No. JDr 121 i
FIGURE 7S.5.6-3 d
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55000 I
i n.
0 Years 1
i e
a
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j 50000 s Years
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10 Years f,
f,
15 Years i
f of f; t
45000 20Yuxe f,
f, i
ACCEPTABLE
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NOT ACCEPTABLE 10000 fj f
if F
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5000 j
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1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) 4 TS.5.6 3 Spent Fuel Pool Checkerboard Region Burnup and Decay Time f
Requirements - OEA Fuel, No CAD i
i Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121 s
=
.______..____._.._._.______..._.__._._._____..-.m.
f TICURE IS.5;6-4 I
i 60000 I
0 Years 1
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1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) l 1
l 3
TS.5.6-4 Spent Fuel Fool Checkerboard Region Burnup and Decay Time 3
Requirements - STD Fuel, No GAD i
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Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
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FICURE 7S.5.6 5 l
l-
-40000 l
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I l
50000 i
ACCEPTAB3 d
0 Years f
s rears
//s dv.ars N
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-l40000
///A it ug:
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1.0 2.0 3.0 4.0 5.0
. Initial U-235 Enrichment (w/o)
TS.5.6 5 Spent Fuel Fool Checkerboard Region Burnup and Decay Time Requiraments - 0FA Fuel. 4 CAD Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
FIGURE TS;5.6 6 l
60000 l
l t -,
l t
1 l
l e gy r,
/
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(
i 50000 2
Tm
/
s v ars I
f f, to voars E
f ffj 15 Years
~
g 20 Years
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NOT ACCEPTM y;
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0 l
4.0 5.0 l
1.0 2.0 3.0 Initial U-235 Enrichment (w/o) l l
l 75.5.6-6 spent Fuel Fool Checkerboard Region Burnup and Decay Time Requi'rements - STD Fuel, 4 CAD Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
]
FIGURE T5.5.6-7 4
{._ _.
50000 i
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45000 i
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2 0 Years-i
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2 t
4 coco 10 Years l
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20 Years
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10000 fa A r l
H 5000
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a l
1.0 2.0 3.0 4.0
'5.0 Initial U-235 Enrichment (w/o)
T5.5.6-7 Spent Fuel Fool Checkerboard Region Burnup and Deci.y Time Requirements - OFA Fuel, 8 CAD
\\
Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
~.. _. -. -.. _.... _ -. -.. - - - - -.. -.
FIGURE 7S.5.608 I
~50000 t
i e v ars e
I
/
45000 l
f s wear.
I e
/
/
10 Years l
i g
g f
f ;
/
/
/. 15 Years
/
2 20 Years 4mang
/
/
///
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/ / //
/
/ ///
' ////
i
/
/ ///
35000 f
.c f ff
/
/ ///
f f///
~
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/ ///
f
/
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30000 i
p f f fff
/
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H D
// ///
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/ / ///
t
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5990 l / / ///
\\
t/
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l
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m 20000 j/ //H
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ffff
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10000
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. r 5000
[
s J
1 0
1 1.0 2.0 3.0 4.0 5.0 i
Initial U-235 Enrichment (w/o) l T5.5.6-8 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 8 CAD i,
1 i
Amendment No. 129 Prairie Island Unit 1 Amendment No. 121 Prairie Island Unit 1
TICURE TS.5.6-9 l
45000 i
s o rurs l
40000
/
I
/ s 5 Years I
/
/,
gn y,,,,
/ / I' ACCEPTABLE 15 rears
/
/ / /' so rurs
~ 35000
/ / ///
i
/ / ///
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/ ////
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y
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gf I
10000
(
r I
p r
i i
i 5000
- /
f Jr 0
/
1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)
TS.5.6-9 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - OTA Fuel, 12 CAD
\\
4
\\
Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121 9
1 i
I FIGURE 7S.5.6010 e rears-45000 f
t --
4
/
l s years to Years i
40000 15 vaars i
t
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/ //
0Yws I
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I J
0
/
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1.0 2.0 3.0 4.0 5.0 j
Initial.U-235 Enrichment (w/o) i I
TS.5.6-10 spent Fuel Pool checkerboard Region Burnup and Decay Time 4,
Requirements - STD Fuel, 3 2 GAD 4
1 i
Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
TICURE TS.5.6-11 45000 I
I I
40000 o re.,a i
/
9 seats y,
/ /s to sear.
35000
-P i
j
/ fj 15 Years 30 tests
, pyy, y
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NOT ACCEPTABLE 10000 fg z
N 1
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/
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1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)
TS.5.6-11 Spent Fuel Fool Checkerboard Region Burnup 'nd. Decay Time a
j Requirements - 0FA Fuel, 16 or More CAD i
4 i
Amendment No. 129 Prairie Island Unit 1 Prairie Island Unit 2 Amendment No. 121
-i j
TZGURE TS.5.6-12 i
~
'45000 i
. re.,s i
/
l 40000
/
) s rurs
/ /
10 years j
f j 15 years
/ / // 20 years ACCEPTABLE
/
/ "/
35000
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2
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NOT ACCEPTABLE 10000 f,
/B F
J 5000
[
t i
I O
I 1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o)
TS.S.6-12 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 16 or More CAD J
Prairie Island Unit 1 Amendment No 129 Prairie Island Unit 2 Amendment No. 121 i
. - -.. _ - -. - ~.. -
j 3.3.8 2 3.8 REFUEL.ING AND FUEL MANDLING d
Raggi continued The Spent Fuel Fool Special Ventilation System (Reference 3) is a safeguards system which maintains a negative pressure in the spent fuel enclosure upon
. detection of high 4rea radiation.
rm _ -
The Spent Fuel Fool Normal Ventilation system is automatically isolated and exhaust air is drawn through filter modules containing a roughing filter, particulate filter, and a sharcoal filter before discharge to the environment via one of the Shield Sullding exhaust stacks.
Two completely redundant trains are provided. The exhaust i
fan and filter of each train are shared with the corresponding train of the containment In service, Purge System. Nigh efficiency particulate absolute (HEPA) filters are installed before the charcoal adsorbers to prevent clogging sf the iodine adsorbers in each STFSYS filter train.
4 The charcoal adsorbers i
are installed to reduce the potential release of radioiodine to the environment.
During movement of irradiated fuel assemblies or control rods, a water
{
1evel of 23 feet is maintained to provide sufficient shielding.
The water level may be lowered to the top of the RCCA drive shafts for i
latching and unistching. The water level may also be lowered below 20 feet for upper internals removal / replacement. The basis for these allowance (s) are (1) the refueling cavity pool has sufficient level to allow time to initiate repairs or emergency procedures to cool the core. (2) during 1stching/unistching and upper internals removal / replacement the level is closely monitored because the activity uses this level as a reference point.
l (3) the time spent at this level is minimal.
4 The Prairie Island spent fuel storage racks have been analyzed (Reference
- 8) in accordance with the methodology contained in Reference 5.
That j
methodology ensures that the spent fuel rack multiplication factor. K rr.
e is less than 0.'95 as recommended by ANSI 57.2-1983 (Reference 6) and NRC guidance (Reference 7). The codes, methods and. techniques contained in the methodology are'used to satisfy this criterion on X,cg. The resulting
~~,
Prairie Island spent fuel rack criticality analysis allows for the storage of fuel assemblies with enrichments up to a maximum of 5.0 weight percent U 235 while maintaining Kerr s 0.95 including uncertainties and credit for soluble boron. In addition, sub. criticality of the pool (K rr
< 1.0) is assured on a 95/95 basis, without the presence of the soluble e
boron in the pool. Credit is taken for radioactive decay time of the spent fuel and for the presence of fuel rods containing Cadolinium burnable poison.
The Prairie Island specific criticality analysis (Reference 8) utilized the following storage configurations to ensure that the spent fuel pool will remain suberitical during the, storage of fuel asssablies with all possible combinations of burnup and initial enrichment:
Prairie Island Unit 1 Amendment No. 30ff. H T. 129 Prairie Island Unit 2 Amendment No. J8f. 2d.121 e-
3.3.8-3 1
s 3.8 REWELINC AND FUEL MANDLYNC j
AgAss continued iJ
~"-~ 'I. -The first stbrage configuration utilizes a checkerboard loading
~
3
{
pattern to accommodate new or low burnup fuel with a maximum d
enrichment of 5.0 wtt U 235. This configuration stieres " burned" and
" fresh" fuel assemblies in a 3x3 checkerboard pattern as shown in' j
Tigure TS.5.6-1.
Fuel assemblies stored in
- burned" cell locations are selected based on a. combination of fuel assembly type, initial j
enrichment, discharge burnup and decay time (Figures TS.5.6-3 through i
75.5.6-12). The criteria for the fuel stored in the " burned" l
locations is also dependent on the number of rods containing Gadolinium in the center " fresh" fuel assembly. The use of empty cells is also an acceptable option for the " burned" cell locations.
{
This will allow the storage of new or low burnup fuel assemblies in j
the outer rows of the spent fuel storage racks because the area j
outside the racks can be considered to be empty cells.
i Fuel assemblies that fall into the restricted range of Figures l
TS.3.8-1 or 75.3.8 2 are required to be stored in " fresh" cell i
locations as shown in Figure TS.5.6-1.
The criteria included in j
Figures TS.3.81 and TS.3.8 2 for the selection of fuel assemblies to j
be stored in the " fresh" cell locations is based on a combination of fuel assembly type, initial enrichment, decay time and discharge i
burnup.
1 2.
The second storage configuration does not utilize any special loading pattern. Fuel assemblies with burnup, initial enrichment and decay
)
time which fall into the unrestricted range of Figures TS.3.91 or i
TS.3.8-2, as applicable, can be stored anywhere in the region with no special placement rostrictions.
l l
The burned / fresh fuel checkerboard region can be positioned anywhere within the spent fuel racks, but the boundary between the checkerboard
- T l
region and the unrestricted region must be either:
i 1.
separated by a vacant row of cells, or i
j 2.
the interface' must be configured such that there is one row carryover of the pattern of burned assemblies from the checkerboard region into the first roit of the unrestricted region (Figure TS.5.6-2).
I Specifications 3.8.E.1, 5.6.A.1.d and 5.6.A.1.s ensure that fuel is l
stored in the spent fuel racks in accordance with the storage configurations assumed in the Prairie Island spent fuel rack criticality 2
analysis (Reference 8).
3 The Prairie Island spent fuel pool ciriticality analysis addresses all the fuel typss currently stored in the spent fuel pool,and in use in the reactor. The fuel types considered in the analysis include the.
{
Westinghouse Standard (STD), OFA, and Vantage Plus designs, and the Exxon
{
fuel assembly types in storage in the Prairie Island spent fuel. pool.
l The CFA designation on the figures in Sections 3.8 and 5.6.A bound all of l
the Westin5 ouse OFA and vant' age Plus fuel assemblies at Prairie Island.
h
[
The STD designation on the figures in Sections 3.8 and 5.6.A bound all of the Westinghouse STD and Exxon fuel assemblies at Prairie Island.
I Prairie Island Unit 1 Amendment No. 1DEC 11 6 129 Prairie Island Unit 2 Amendment No. J9r, H2,121 1
i 3.8 REMELTNC AND WEL MANDUNC.
]
j 3agag continued i
j Most accident conditions in the spent fuel pool will not result in an j -
increase in Err of the racks in either of the two storage configurations.
_J Examples of those' accident conditions which will not result in an increase in Nrr are a fuel assembly drop on the top of, the racks, a fuel j
assembly drop between rack modules and wall (rack design precludes this condition), and a drop or placement of a fuel assembly into the cask j
loading area of the small, pool. Nowever, two accidents can be postulated
]
which could increase reactivity. The first postulated, accident would be j
a loss of the fuel pool cooling system and the second would be a misload of a fuel assembly into a cell for which the restrictions on location, i
enrichment, burnup, decay time or Gadolinium credit.are not satisfied.
2 For an occurrence of these postulated accident conditions, the double 4
contingency principle of ANSI /ANS-8.1-1983 can be applied. This states j
that one is not required to assume two unlikely, independent, concurrent 4
ovents to ensure protection against a criticality accident. Thus, for j
these postulated accident conditions, the presence of additional soluble boron in the spent fuel pool water (above the 750 ppa required to maintain Nrr less than 0.95 under r.ormal conditions) can be assumed as a 1
realistic initial condition since not assuming its presence would be a l
second unlikely event.
{
Calculations were performed (Reference E) to determine the amount of j
soluble boron required to offset the highest reactivity increase caused i
by either of these postulated accidents and to maintain Nrr less than or i
equal to 0.95.
It wae found that a spent fuel pool boron concentration j
of 1300 ppa was adequate to mitigate these postulated criticality related 1
accidents and to maintain her less than or equal to 0.95, specification
?
3.8.E.2 ensures the spent fuel pool contains adequate dissolved boron to compensate for the increased reactivity caused by a mispositioned fuel l.
assembly or a loss of spent fuel pool cooling. The 1800 ppa spent fuel pool boron concentration limit in Specification 3.8.E.2 was chosen to be 5
j consistent with the boron concentration limit required by Specification
{
i 3.8.B.,1.c for a spent' fuel cask containing fuel.
i l
Specification 5.6.A.1.c requires that the spent fuel rack Nig be less j
than or equal to 0.95 when flooded with water borated to 750 ppa.
A spent fual pool boron dilution analysis was performed which confirmed i
that sufficient time is available to detect and mitigate a dilution of j
the spent fuel pool before the 0.95 Ntr design basis is exceeded. The spent fuel pool boron dilution analysis concluded that an unplannad or inadvertent event which.could result in the dilution of the spent fuel j
pool boron concentration from 1800 ppa to 750 ppa is not a credible i
eve.nt.
a When the requirements of specification 3.8.E.1.a are not met, immediate j
action must be taken to move any non complying fuel assembly to an j
acceptable location to preserve the double contingency principle assumption of the criticality accident analysis.
4 i
4 Prairie Island Unit 1 Amendment No. K 129 i
Prairie Island Unit 2 Amendment No. p.
, 121 i-
.. = -
3.3.8 5
)
3.8 REFUELING AND FUEL MANDLING E
- - - :- Esses -continued
- - _. _,=
=.= -- = - -- - : : :---
Uhen the concentration of boron in the spent fuel pool is less than required by specification 3.8.E.2.a. inanediate 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 ir=ciately suspending the movement of fuel assemblies. The i
concentration of boron is restored simultaneously with suspending movement of fuel assamblies. The ' suspension of fuel movement is not intended to preclude movement of a fuel assembly to a safe position.
References l
1.
USAR, Section 10.2.1.2 l
2.
USAR, Section 14.5.1 3.
USAR, Section 10.3.7 4
4.
" Criticality Analysis of the Prairie Island Units 1 & 2 Fresh and Spent Fuel Racks", Wastinghouse Commercial Nuclear Fuel Division, February 1993.
5.
UCAP 14416-NP-A,
- Westinghouse spent Fuel Rack Criticality Analysis Nethodology", Revision 1. November 1996.
6.
American Nuclear Society "American National Star.dard Design i
Requirements for Light Water Reactor' Fuel Storage Facilities at l
Nuclear Power Plants" ANSI /ANS-57.2-1983, October 7,1983.
7.
Nuclear Regulatory Comission,1Atter to All Power Reactor Licensees
~
from 3. K. Crimes, '07 Position for Review and Acceptance of Spent Fuel Storage and Handling Applications", April 14, 1978.
8.
" Northern States Power Prairie Island Units 1 and. 2 Spent Fuel Rack' Criticality Analysis Using Soluble Boron Credit" Westinghouse comercial Nuclear Fuel Division, February 1997.
i Amendment M Prairie Island Unit 1 Amendment M, p) 1f, 129 Prairie Island Unit 2 2, 121 1
4 i
B.4.20-1 l
l i
i 4.20 Seent Fuel Pool Storere Confinuration
- 1.._ _ _ _ _ _
l This surveillance verifies that the fuel assemblies in the spent fuel l
storage racks are stored in accordance with the requirements of 4
Specifications 3.8.E.1, 5.6.A.1.d and 5.6.A.I.e.
4 e
The surveillance is required to be completed within 7 days after the completion of any fuel handling campaign which inolves the relocation of fuel assemblies within the spent fuel pool or the addition of fuel i
assemblies to the s' pent fuel pool. The extent of a fuel handling campaign 4
will be defined by plant administrative procedures. Examples of a fuel handling campaign would include all of the fuel handling performed during a l
refueling outage or associated with the placement of new fuel into the spent fuel pool.
It is not the intent of this surveillance to require the completion of-a spent fuel pool imentory verification during interruptions in fuel l
handling during a defined fuel handling campaign. No spent fuel pool l
imentory verification is required following fuel movements where no fuel-assemblies are relocated to different spent fuel rack locations.
The 7 day allowance for completion of this surveillance provides adequate 1
time for the completion of a spent fuel pool imentory verification while j
minimizing the time a fuel assembly may be misloaded in the spent fuel pool.
If a fuel assembly is misloaded durin5 a. fuel handling campaign, the minimum boron concentration required by Specification 3.8.E.2 will ensure j
1,that the spent fuel rack Kort remains within limits until the spent fuel pool i mencory verification is performed.
i 1
Prairie Island Unit 1 Prairie Island Unit 2 Amendment No. 129 Amendment No. 121
Sn ng r
t UNITED STATES f,
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. enmaa anni 49*****
,o NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.121 License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated July 28, 1995, as revised February 21, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I:
B.
The facility will operate in conformity with the application, the l
' 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:
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health rn, safety of the public; and a
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.
l 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
l l
l 1
~ -
l Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.121, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, with full implementation within 30 days.
i l
FOR THE NUCLEAR REGULATORY COMMISSION hv 0.
Beth A. Wetzel, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV l
Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical l
Specifications Date of Issuance: June 12, 1997 l
i l
4 l
j i
l e
l l
i ATTACHMENT TO LICENSE AMENDMENT NO. 121 FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NO. 50-306 Revise Appendix A Technical S)ecifications by removing the pages identified below and inserting the attacled pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT TS-vi TS-vi l
TS-xi TS-xi TS-xiii TS-xiii i
l TS.3.8-4 TS.3.8-4 TS.3.8-5 Figure TS.3.8-1 Figure TS.3.8-1 Figure TS.3.8-2 Tabl[TS.4.1-2B (Page 1 of 2)
Table TS.4.1-2B (Page 1 of 2)
Table TS.4.1-28 (Page 2 of 2)
Table TS.4.1-2B (Page 2 of 2) l TS.4.20-1
-TS.5.6-1 TS.S.6-1 TS.5.6-3 TS.S.6-3 Figure TS.5.6-1 Figure TS.S.6-1 Figure TS.5.6-2 Figure TS.S.6-2
)
Figure TS.5.6-3 Figure TS.5.6-4 Figure TS.5.6-5 Figure TS.5.6-6 Figure TS.5.6-7 Figure TS.5.6-8 Figure TS.5.6-9 Figure TS.5.6-10 Figure TS.5.6-11 Figure TS.5.6-12 B.3.8-2 B.3.8-2 B.3.8-3 B.3.8-3 B.3.8-4 B.3.8-4 B.3.8-5 3.4.20-1 I
1 l
F l
TS-vi i
j I
TABLE OF CONTENTS (Continued)
TS SECTION
'M PAGE 4.12 Steam Generator Tube Surveillance TS.4.12-1 A. Steam Generator Samp1-Selection and TS.4.12-1 Inspection B. Steam Generator Tube Sample Selection TS.4.12-1 and Inspection C. Inspection Frequencies TS.4.12-3 D. Acceptance criteria TS.4.12-4 E. Reports TS.4.12-5 4.13 Snubbers TS.4.13-1 4.14 Control Room Air Treatment System Tests TS.4.14-1
)
4.15 Spent Fuel Fool Special Ventilation System TS.4.15-1 l
4.16 Deleted 4.17 Deleted 4.18 Reactor Coolant Vent System Paths TS.4.18-1 A. Vent Path Operability TS.4.18-1
{
B. System Flow Testing TS.4.18-1 l
4.19 Auxiliary Building Crane 1.ifting Devices TS.4.19-1 4.20 Spent Fuel Pool Storage Configuration 75.4.20-1 l
l 1
i l
1 i
i Prairie Island Unit 1 Amendment No.,126,,3 E 129 Prairie Island Unit 2 Amendment No. J337Ji% 121 1
I
~ - _ _ - -..
TS-xi TABLE OF CONirNr5 (continued)
TS BASES SECTION M
PACE 4.0 3ASES FOR SURVEILLANCE REQUIREMENTS 4.1 Operational Safety Review B.4.1-1 4.2 Inservice Inspection and Testing of Pumps B.4.2-1 and Valves Requirements 4.3 Primary Coolant System Pressure Isolation B.4.3-1 Valves 4.4 Containment System Tests B.4.4-1 4.5 Engineered Safety Features B.4.5-1 4.6 Periodic Testing of Emergency Power Systems B.4.6-1 4.7 Main Steam Isolation Valves B.4.7-1 4.8 Steam and Power Conversion Systems B.4.8-1 4.9 neactivity Anomalies B.4.9-1 4.10 Del e ted 4.11 D(leted 4.12 Steam Generator Tube f,urveillance B.4.12-1 4.13 Snubbard B.4.13-1 4.14 Control Room Air "'rmatment System Tests B.4.14-1 4.15 Spent Fuel Fool Special Ventilation Systen B.4.15-1 4.16 Deleted 4.17 Deleted 4.18 Reactor Coolant Vent System Paths B.4.18-1 4.19 Auxiliary Building Crane 1.ifting Devices B.4.19-1 4.20 Spent Fuel Pool Storage Configuration B.4.20-1 i
Amendment No. M 4-22'~ 129 Prairie Island Unie ?
Prairie Island Unit 7 Amendment NO. JtT, J15~ 121
-.. -. - - ~. -. -... - -. -
. - - ~...
TS-xiii a
APPENDIX A TECHNICAL SPECIFICATIONS
~
. ~ - - - -.
LIST OF FICURES TS FIGURE TITLE 4
2.1-1 Reactor Cors Safety Limits 4
3.1-1 Unit 1 and Unit 2 Reactor Coolant System Heatup Limitations 3.1-2 Vnit 1 and Unit 2 Reactor Coolant System Cooldown Limitations 3.1-3 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >1.0 uCi/ gram DOSE EQUIVALENT I-131 l
3.8-1 Spent Fuel Fool Unrestricted Region Burnup and Decay Time Requirements - OFA Fuel 3.8-2 Spent Fuel Pool Unrestricted Region Burnup and Decay Time j
Requirements - STD Fuel 3.10-1 Required Shutdown Margin Vs Reac' tor Boron Concentration 4
4.4-1 Ehield Building Design In IAakage Rate 5.6-1 Spent Fuel Fool Burned / Fresh Checkerboard Cell Layout 5.6-2 Spent Fuel Fool Checkerboard Interface Requirements j
5.6-3 Spent Fuel Pool Checkerboard Region Burnup and Decay Time j
Requirements - CFA Fuel, No GAD i
5.6-4 Spent Fuel Fool Checkerboard Region Burnup and Decay Time j
Requirements.STD Fuel, No GAD
{
5.6-5 Spent Fuel Pool Checkerboard Region Burnup and Decay Time
=
l Requirements - 0FA Fuel -4 CAD 5.6-6 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 4 GAD 5.6-7 Spent Fuel Fool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 8 GAD i
5.6-8 Spent Fuel Fool Checkerboard Region Burnup and Decay Time l
Requirements - STD Fuel, 8 GAD
~
5.6-9 Spent Fuel Pool checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 12 GAD 5.6-10 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 12 GAD 5.6-11 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 16 or More GAD 5.6-12 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 16 or More CAD B.2.1-1 Origin of Safety Limit curvos at 2235 psig with delta-T Trips and Locus of Reactor Conditions at which SG Safety Valves Open Prairie Island Unit 1 Amendment No. g g 129 Prairie Island Unit 2 Amendment No. g.1.HC 121'
TS.3.8-4 3.8.C.
Small Seent Fuel Fool Restrictions No more than 45 recently discharged assemblies shall be located in the amall pool (pool No. 1).
b.
Feent Fusi Pool Special Ventilstion System 1.
Both trains of the Spent Fuel Pool Special Ventilation System shall be OPERABLE at all times (except as specified in 3.8.D.2 *and 3.8.D.3 below).
2.
With one train of the Spent Fuel Pool Special Ventilation System inoperable, fuel handling operations and crane operations with loads over spent fuel (inside the spent fuel pool enclosure) are permissible during the following 7 days, provided the redundant train is demonstrated OPERABLE prior to proceeding with those operations.
3.
With both trains of the Spent Fuel Pool Special Ventilation System inoperable, suspend all fuel handling operations and crane operations with loads over spent fuel (inside the spent fuel pool enclosure).
4.
' The provisions of specification 3.0.C are not applicable.
E.
Spent Fuel Pool Storare 1.
Fuel Assembly Storage The combination of initial enrichment, burnup and decay time of a.
each spent fuel assembly stored in the spent fuel pool shall be within.the unrestricted range of Figures TS.3.8-1 or TS.3.8-2, as applicable, or fuel assemblies shall be stored in accordance with Specification 5.6.A.1.e.
b.
If the requirements of 3.8.E.1.a are not met, immediately initiate action to move any noncomplying fuel assembly to an acceptable location.
The p'ovisions of Specification 3.0.C are not applicable.
l c.
r 2.
Spent Fuel Pool Boron Concentration a.
The spent fuel pool boron concentration shall be t 1,800 ppm when fuel assemblies are stored. in the spent fuel pool, b.
If the spent fuel pool boron concentration is not within limit, I
then immedi'ately:
- 1. Suspend movement of fuel assemblies in the spent fuel pool, and
- 2. Initiate action to restore spent fuel pool boron concentration to within limit.
The provisions of Specification 3.0.C are not applicable. '.JC87~129 c.
Amendment No. JMj)4d,121 Prairie Island Unit 1 Prairie Island Unit 2 Amendment No.-84 j
~
l 1
l l
l FIGURE T5.3.8-1 40000 I
1 8
o rur.
35000
/
f, s Yurs
/ /, 10 Years f//> }l }*g
~
.h
/ //#
30000
////f
~
/ ////
c LARESTRICTED
/////
g
/ //f/
~
/////
o,25000
/ /M r
a
//f//
/////
m*
.fM/
///#
A o0000
//H/
/f//
g
/Hf/
am
)f/f
/#
~ 15000 ifM
/2 7
=
a M
i h#
10000 A
J RE5ifoCi eu -
2
[
5000
/
J
/
0
/
1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) i FIGURE TS.3.8 1' Spent Fuel' Pool Unrestricted Region Burnup and Decay Time Requirements - 0FA Fuel Prairie Island Unit 1 Amendment No. Jeff,129, Prairie Island Unit 2 Amendment No. JOr; 121 p
g
+----s,
.w
I i
i FIGURE TS.3.8 2 40000 i
i
~- ~
i i
l
/
5 Years g
j 35000 l
/
/- 10 Years
]
/ / / 15 Years I
/ / //a 20 Years l
/ ) ///
i O
30000 k
/ / ///
/ ////
UNREiiifepi r.u j ////
)
/ f)//
1
/////
5000
/VH/
l c
/ ////
)
l
/VM to l
/H/)
>' 2 0 0 0 0 f/ff l
I b
///#
l
//ff l
E f///
i 4
/Hf l
15000 g
fgf y
/Hf k
//f l
/7
///
l 10000'
, 7f L
F 1
F RESTRICTED A V f
5000 g
I
\\
/
I O
i 1.0 2.0 3.0 4.0 5.0 l
' Initial U-235 Enrichment (w/o) l l
FIGURE TS.3.8-2 Spent Fuel Pool Unrestricted Region Burnup and Decay Time l
Requirements - STD Fuel Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121 w
m-
l l
Tcblo TS.4.1-25 (Pags 1 of 2) l TABLE TS.4.1-2B MINIMUM TREOUENCIES FOR SAMPLING TESTS TEST FREOUENCY 1.
RCS cross 5/ week Activity Determination 2.
RCS Isotopic Analysis for DOSE 1/14 days (when at power) l EQUIVALENT I-131 Concentration 3.
RCS Radiochemistry E determination 1./6 months (1) (when at power) l 4.
RCS Isotopic Analysis for Iodine-a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever Including I-131, I-133, and I-135 the specific activity ex-ceeds 1.0 uCi/ gram DOSE,,
EQUIVALENT I-131 or 100/E uCi/ gram (at or above cold shutdown), and b) One sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following THERMAL POWER' change exceeding 15 percent of the RATED THERMAL POWER within a one hour period (above hot shutdown) 5.
RCS Radiochemistry (2)
Monthly 6.
RCS Tritium Activity-Weekly 7.
RCS Chemistry (Cl*,F*, 02) 5/ Week 8.
RCS Boron Concentration *(3) 2/ Week (4) 9.
RWST Boron Concentration Weekly
- 10. Boric Acid Tanks Boron Concentration 2/ Week
- 11. Caustic Standpipe NaOH Concentration Monthly
- 12. Accumulator Boron concentration Monthly
- 13. Spent Fuel Pit Boron Concentration Weekly
- Required at all times.
i l
Prairie Island Unit 1 Amendment Nos.
, 129 Prairie Island Unit 2 Amendment Nos.
4, 121
Tchla TS.4.1-2B (Pegs 2 of 2)
TABLE TS.4.1-2B MINIMUM FREOUENCIES FOR SAMPLING TESTS i
TEST FREOUENCY l
- 14. Secondary Coolant Cross Weekly Beta-Gamma activity
- 15. Secondary Coolant Isotopic 1/6 months (5)
Analysis for DOSE EQUIVALENT l
I-131 concentration
- 16. Secondary Coolant chemistry pH 5/ week (6) pH Control Additive 5/ week (6)
Sodium 5/ week (6)
Notes
- 1.
Sample to be taken after a minimum of 2 EFPD and 20 days of POWER l
OPERATION have elapsed since reactor was last suberitical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
2.
To determine activity of corrosion products having a half-life greater than 30 minutes.
i 3.
During REFUELING, the boron concentration shall be. verified by chemical analysts daily.
4.
The maxisum interval between analyses shall mot 9xceed 5 days.
5.
If activity of the samples is greater than 10% of the limit.in Specification 3.4.D, the frequency shall be once per month.
6.
The maximum interval b'etween analyses shall not axceed 3 days.
l l
l Prairie Island Unit 1 Amendment No.
(l. 129 Prairie Island Unit 2 Amendment No.
104, 121
TS.4.20 1 i
l 4.20 Seent Fuel Pool Storare Confiruration Aeolicability This surveillance is applicable whenever fuel is stored in the spent fuel pool.
Obiective Te verify that fuel assemblies in the spent fuel pool are stored in accordance with the requirements of Specification 3.8.E.1.a.
l l
Specification l
l A spent fuel pool inventory verification shall be perfetised within 7 days of the completion of any fuel handling campaign which involves the relocation of fuel assemblies within the spent fuel pool or the addition of. fuel assemblies to the spent fuel pool.
1 l
l Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
..~ _ -
.~ - -
TS.5'.6-1 5.6 FUIL HANDLING A.
Criticality Consideration 1.
The spent fuel storage racks are designed (Reference 1) and shall be maintained with:
Fuel assemblies having a mawimum U-235 enrichment of 5.0 weight a.
I percent; b.
Nrr < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Reference 3; c.
bar s 0.95 if fully flooded with water borated to 750 ppa, which includes an allowance for uncertainties as described in Reference 3;
t l
d.
New or spent fuel assemblies with a combination of discharge l
burnup, initial enrichment and dec'ay time in the unrestricted range of Figures TS.3.8-1 or TS.3.8-2, as applicable, may be allowed unrestricted storage in the spent fuel racks; and New or spent fuel assemblies with a combination of discharge e.
i burnup, initial enrichment and decay time in the restricted range of Figures TS.3.8-1 or TS.3.8-2, as applicable, will be stored in 1
compliance with Figures TS.5.6-1 through TS.5.6 12.
l 2.
The new fuel storage racks are designed (Reference 1) and shall be maintained with:
Fuel asremblies having a maximum U-235 enrichment of 5.0 weight a.
percent; b.
Ntr s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Reference 2; and l
c. 'X.cr s 0.98 if' accidentally filled with a low density moderator which resulted in optimum low density. moderation conditions.
3.
Fuel will not'be' inserted into a spent fuel cask in the pool, unless a minimum boron concentration cif 1800 ppa is present. The 1800 ppa will ensure that k rt for the spent fuel cack, including statistical o
uncertiainties, will be less than or equal to 0.95 for all postulated arrangements of fuel within the cask. The criticality analysis for the TN 40 spent fuel storage cask was based on fresh fuel enriched to 3.85 weight percent U-235.
B.
Soent Fuel Storare Structure The spent fuel storage pool is enclosed with a reinforced concrete building having 12 to 18-inch thi.ek walls and roof *(Reference 1).
The pool and pool enclosure are Class I (reismic) structures that i
afford protection against loss of integrity from postulated tornado i
missiles. The storage compartments and the fuel transfer canal are l
connected by fuel transfer slots that can be closed off with I
pneumatically sealed gates. The bottoms of the slots are above the tops of the active fuel in the fuel assemblies which will be stored vertically in specially constructed racks.
d,129 Amendment No.%pf MW, Prairie Island Unit 1 Amendment No.
Prairie Island Unit 2
. =..._-
TS.5.6-3 D.
Soent Fuel Storare Canacity The spent fuel s'torage. facility is a two-compartment pool that, if completely filled with fuel storage racks, provides up to 1582 storage locations. The southeast corner of the small pool (pool no. 1) also serves as the cask lay down area. During times when the cask is being used, four racks are removed from the small pool. With the four i
storage racks in the southeast corner of pool 1 removed, a total of 1356 s crage locations are provided. To allow insertion of a spent fuel cask, total storage is limited to 1386 assemblies, not including those assemblies which can be returned to the reactor.
l l
l l
l i
l Reference l
1.
USAR, Section 10.2 2.
" Criticality Analysis of the Prairie Island Units 1 & 2 Fresh and Spent Fuel Racks", Westinghouse Commercial Nuclear Fuel Division, February 1993.
3.
" Northern States Power Prairie Island Uriits 1 and 2 Spent Fuel Rael Criticality Analysis Using' Soluble Boron. Credit", Westinghouse Commercial Nuclear Fuel Division, February 1997.
AmendmentNo.[KJol,g Prairie Island Unit 1 Amendment No.
121 Prairie Island Unit 2 i
TICURE TS.S.6-1 E
E E
1 E
E E
~
E E
E Fresh Fuel:
Must be less than or equal to nominal 4.95 w/o assU No restrictions on burnup Burned Fuel: Must satisfy minimum burnup requirements of Figures TS.5.6-3 through TS.5.6-12 depending 1
on number of CAD n>ds in fresh fuel FIGURE TS.5.6-1 Spent Fuel Pool Burned / Fresh Checkerboard Cell Layout i
Prairie Island Unit 1 Amendment No.
129 Prairie Island Unit 2 Amendment No.
, 121
.. _ ~..... = _ -. _ ~. _ -. -... -.. -. _...
I FIGURE TS.5.6-2 k
4 l
1 MMMMME l
MMMMME Interface i
EE l
E ME i
EM 8
l I
i l
&l$,$,$,$,:
Fresh Fuel:
Must be less than or equal to nominal 4.95 w/o ***U j
, ' ~ "
No restrictions on bumup i;
l Bumed Fuel:. 3x3 Checkertoard Region i
Must satisfy minimum bumup requirements of Figures TS.5.6-3 through TS.5.6-12 i
l Bumed Fuel:
All Cell Unrestricted Region l
A Must satisfy minimum bumup requirements 1
of Figures TS.3.81 or TS.3.8-2 i
i i
\\
i FIGURE TS.S.6-2 Spent Fuel Pool Checkerboard Interface Requirements 1
AmendmentNo.)K,'129
- Der, Prairie Island Unit 1 Amendment No.
121 i
Prairie Island Unit 2 n
1' i
FIGURE T5.5.6-3 1
1 s
i I.
55000 I
~ t e
0 Years 50000 l
s vars f
to Y urs 4
f
,/
/
I is vars
.f f;
45000 so rurs f,
f, 4
l ACCEPTABLE f j ff
^
f l
t
/
/ ///
6 e
/ / / //
40000
/
/ ///
i N
f f / //
.l
/
/ ///
}
l
/
/s'//
t
)
////
i o,35000
,,, f ff 6
/ / ///
y 6
/
/ Y//
g t
b4 f / ///
1 0
f
/ ///
m 30000
, fff, 6 >~ ////
e/
/J//
]
l f}
//f
/i / ///
i
$ 25000 f f f,7 i
to
/ ////
M
/ ////
i A
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)/Hfs i
a 20000 f,fy i
G
<//r f
/ ///f a
/ /H/
l f /N/
15000 fef,
s f/W j
'[
NOT ACCEPTABLE 10000 f7 i
w i
r i
5000 j
1 E
a I
\\
0 i
i 1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) 4 j
TS.5.6-3 Spent Fuel Pool checkerboard Region Burnup and Decay Time Requirements - OEA Fuel, No CAD e
1 1
Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121 4
4
_ =. -. =. - -. -........
l-FZGURE TS.5;6-4 60000 I
l 4
0 Years I
-/
/
j s rurs
/, /
I
/
/ /
50000 mim
/ / //
$r 2
I
/ / ///
^p E
/ / ///
/ / ///
l llN
~ 40000
/ ////
/ ////
E l ! ////
E
\\/ ////
N 30000
/ ////
8
/ ////
E
/ ////
////
\\
20000 w
//#/
M//
////
NOT ACCEPTABLE j
//K 10000 77 W
r i
O
[
1.0 2.0 3.0 4.0 s.0 Initial U-235 Enrichment (w/o)
TS.5.6-4 Spent Fuel Fool checkerboard Region Burnup and Decay Time Requirements - STD Fuel, No GAD i
i 4
Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121 i
FIGURE 7S.5.6-5 r
40000 j
l l
1 I
50000 ACCEPTABLE l
a 0 Years Pg l
/
j t vence 2 >j
~
s
> 10 Years g
2 !! NI'!
~ 40000
/V/#
Z l
///S B
1
/ /Y#
E
/////
I
> 30000
/Hf
/H//
E
/Hf
////
2 NN
- s 20000
////
u.
////
,lf
/#
NOT ACCEPTABLE 10000 f
/
/
0
/
~
1.0 2.0 3.0 4.0 s.O Initial U-235 Enrichment (w/o)
TS.S.6-5 Spent Fuel Pool Checkerboard Region Burnup and Decay Time l
Requirements - 0FA Fuel, 4 GAD Prairie Island Unit 1 Acendment.No. 129 Prairie Island Unit 2 Amendment No. 121
FIGURE TS;5.6 6 i
l 60000 i
I l
l 0 Years I
/
50000
/
s Years ACCEPTABLE l
j l
/ /,
10 Years l
a
/ /%
15 Years 20 Years Z
/ //X/
~40000 I
/ ////
9 l
/ /6'/
E l
/ //H 8
l
/ /4'/
s' 30000 1/////
/!N/
\\
l E
/ ////
./////
\\
t YMX
- s 20000
,/XO)7 t
w
//M
////
///[
NOT ACCEPTABLE Uf I
10000
~
gr l
f i
i i
I O
[
4.0 5.0 1.0 2.0 3.0 Initial U-235 Enrichment (w/o) l TS.5.6-6 Spent fuel Fool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 4 GAD 4
Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
FIGURE TS.5.6-7 l
50000 i
i i
i i
1 1
I I
j i
i l
l 45000 l
l I
i 2
0 Years' ACCEPTABLE f
5 y,,,,
40000 f
f 10 Years g
l 15 Years j
f 7j 20 Years 3
i t
/ ////
e
//
f//
g 35000 y f f rf E
~~~ T
/6 / ///
f I ///
~
/ / f//
O
/ / ///
\\
\\
l 30000
/ / <//
M
/ ////
D
/ ///)
G
/ //H
/ ////
' y 25000 g
f ffff
/////
//Hf
//f//
a I
/ /H/
g< 20000 inyf f/P/
/H//
g VHf N/A 15000 uff N//
/>W
~
NOT ACCEPTABLE
[
10000 fw J r g
5000
[
s I
s 0
/
1.0 2.0 3.0 4.?
~5. 0 Initial U-235 Enrichment (w/c)
TS.5.6-7 Spent Fuel Fool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 8 CAD Prairie Island Unit 1
. Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
FIGURE TS.5.6-8 i
l
'50000 i
i iI.
i 6
O Years ~"
f
/
45000 l
f s rears
/
/
f 3
a 10 Years
/
/ j l
i i I
/
/
/. 15 Years l
MNTM r >, /. 20 years guvu0 aaa
,,7 l
-)
/ ///
\\
/
/ / //
i // //
o 35000
,' /,',j' h
t
/
/ ///
~
\\
f
////
(
/
/s ///
g 5 30000 c
t
/ / ///
k 1
/ / /H D
l
// ///
O t
/ / ///
> 25000 I / //H M
Q S/ fM/
//HJ y
/;//f/
mm
//Hf
,,c 20000 j fyf
/ //M f //// n g
0
/HH f l
he
/ N//i i
15000 ffff NM i
MM t
l[#
l NOT ACCEPTABLE
[
f 10000 fff If f
. r l
J 5000
[
l 1
I O
I 1.0 2.0 3.0 4.0 5.0 l
Initial U-235 Enrichment'(w/o) l l
t T5.5.6-8 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 8 GAD Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 1 Amendment No. 121
FIGURE 75.5.6-9
(
45000 i
t l
o rears 40000
/
/ s 5 Years l
l
/
/,
gn y,,,,
15 Years ACCEPTABLE
/ I "' 2o Y.ars i
^ 35000
/ / ///
/ ////
i
/////
/ ///)
/ "//
I
~ 30000
/ ////
f///f g
/ ////
- sC f//M I
$ 25000 to
///H
/////
h
///H
.0
/////
$ 20000 f////
e a
/f/f A
/Hf/
N/K m
$ 15000 H/1 w
Nr/
i
\\
//K
[
NOT ACCEPTABLE f
10000 r,
y J
5000
. f v
i
/
0
/
1.0 2.0 3.0 4.0 5.0 '
Initial U-235 Enrichment (w/o) l 75.5.6-9 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - 0FA Fuel, 12 GAD Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
---1.
-4 vv
--ww--
FIGURE 2S.5.6-10 i
?
4 45000 j o rurs-l
/
/
s rurs i
j j
/ /
in rurs 40000
[
is rurs I//
20 years I
/
/ / //
/ / /ff k
mm
//
///
i
^ 35000 I
/
// //
j 2
/ / ///
k
/
/ ///
1 i
)
/ ///
/ ' /N J-30000 I
/////
2 I
/ / ///
g, i
// /N p
t
/ ////
i G
p 25000 1
/ ///)
1 to I
/ /N/
i 3
e I i / f//
a t/ f///
Q i
i a) 20000 f//f/
a a
/////
A
//N/
1 HHJ A
H i
0 15000
} ///( '
w
/)ff f/M NOT ACCEPTABLE ff 10000 eff H
~
D H
5000
[
f J
0
/
1.0 2.0 3.0 4.0 5.0 Initial.U-235 Enrichment (w/o) 1 TS.5.6-10 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - STD Fuel, 12 GAD Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
~
m-1
-,wy y
,,-,eg-m g--,
d
- l F2GURE TS.5.6-11 1
I 45000 i
i i
4 s
t j
40000 I
i O Years j
/
/ /
ACCEPTABLE
/ /s to rears I
^ 35000
/
15 Years i
,/
/,j 1
20 seata
/y7
/ ///f
/ ////
/ IM
_ 30000
/ f/f/
J
/ ////
o,
/ f///
D
//f//
/ /L'/
1 0 25000 i
/ ////
CD
/ fM j
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a
///H
} 20000
///F
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g e
m
,/,/,ff y
/)ff H
N
$ 15000 I
//M w
//M jff 1
//f NOT ACCEPTABLE g,
10000 A r i
H N
I f
5000 j
/
/
/
4 O
I 1.0 2.0 3.0 4.0 5.0 sl Initial.U-235 Enrichment (w/o) j 1
i TS.5.6-11 Spent Fuel Pool Chnckerboard Region Burnup 'and Decay Time Requirements - 0FA Fuel, 16 or More CAD i
l i
j Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121 a
-m.,
r
FIGURE TS.S.6-12 I
l 45000 i
i O Years 40000 s Yaars f
/ '
10 Years j
f j 15 Years
' / ##
ACCEPTABLE 20 Years
- "/
35000
/
/ //f
/
/ / f/
i
/ / ///
A
)
/ ///
]
G E 30000
/ > ///
/ ////
a
///N
- C
/ ///)
/"#
i
$ 25000
/ ////
i m
/ ////
1 0
h
//H/
i
//Hf i-20000
/ f/H f
a a
(/f//
4
/////
b
/)/U e*
I g 15000 LW
/M HM i
g[
NOT ACCEPTABLE i
}
10000 fg i
m r
4 j r 5000
[
f p
I l
I O
I l
1.0 2.0 3.0 4.0 5.0 Initial U-235 Enrichment (w/o) 4-j TS.5.6-12 Spent Fuel Pool Checkerboard Region Burnup and Decay Time j
Requirements - STD Fuel, 16 or More CAD e
Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
3.3.802 3.8 REFUELING AND PUEL HANDLING
{
1agag continued i
The Spent Fuel Pool Special Ventilation System (Reference 3) is a safeguards systes which maintains a negative pressure in the spent fuel enclosure upon i
- detection of high area radiation. The Spent Fuel Fool Normal Ventilation System is automatically isolated and exhaust air is drawn throu5h filter modules containing a roughing filter, particulate filter, and a charcoal filter before discharge to the environment via one of the Shield Building i
exhaust stacks.
Two completely radundant trains are provided. The exhaust
{
fan and filter of each train are shared with the sorresponding train of the j
containment In service. Purge System. High efficiency particulate absolute (MEPA) filters are installed before the charcoal adsorbers to prevent clogging v
}
of the iodine adsorbers in each 8FFSVS filter train. The charcoal adsorbers are installed to reduce the potential release of radiciodine to the environment.
During movement of irradiated fuel assemblies or control rods, a water level of 23 feet is maintained to provide sufficient shielding.
The water level may be lowered to the top of the RCCA drive shafts for 4
latching and unlatching. The water level may also be lowered below 20 feet for upper internals removal / replacement. The basis for these allowance (s) are (1) the refueling cavity pool has sufficient level to allow time to initiate i
repairs or emergency procedures to cool the core, (2) during latching /unistching and upper internals removal / replacement the level is closely monitored because the activity uses this level as a reference point, i
(3) the time spent at this level is minimal.
{
The Prairie Island spent fuel storage racks have been analyzed (Reference 1
- 8) in accordance with the methodology contained in Reference 5.
That methodology ensures that the spent fuel rack multiplication factor, K rr.
e is less than 0.'95 as recommended by ANSI 57.2-1983 (Reference 6) and NRC guidance (Reference 7). The codes, methods and. techniques contained in 4
j the methodology are'used to satisfy this criterion on K cc. The resulting 1
Prairie Island spent fuel rack. criticality analysis allows for the j
storage of fuel assemblies with enrichments up to a maximum of 5.0 weight j
percent U-235 while maintaining Kerr s 0.95 including uncertainties and credit for soluble boron. In addition, sub criticality of the pool (K rr j
e
< 1.0) is assured on a 95/95 basis, without the presence of the soluble boron in the pool. Credit is taken for radioactive decay time of the spent fuel and for the presence of fuel rods containing Cadolinium burnable poison.
The Prairie Island specific criticality analysis (Reference 8) utilized 3
the following storage configurations to ensure that the spent fuel pool will remain suberitical during the, storage of fuel assemblies with all possible combinations of burnup and initial enrichment:
k I
1 Prairie Island Unit 1 Amendment No. Jeff, JFf,129 Prairie Island Unit 2 Amendment No. JB1", Jd,121
--w-a
.-------v--
e-w w
y
3.3.803 3.8 REFUELING AND TUEL MANDLINC laaga centinued 7.
The first stbrage configuration utilizes 'a checkerboard loading
' ' - ~
1 pattern to accommodate new or low burnup fuel with a maximum enrichment of 5.0 wet U-235. This configuration stores " burned" and
" fresh" fuel assemblies in a 3x3 checkerboard pattern as shown in' Figure 75.5.6 1.
Fuel assemblies stored in ' burned" cell locations are selected based on a. combination of fuel assembly type, initial enrichment, discharge burnup and decay time (Figures TS.5.6-3 through TS.5.6-12). The criteria for the fuel stored in the ' burned" locations is also dependent on the number of rods containing Cadolinium in the center " fresh" fuel assembly. The use of empty calls is also an acceptable option for the " burned" cell locations.
This will allow the storage of new or low burnup fuel assemblies in the outer rows of the spent fuel storage racks because the area j
outside the racks can be considered to be empty cells.
l Fuel assemblies that fall into the restricted range of Figures
{
TS.3.8-1 or 75.3.8-2 are required to be stored in " fresh" cell j
locations as shown in Figure TS.5.6-1.
The criteria included in i
Figures TS.3.8-1 and TS.3.8-2 for the r, election of fuel assemblies to
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be stored in the " fresh" cell locations is based on a combination of j
fuel assembly type, initial enrichment, decay time and discharge l
burnup.
j 2.
The second storage configuration does not utilize any special loading pattern. Fuel assemblies with burnup, initial enrichment and decay l
time which fall into the unrestricted range of Figures TS.3.1-1 er j
TS.3.8-2, as applicable, can be stored anywhere in the region with no j
special placement restrictions.
I The burned / fresh fuel checkerboard region can be positioned anywhere within the spent fuel racks, but the boundary between the checkerboard
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region and the unrestricted region must be either:
1.
separated by a vacant row of cells, or 2.
the interface' must be configured such that there is one row carryover of the pattern of burned assemblies from the checkerboard region into j
the first row of the unrestricted region (Figure TS.5.6-2).
4 i
specifications 3.8.E.1, 5.6.A.1.d and 5.6.A.1.e ensure that fuel is j
stored in the spent fuel racks in accordance with the storage i
configurations assumed in the Prairie Island spent fuel rack criticality j
analysis (Reference 8).
4 The Prairie Island spent fuel pool criticality analysis addresses all the j
fuel types currently stored in the spent fuel pool,and in use in the i
reactor. The fuel types considered in the analysis include the.
i Westinghouse Scandard (STD), OFA, and Vantage Plus designs, and the Exxon i
fuel assembly types.in storage in the Prairie Island spent fuel. pool.
The OFA designation on the figures in Sections 3.8 and 5.6.A bound all of j
the Westin5 ouse OFA and Vant' age Plus fuel assemblies at Prairie Island.
h The STD designation on the figures in Sections 3.8 and 5.6.A bound all of
^
the. Westinghouse STD and Exxon fuel assemblies at Prairie Island.
Prairie Island Unit 1 Amendment No. JOC 1 6 129 Prairie Island Unit 2 Amendment No. JOi, W [, 121 I
3.8 REMELYNC AND TUEL MANDUNC
)
3333g continued Most accident conditions in the spent fuel pool will not result in an increase in her of the racks in either of the two storage configurations.
Examples of those accident conditions which will not result in an j
increase in Nig are a fuel assembly drop on the top of,the racks, a fuel i
assembly drop between rack modules and wall (rack design precludes this 3
j condition), and a drop or placement of a fuel assembly into the cask i
loading area of the small. pool. Novever, two accidents can be postulated i
j which could increase reactivity. The first postulated accident would be i
a loss ei the fuel pool cooling system and the second would be a misload of a fuel assembly into a cell for which the restrictions on location, enrichment, burnup, decay time or Gadolinium credit.are not satisfied.
For an occurrence of these postulated accident conditions, the double contingency principle of ANSI /ANS 8.1 1983 can be applied. This states 4
that one is not required to assume two unlikely, independent, concurrent 1
events to ensure protection against a criticality accident. Thus, for these postulated accident conditions, the presence of additional soluble i
boren in the spent fuel pool water (above the 750 ppm required to j
maintain Nrg less than 0.95 under normal conditions) can be assumed as a realistic initial condition since not assuming its presence would be a l
second unlikely event.
i Calculations were performed (Reference 8) to determine the amount of soluble boron requi :d to offset the highest reactivity increase caused by either of these postninted accidents and to maintain Nrr less than or equal to 0.95.
It was found that a spent fuel pool boron concentration i
of 1300 ppa was adequate to mitigate these postulated criticality related
{
accidents and to maintain Nrr less than or equal to 0.95.
Specification 3.8.E.2 ansures the spent fuel pool contains adaquate dissolved boron to i
i compensate for the increased reactivity caused by a mispositioned fuel assembly or a loss of spent fuel pool cooling. The 1800 ppa spent fuel
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pool boron concentration limit in Specification 3.8.E.2 was chosen to be i
consistent with the boron concentration limit required by Specification l
3.8.B.1.c for a spent fuel cask containing fuel, t
j-Specification 5.6.A.1.c requires that the spent fuel rack Nig be less i
than or equal to 0.95 when flooded with water borated to 750 ppa.
A j
spent fuel pool boron dilution analysis was performed which confirmed that sufficient time is available to detect and mitigate a dilution of i
the spent fuel pool before the 0.95 brr design basis is exceeded. The i
spent fuel pool boron dilution analysis concluded that an unplanned or 4
inadvertent event which.could result in the dilution of the spent fuel pool boron concentration from 1800 ppa to 750 ppa is not a credible event.
Uhen the requirements of Specification 3.8.E.1.a are not met, immediate action must be taken to move any non complying fuel assembly to an acceptable location to preserve the double contingency principle assumption of the criticality accident analysis.
Prairie Island Unit 1 Amendment No. J1 8',
129 Prairie Island Unit 2 AmendmentNo.1).k,
, 121
B.3.8-5 3.8 RETUELING AND FUEL MANDLING
_ _.- ---Agg31 tontinued -
When the concentration of boron in the spent fuel pool is less than required by Specification 3.8.E.2.a. immediate 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. The concentration of boron is restored simultaneously with suspending movement of fuel assemblies. The' suspension of fuel movement is not intended to preclude movement of a fuel assembly to a safe position.
References 1.
USAR, Section 10.2.1.2 l
2.
USAR, Section 14.5.1 3.
USAR, Section 10.3.7 4.
- Criticality Analysis of the Prairie Island Units 1 & 2 Fresh and Spent Fuel Racks" Westinghouse Commercial Nuclear Fuel Division, j
February 1993.
l 5.
WCAP-14416-NP-A, ' Westinghouse Spent Fuel Rack Criticality Analysis i
Methodology", Revision 1, November 1996.
6.
American Nu m *ociety. "American National Standard Design Requiremente L.
d ght Water Reactor' Fuel Storage Facilities at Nuclear Power E nts" ANSI /ANS-57.2-1983, October 7,1983.
7.
Nuclear Regulatory Commission,14tter to All Power Reactor 1.icensees from B. K. Crimes, "OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications", April 14, 1978.
8.
" Northern States Power Prairie Island Units 1 and. 2 Spent Fuel Rack' Criticality Analysis Using Soluble Boron Credit", Westinghouse Commercial Nuclear Fuel Division, February 1997.
Amendment M Prairie Island Unit 1 Amendment M.))FT, 129 Prairie Island Unit 2 M, 121
_ _ _. _ -. _. _. _. _ _ _. _ - _ =. _ - _ _ _..
l B.4.20-1 1
{
4.20 Soent Fuel Pool Storare Confiruration i
i
}
This surveillance verifies that the fuel assemblies in the spent fuel storage racks are stored in accordance with the requirements of Specifications 3.8.E.1, 5.6.A.1.d and 5.6.A.I.e.
The surveillance is required to be completed within 7 days after the completion of any fuel handling campaign which involves the relocation of
}
fuel assemblies wi, thin the spent fuel pool or the addition of fuel assemblies to the spent fuel pool. The extent of a fuel handling campaign will be defined by plant administrative procedures. Examples of a fuel handling campaign would include all of the fuel handling performed during a i
refueling outage or associated with the placement of new fuel into the spent fuel pool.
j It is not the intent of this surveillance to require the completion of a j
spent fuel pool inventory verification during interruptions in fuel i
handling during a defined fuel handling campaign. No spent fuel pool inventory verification is required following fuel movements where no fuel assemblies are relocatad to different spent fuel rack locations.
The 7 day allowance for completion of this surveillance provides adequate 1
- }
time for the completion of a spent fuel pool inventory verification while minimizing the time a fuel assembly may be misloaded in the spent fuel pool.
If a fuel assembly is misloaded during a fuel handling campaign, the j
minimum boron concentration required by Specification 3.8.E.2 will ensure i
that the spent fuel rack Kort remains within limits until the spent fuel pool inventory verification is performed.
1 t
i i
I Prairie Island Unit 1 Amendment No. 129 Prairie Island Unit 2 Amendment No. 121
'