B18731, Technical Specifications Change Request 2-10-01, Revision 1, Fuel Pool Requirements
| ML022330029 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/06/2002 |
| From: | Price J Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| B18731 | |
| Download: ML022330029 (13) | |
Text
Dominion Nuclear Connecticut, Inc.
Dominion M',illkt~mcl P rovrStation Ropc IFcrry Road
\\Vatcrtordf, CTV 0638ý AUG 62002 Docket No. 50-336 B18731 Re: 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Power Station, Unit No. 2 Technical Specifications Change Request (TSCR) 2-10-01, Revision 1 Fuel Pool Requirements In a letter dated November 6, 2001,(1) Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request in the form of changes to the Millstone Unit No. 2 Technical Specifications.
The proposed changes would: (1) increase the allowable nominal average fuel assembly enrichment from 4.5 w/o U-235 to 4.85 w/o U-235 for all regions of the spent fuel pool, the new fuel storage racks (dry), and the reactor core; (2) allow fuel to be located in 40 Region B Storage Cells, which are currently empty and blocked, and (3) credit spent fuel pool soluble boron for reactivity control during normal conditions to maintain spent fuel pool Keff 0.95. Additionally, as a result of a subsequent discussion with the staff of the Nuclear Regulatory Commission (NRC), DNC provided a revision to the Significant Hazards Consideration (SHC) discussion (Attachment 1) in a letter dated December 27, 2001.(2) The revised SHC discussion did not affect the conclusion of the safety summary nor the original SHC determination. Additionally, in a letter dated July 15, 2002,(3) DNC responded to a Request for Additional Information (RAI) from the NRC related to the aforementioned (1)
J. A. Price letter to the U.S. NRC, "Millstone Power Station, Unit No. 2, Technical Specifications Change Request (TSCR) 2-10-01, Fuel Pool Requirements," dated November 6, 2001.
(2)
J. A. Price letter to the U.S. NRC, "Millstone Power Station, Unit No. 2, Technical Specifications Change Request (TSCR) 2-10-01, Fuel Pool Requirements, Revised Significant Hazards Consideration Discussion," dated December 27, 2001.
(3)
J. A. Price letter to the U.S. NRC, "Millstone Power Station, Unit No. 2, Response to a Request for Additional Information Technical Specifications Change Request (TSCR) 2 10-01, Fuel Pool Requirements," dated July 15, 2002
U.S. Nuclear Regulatory Commission B18731/Page 2 license amendment request. The additional information provided did not affect the conclusions of the Safety Summary nor SHC discussion in the DNC November 6, 2001 and December 27, 2001 letters.
This letter provides a revision to the aforementioned license amendment request.
Proposed Design Features TS 5.6.1 is revised by this letter. Attachments 1 and 2 provide marked-up and retyped versions of Proposed Design Features TS 5.6.1, as previously submitted in the DNC November 6, 2001 letter.
Only proposed Design Features TS 5.6.1 is shown in Attachments 1 and 2, since all other proposed Technical Specification changes previously submitted by DNC in the November 6, 2001 letter remain unchanged by this letter. Attachments 3 and 4 provide marked-up and retyped versions of Proposed Design Features TS 5.6.1, as proposed by this letter. Thus by comparing Attachment 1 to Attachment 3, or comparing Attachment 2 to Attachment 4, the NRC can more easily see the changes proposed by DNC in this letter, relative to the DNC November 6, 2001 letter.
As shown in Attachment 1, the next to last sentence in proposed Design Features Technical Specification 5.6.1f) is: "Fuel having a maximum nominal enrichment of 4.85 weight percent U-235, with no burnup may be stored in un-blocked locations."
As shown in Attachment 3, the next to last sentence in proposed Design Features Technical Specification 5.6.1f) is: "Fuel having a maximum nominal enrichment of 4.85 weight percent U-235, may be stored in un-blocked locations." Thus, the only revision that DNC is proposing in this letter, involves the removal of the words "with no burnup" in proposed Design Features Technical Specification 5.6.1f).
The purpose of this sentence in proposed Design Features Technical Specification 5.6.1f) is to state what fuel may be stored in Region B un-blocked locations.
The criticality analyses previously submitted by DNC in the November 6, 2001 letter are based on storing maximum reactivity fuel in the Region B un-blocked locations. The maximum reactivity fuel analyzed were 4.85 weight percent U-235 fuel assemblies, with no burnup. A fuel assembly which has any amount of burnup will be less reactive and therefore less limiting than a fuel assembly with no burnup. Thus the criticality analyses previously submitted in the DNC November 6, 2001 letter bound the storage of fresh or burned fuel having a maximum nominal enrichment of 4.85 weight percent U-235, in un blocked locations of Region B.
DNC has determined that these words "with no burnup" previously submitted in Proposed Design Features TS 5.6.1f) could be misinterpreted, and should be removed.
The words "with no burnup" were originally inserted by DNC to add emphasis that fuel up to 4.85 w/o U-235 "with no burnup" could be placed in un-blocked storage cells of Region B. However, these words could be misinterpreted to read that only fuel "with no burnup" can be placed in the un-blocked cells of Region B, which is an unintended interpretation.
U.S. Nuclear Regulatory Commission B18731/Page 3 The removal of these 3 words does not change the intent of the proposed specification, nor alter any analysis that supports it. The revised Technical Specification provided in this letter will not affect the conclusions of the Safety Summary and SHC discussion in the DNC November 6, 2001 and December 27, 2001 letters.
There are no regulatory commitments contained within this letter.
If you should have any questions on the above, please contact Mr. Ravi Joshi at (860) 440-2080.
Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.
Site VcePresident - Millstone Sworn to and subscribed before me this da f
l~-o jý 2002 Notary'Public/
My Commission expires WM. E. BROWN NOTARY PUBLIC MYCOMISSION EXPIRES MAR. 31. M Attachments (4) cc:
H. J. Miller, Region I Administrator R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 NRC Senior Resident Inspector, Millstone Unit No. 2 Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Docket No. 50-336 B18731 Millstone Power Station, Unit No. 2 Technical Specifications Change Request (TSCR) 2-10-01 Revision 0 Proposed Design Features TS 5.6.1 Fuel Pool Requirements Marked-Up Pages
May 26, 1998 DESIGN FEATURES Voiuri 5-4.-
ihe total water and steam volume of the reactor coolant system is a
nominal 10,981 ft.
5.5 [K[RG[NCY CORE COOLING SYSIEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the design provisions contained in Section 6.3 of the FSARI with allowance for normal degradation pursuant to the applicable Surveillance Requirements 5.6. FU[
STORAGEW CRITICALITY 6
a) the new fuel (dry) storage racks are designed and shall maintained with sufficient center to center distance between assemblie/to atnsoensure a
< _95-the maximum nominal fuel enrichment to be storat in these racks ist4.50 weight percent of U-235sae b)
Region A of the spent fuel storage pool is designed nd shall be maintained with a nominal 9.8 inch center to center distance between storage locations to ensure a Kt, <.95 with the storage pool filled with unborated water.
Fuel assemblies stored in this region must comply ih Figure 3.9o ensure that the design burnup has been sustained.m sio c)
Region B of the spent fuel storage po is designed and shall be maintained with a nominal 998 inch center-tone distance between storage locations to ensure K,,,
.95 with a
storageppoolfilled with unborated water.
fuel assemblies stored in this re ion mu have a maximumr nominal enrichment of 4.5 weight percent U-23br5-tored in this region are placed in a 3 out of 4 STORAGE PAITN for reactivity control..
d) Region C of the spent el storage pool is designed od shape maintained with a 9.0 inch cent t
etrdsacebtensoaelcations to ensure a Ko ns o 9d with e suorage a
filld with unboratednwaters fuel assemb fblu es stored in his region must comply withor 3.9-lb to ens U
2 b
-u Amendmntano. Additionally, fuel assemblies utili gFgr breur htbrtd st~ainless steel poison pins are in Ie ntefe sebyscne ud ueadi w
diagonally uppsegud tue-Tepio pisaesld08 inh
.D borated stai]ssel ihabrncneto egtpretbrn e)/Region C of the spent fuel storage pool is designed to permit ri re 3-9-3.
MILLSIO NE
-UNIT 7
5-5 Amendment No.
JOYF ll,I 7,215
I MLK NO. Z-lIU-UI Unit 2 Technical Specification Changes Insert C Change 5.6 FUEL STORAGE Page 5-5 to read...
CRITICALITY 5.6.1 a)
The new fuel (dry) storage racks are designed and shall be maintained with sufficient center to center distance between assemblies to ensure a kff-<.95. The maximum nominal average fuel assembly enrichment to be stored in these racks is 4.85 weight percent
-m The maximum fuel rod enrichment to be stored in these racks is 5.0 weight percent LI-,.3--.
b)
The spent fuel storage racks are designe~dand shall be Mal with fuel assemblies having a maximum nominal average enrichment of 4.85 weight percen U,, 5. The maximum fuel rod enrichment to be stored in these racks is 5.0 weight percent U,. 5.
c)
The spent fuel storage racks are designed and shall be maintained with kff -< 1.00 if fully flooded with unborated water, which includes an allowance for uncertainties.
d)
The spent fuel storage racks are designed and shall be maintained with kff <.95 if fully flooded with water borated to 600 ppm, which includes an allowance for uncertainties.
e)
Region A of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations. Fuel assemblies stored in this region must comply with Figure 3.9-4 to ensure that the design bumup has been sustained.
f)
Region B of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations. Region B contains both blocked and un-blocked storage locations, shown in Figure 3.9-2. Fuel having a maximum nominal enrichment of 4.85 weight percent 14yr5, with no burnup may be stored in un-blocked locations. Fuel stored in blocked lotIons must be Batch B fuel assemblies.
I V-z3S, g)
Region C of the spent fuel storage pool is designed and shall be maintained with a 9.0 inch center to center distance between storage locations. Fuel assemblies stored in this region must comply with Figures 3.9-l a or 3.9-1b to ensure that the design bum-up has been sustained. Additionally, fuel assemblies utilizing Figure 3.9-l b require that borated stainless steel poison pins are installed in the fuel assembly's center guide tube and in two diagonally opposite guide tubes. The poison pins are solid 0.87 inch O.D. borated stainless steel, with a boron content of 2 weight percent boron.
h)
Region C of the spent fuel storage pool is designed to permit storage of consolidated fuel. The contents of the consolidated fuel storage boxes to be stored in this region must comply with Figure 3.9-3 to ensure that the design burnup has been sustained.
Docket No. 50-336 B18731 Millstone Power Station, Unit No. 2 Technical Specifications Change Request (TSCR) 2-10-01 Revision 0 Proposed Design Features TS 5.6.1 Fuel Pool Requirements Retyped Pages
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is a
nominal 10,981 ft 3.
5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY 5.6.1 a)
The new fuel (dry) storage racks are designed and shall be maintained with sufficient center to center distance between assemblies to ensure a keff <.95.
The maximum nominal average fuel assembly enrichment to be stored in these racks is 4.85 weight percent U-235.
The maximum fuel rod enrichment to be stored in these racks is 5.0 weight percent U-235.
b)
The spent fuel storage racks are designed and shall be maintained with fuel assemblies having a maximum nominal average enrichment of 4.85 weight percent U-235.
The maximum fuel rod enrichment to be stored in these racks is 5.0 weight percent U-235.
c)
The spent fuel storage racks are designed and shall be maintained with Kef <
1.00 if fully flooded with unborated water, which includes an allowance for uncertainties.
d) The spent fuel storage racks are designed and shall be maintained with Keff <.95 if fully flooded with water borated to 600 ppm, which includes an allowance for uncertainties.
e)
Region A of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations.
Fuel assemblies stored in this region must comply with Figure 3.9-4 to ensure that the design burnup has been sustained.
f)
Region B of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations.
Region B contains both blocked and un-blocked storage locations, shown in Figure 3.9-2.
Fuel having a maximum nominal enrichment of 4.85 weight percent U-235, with no burnup may be stored in un-blocked locations.
Fuel stored in blocked locations must be Batch B fuel assemblies.
g)
Region C of the spent fuel storage pool is designed and shall be maintained with a 9.0 inch center to center distance between storage locations.
Fuel assemblies stored in this region must comply with Figures 3.9-1a or 3.9-lb to ensure that the design burn-up has been sustained.
Additionally, fuel assemblies utilizing Figure 3.9-lb require that borated stainless steel poison pins are installed in the fuel assembly's center guide tube and in two diagonally opposite guide tubes.
The poison pins are solid 0.87 inch O.D.
borated stainless steel, with a boron content of 2 weight percent boron.
h)
Region C of the spent fuel storage pool is designed to permit storage of consolidated fuel.
The contents of the consolidated fuel storage boxes to be stored in this region must comply with Figure 3.9-3 to ensure that the design burnup has been sustained.
MILLSTONE - UNIT 2 5-5 Amendment No.
9, $, jy, 0745 77, J0, 00, 177, 797, WX,
Docket No. 50-336 B18731 Millstone Power Station, Unit No. 2 Technical Specifications Change Request (TSCR) 2-10-01 Revision 1 Proposed Design Features TS 5.6.1 Fuel Pool Requirements Marked-Up Pages
May 26, 1998 DESIGN FEATURES VOLUME 5 -. 2 4
he total water and steam volume of the reactor coolant system is a
nominal 10,981 ft 3.
5.5 EMERGENCY CORE COOLING SYSIE14S 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the design provisions contained in Section 6.3 of the FSARI with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.6. FUEL SIORAGE W
CRITICALITY CS. 6. 1 a) lhe new fuel (dry) storage racks are designed and shall maintained with sufficient center to center distance between assemblie /to ensure a
k,,, <.95.
The maximum nominal fuel enrichment to be storo in these racks is 4.50 weight percent of U-235.
b)
Region A of the spent fuel storage pool is designed nd shall be maintained with a nominal 9.8 inch center to center distance tween storage locations to ensure a K,11 <.95 with the storage pool fill with unborated water.
Fuel assemblies stored in this region must comply ith figure 3.9-4 to ensure that the design burnup has been sustained.
c)
Region B of the spent fuel storage po is designed and shall be maintained with a nominal 9.8 inch center-to-c er distance between storage locations to ensure K,,,
.95 with a
stor e pool filled with unborated water.
fuel assemblies stored in this r
ion may have a
maximum nominal enrichment of 4.5 weight percent U-235.
el assemblies stored in this region are placed in a 3 out of 4 STORAGE PAll N for reactivity control.
d) Region C of the spent el storage pool is designed and shall be maintained with a 9.0 inch cent to center distance between storage locations to ensure a
K,,,
.95 with e storage pool filled with unborated water.
Fuel assemblies stored in his region must comply with Figures 3.9-la or 3.9-lb to ensure that t design burn-up has been sustained.
Additionally, fuel assemblies utili ng figure 3.9-lb require that borated stainless steel poison pins are in led in the fuel assembly's center guide tube and in two diagonally oppos e guide tubes.
The poison pins are solid 0.87 inch O.D.
borated stainl s steel, with a boron content of 2 weight percent boron.
e)
Region C of the spent fuel storage pool is designed to permit storage of consolidated fuel and ensure a K,,
0.95.
The contents of cons idated fuel storage boxes to be stored in this region must comply with Vo re 3.9-3_
MILLSIO1[E UNII 2 5-5 Amendment No.
F.
I*,
117.
- 9, J,
- j77, w-7, 215
1 3%-, A JINt-L-IV-VI Unit 2 Technical Specification Changes Insert C Change 5.6 FUEL STORAGE Page 5-5 to read...
CRITICALITY 5.6.1 a)
The new fuel (dry) storage racks are designed and shall be maintained with sufficient center to center distance between assemblies to ensure a krf- *.95. The maximum nominal average fuel assembly enrichment to be stored in these racks is 4.85 weight percent U73,3The maximum fuel rod enrichment to be stored in these racks is 5.0 weight percent 1
.2-3....
t-2-?-% r, b)
The spent fuel storage racks are designed and shall be mai with fuel assemblies having a maximum nominal average enrichment of 4.85 weight percen t4,,. The maximum fuel rod enrichment to be stored in these racks is 5.0 weight percent l-z-y.
c)
The spent fuel storage racks are designed and shall be maintained with kfr < 1.00 if fully flooded with unborated water, which includes an allowance for uncertainties.
d)
The spent fuel storage tacks are designed and shall be maintained with klt -<.95 if fully flooded with water borated to 600 ppm, which includes an allowance for uncertainties.
e)
Region A of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations. Fuel assemblies stored in this region must comply with Figure 3.9-4 to ensure that the design bumup has been sustained.
f)
Region B of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations. Region B contains both blocked and un-blocked storage locations, shown in Figure 3.9-2. Fuel having a maximum nominal enrichment of 4.85 weight percent wk4"s, wi4h-
- may be stored in un-blocked locations. Fuel stored in blocked locations must be Batch B fuel assemblies.
k._ 7-S, g)
Region C of the spent fuel storage pool is designed and shall be maintained with a 9.0 inch center to center distance between storage locations. Fuel assemblies stored in this region must comply with Figures 3.9-l a or 3.9-lb to ensure that the design bum-up has been sustained. Additionally, fuel assemblies utilizing Figure 3.9-lb require that borated stainless steel poison pins are installed in the fuel assembly's center guide tube and in two diagonally opposite guide tubes. The poison pins are solid 0.87 inch O.D. borated stainless steel, with a boron content of 2 weight percent boron.
h)
Region C of the spent fuel storage pool is designed to permit storage of consolidated fuel. The contents of the consolidated fuel storage boxes to be stored in this region must comply with Figure 3.9-3 to ensure that the design bumup has been sustained.
Docket No. 50-336 B18731 Millstone Power Station, Unit No. 2 Technical Specifications Change Request (TSCR) 2-10-01 Revision 1 Proposed Design Features TS 5.6.1 Fuel Pool Requirements Retyped Pages
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is a nominal 10,981 ft 3.
5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY 5.6.1 a)
The new fuel (dry) storage racks are designed and shall be maintained with sufficient center to center distance between assemblies to ensure a
keff <.95.
The maximum nominal average fuel assembly enrichment to be stored in these racks is 4.85 weight percent U-235.
The maximum fuel rod enrichment to be stored in these racks is 5.0 weight percent U-235.
b)
The spent fuel storage racks are designed and shall be maintained with fuel assemblies having a maximum nominal average enrichment of 4.85 weight percent U-235.
The maximum fuel rod enrichment to be stored in these racks is 5.0 weight percent U-235.
c)
The spent fuel storage racks are designed and shall be maintained with Keff
< 1.00 if fully flooded with unborated water, which includes an allowance for uncertainties.
d) The spent fuel storage racks are designed and shall be maintained with Keff
.95 if fully flooded with water borated to 600 ppm, which includes an allowance for uncertainties.
e)
Region A of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations.
Fuel assemblies stored in this region must comply with Figure 3.9-4 to ensure that the design burnup has been sustained.
f)
Region B of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations.
Region B contains both blocked and un-blocked storage locations, shown in Figure 3.9-2.
Fuel having a maximum nominal enrichment of 4.85 weight percent U-235, may be stored in un-blocked locations.
Fuel stored in blocked locations must be Batch B fuel assemblies.
g)
Region C of the spent fuel storage pool is designed and shall be maintained with a 9.0 inch center to center distance between storage locations.
Fuel assemblies stored in this region must comply with Figures 3.9-1a or 3.9-lb to ensure that the design burn-up has been sustained.
Additionally, fuel assemblies utilizing Figure 3.9-1b require that borated stainless steel poison pins are installed in the fuel assembly's center guide tube and in two diagonally opposite guide tubes.
The poison pins are solid 0.87 inch O.D.
borated stainless steel, with a boron content of 2 weight percent boron.
h)
Region C of the spent fuel storage pool is designed to permit storage of consolidated fuel.
The contents of the consolidated fuel storage boxes to be stored in this region must comply with Figure 3.9-3 to ensure that the design burnup has been sustained.
MILLSTONE - UNIT 2 5-5 Amendment No. 7, g, ;PP, 0745 117',I*
- ll7, 707, 779,