RA-09-081, Independent Spent Fuel Storage Installation Annual Report for November 2008 Through October 2009

Independent Spent Fuel Storage Installation Annual Report for November 2008 Through October 2009

ML093410382
Person / Time
Site:	Oyster Creek
Issue date:	11/19/2009
From:	Massaro M Exelon Nuclear
To:	Parker J Lacey Township, NJ, Office of Nuclear Material Safety and Safeguards
References
RA-09-081
Download: ML093410382 (7)

Text

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Oyster Creek Generating Station wVWMV.exeIUI '-UI p.I.-TJI I IN UL.LI Cd.I Route 9 South PO Box 388 Forked River, NJ 08731 November 19, 2009 RA-09-081 The Honorable John C. Parker Mayor, Lacey Township 818 West Lacey Road Forked River, NJ 08731

Subject:

Oyster Creek Nuclear Generating Station Independent Spent Fuel Storage Installation Annual Report

Reference:

Building Permit; Appeal 93-40 (after remand)

The above referenced Building Permit requires the Oyster Creek Generating Station to submit routine monitoring reports to Lacey Township on an annual basis. Enclosed is the Temperature Monitoring and Radiation Survey data as required by Condition 10 of the Building Permit, and the number of spent fuel assemblies in dry storage as required by Condition 11 of the Building Permit.

The status of Federal Government's plans to site a permanent spent fuel repository is also provided, as required by Condition 17 of the Building Permit. This fulfills the reporting requirements for the year 2009 (November 2008 through October 2009).

If any further information or assistance is needed, please contact Richard Milos at 609-971-4973.

Sincerely, Michael J. Massaro Vice President, Oyster Creek Nuclear Generating Station Enclosure cc: USNRC Document Control Desk; Docket 72-15 Administrator, USNRC Region I USNRC Senior Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek File No. 09006

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Enclosure Independent Spent Fuel Storage Installation (ISFSI) Building Permit Condition Ten:

"The applicant shall provide to the township on a yearly basis, written records revealing all temperature and radiation measurements. The applicant shall further advise of any and all repairs made to the concrete modules."

Oyster Creek Generating Station Reply to Condition Ten:

The temperatures of the loaded, concrete, Horizontal Storage Modules (HSMs) are monitored daily and are part of the station's surveillance records. The temperatures of the loaded HSMs can be up to 30 degrees higher than the unloaded HSMs depending on the heat load of the spent fuel loaded.

During the summer months, the highest concrete HSM temperatures were less than 120 degrees.

This is well within the design limits of the HSMs and represents an actual heat loading of about 7.5 KW.

The attached temperature graphs represent average monthly temperature data for the period from October 2008 through September 2009, for the HSMs we loaded in 2002 (# 1-4), the HSMs we loaded in 2003 (# 5-8), the HSMs we loaded in 2004 (# 9-11), and the HSMs we loaded in 2005 (#

12-16). HSMs #17-20 remain empty and are at ambient temperatures.

The highest radiation measurements on the vertical face of the HSMs were 0.8 mr/hr gamma and

<0.1 mr/hr neutron. The highest gamma dose rate at the opening between the HSMs (bird screens) was 3.6 mrem/hr. These readings are well within the design limits of the HSMs. The roof of the HSMs is a posted radiation area and is not readily accessible. The highest radiation levels at the ISFSI security fence facing Route 9 was <0.2 mr/hr gamma and <0.1 mr/hr neutron.

Radiation survey data sheets are included following the temperature graphs.

Two HSMs (#19-20), were installed in October 2008. We plan to load the remaining four spent fuel canisters into HSMs #17-20 during 2010. This will complete the existing Independent Spent Fuel Storage Installation reviewed under the Building Permit, Appeal 93-40 (after remand).

There were no repairs to the concrete modules since the last report.

Independent Spent Fuel Storage Installation Buildinq Permit Condition Eleven:

"The applicant shall provide to the township on a yearly basis, the specific number of spent fuel rod assemblies which have been moved into the dry storage facility."

• Oyster Creek Generating Station Reply to Condition Eleven:

There were no fuel assemblies loaded into the ISFSI prior to 2002. During 2002, 244 fuel assemblies were transferred to the ISFSI. During 2003, 244 additional fuel assemblies were transferred to the ISFSI. During 2004, 183 additional fuel assemblies were transferred to the ISFSI. During 2005, 305 additional assemblies were transferred to the ISFSI. No fuel assemblies have been loaded into the ISFSI since 2005. The Oyster Creek ISFSI currently contains 976 fuel assemblies.

Independent Spent Fuel Storage Installation Building Permit Condition Seventeen:

"The applicant shall submit a report to the Township of Lacey no less than annually as to the status of the efforts of the Federal Government to site a permanent spent fuel repository."

Oyster Creek Generating Station Reply to Condition Seventeen:

The Yucca Mountain Repository project funding has been reduced to those costs necessary to answer licensing inquiries from the Nuclear Regulatory Commission. The current Administration is considering a new strategy toward spent nuclear fuel storage.

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HORIZONTAL STORAGE MODULE TEMPERATURE TRENDS 120 100-.---HSM #1

-- HSM #2

-EHSM #4

-*--e-HSM #5 80 -- HSM #5

---

HSM #8 I-40 . .HSM

. *HSM #10#12 HSM #13 HSM #14 HSM #15 20 HS#1 0

A 0)

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I 3Ct S Radioloaical Survev IND. Vjt*s 6 fs% - 6. 1/0 IDate /[0)- //OYITIme // Location INDEPENDENT SPENT FUEL STORAGE FACILITY RWP e8-8 0 //S.* Reason 744-57-In J& 4/Z Rx. Power - 0%7 D9 j

)3x LOCATION SMEARABLE CONTAMINATION y 0 CCPM [ DPM I INSTRUMENTATION DATA RADIATION SURVEY A R DPM AREA

_____ ____ ____ ____ ____ ____ _____ _____ I_ _ _ __ _ __ _ __

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/) -7;9 BCF f1_4~ 5 ____________ _____CDD Ism 5

CDD_ CONTAMINATION SURVEY 7 INS fAkIA' O.A 9 _CDD 8 S/N 10%

10 ___EFF BKG", CPM

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• .cApes~ r - 11 __________ ___INST 12 _______________ S/N CJ_0TL~vA? 1j3 ____________DD I"I~' I"'1411m I*!* I*'! 14 15 CF BKG AIR SAMPLE DATA CPM I

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161 17 18 _________

FC LL_________

Larg Ar

=________

T NC = Not Countea_

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-7 19. N.A - Not Ilicable 201 NT = Not Taken syor:lPrlnt Name) /o 41

- "o # = Gamma G.A. = Smear P k DV

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.~1v Date # B = Beta OF - Direct Frisk

£V~oF I~~YkV f '1~4 1/i 1 /(.Y ;411~-k /j IO; 11(C*' T

, # N = Neutron X-X or - - = Rad Bound Signature .*-

• Date #/# = Contact 3/cm 3 #_ Beta / yContai Hd = Head, =ChestK =Knee, w= aiSt #BI#=P/y #1# Beta / y 30cm All dose rates in mrem/hr unless otherwise noted I 0 No Beta Detected Unless Otherwise Noted X--No Beta Readings Taken EAL Threshold Values: HSM Dose Rate Tech Spec Limits: A/outiine Surveys:

1. Natural phenomena affecting a loaded cask CONFINEMENT BOUNDARY <400 muernhr at 3 feet from the HSM yand 'it dose rate surveys on conttact as indicaled by on contact radiation reading a 10 times normal. OR surface and lfl from the loaded HSMs.

General area and fence line as

2. Accident conditions affecting a loaded cask CONFINEMENT BOUNDARY < 100 mren/hr HBM door on center line necessary to verily postings. Gross as indicated by on contact radiation reading , 10 times normal. OR of DSC wipe contaminalion survey.

3. Any condition in the opinion of the Emergency Director that indicates loss < 20 mrem/hr end shseld wall extenot of loaded fuel storage cask CONFINEMENT BOUNDARY.

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DCGS Radiological Survey

• INo.~,4F.S

= l

&V OR--)iG =

I* I* Date a til ITime /),'L?

iT Location INDEPENDENT SPENT FUEL STORAGE FACILITY

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iii~~eason j 'v, C.~6 000SMEARABLE

-O *'" ~~~~~Rx. Power- /0j/O % I*Ha~

CONTAMINATION ____INSTRUMENTATION DATA

-OC- 703OCCPM 9 ,'(/**** DPM RADIATION SURVEY LCTO 0MRAD/HR io*SM /, IBC ov/:

a~ P C (03 1 LOCATION AREA

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3. .- *,4 . _INST /Z.2 4 1.ti, S/N 0 733,4 BCF 9(0 4 .7 6 - (, . I S CONTAMINATION SURVEY 7 k,-j Lf _ -____-- INST l- 0 L) 8 F Cr,

.- Cf 1 ( SIN a0 -7 1 .1 1 -

, Z.Z .3~ 2-( 9 u-*.. k COD /-1-t,

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r9) 10: . ______-______ EFF 10% BKG It_, CPM

/- -4 r7L5J'14"I.' a13*1I11 11 12 131

__________SIN 1I__S-'_-_,__,

COD 14 CF BKG CPM-.

15 __ ýP-"-AIRSA14PLE DATA 4.1. its .'a 16 FC NT 171 L= Large Area Smear I

18_ INC Not Counted 191 NA = Not Applicable 201 1 NT - Not Taken Surneyor:(Print plame) ,

/# L4 _ I#Gamma G.A. @ = Smear I

1. N = Neutron X-X or - - = Rad Bound z SI.0 # I # = Contact 1 30 cm /# _ Beta/ y Conta, Z. G 0pp 0 -.00 d, CCh=hest, Kn = Knee, W'= Wiai# #BI#=P1# Beta / y 30cm 1

All dose rates In mremthr unless otherwise noted 2 ý -3 '1 - I-all r.A . . . .

4LL COMA4T*- JTaoP'. EAL Threshold Values:

_______________ 11NoseBOW 12f ... nI~a%

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l Ew nom aReaingsin SKen HSM Dose Rate Tech Spec Limits: Routine Surveys:

1. Natural phenomena affecting a loaded cask CONFINEMENT BOUNDARY _

400 mrernhr at 3 feet Irom the HSM 7 and 'n. dose rate surveys on contact as indicated by on contact radiatiornreading > 10 times normal. OR surface andill from the loaded HSMs.

General area and fence line as CH.. '- L._&.

.4* e-.' A C ý

• 2. E Accidlent conditions affecting a loaded cask CONFINEMENT BOUNDARY s 100 mremrohr HSM door on center line necessary to verily postings. Gross as incdicated by on contact radiation reading > 10 times normal. OR ot DSC nape contamination survey.

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jI-4 (~~Dot , 10 Q.A*"{-j I' 3. Any condition of loaded in storage fuel the opinion ofthe cask Emergency Director CONFINEMENT that indicates loss BOUNDARY. < 20 mrem/hr end shield wall exterior

)CGS Radioloqical Su rvey i~o'IF- q -5'S-9 !S Date O(0 09 I1~Time I( 3e"3 Location INDEPENDENT SPENT FUEL STORAGE FACILIT IQIQ~'Q 0Q I NWI I/ "Z3 Reason e4-NjA.-TQrt-2Li\J . -- enlJ-17 "9 ERx-Power - 50 t-rF ~ ~ U 7 -~

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LOCATION I

SMEARABLE CONTAMINATION I

0 0y0 CCPM MRAD/HR IW DPM I A)

PM 17 AREA if INST i u~ew .&UicftJ INSTRUMENTATION OAT RADIATION SURVEY 2 o 2-2z. ons I.

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• <.2. 2___ CDO 65* 0-+ 1 3 ______ __ INST Ak~ -

4,S/N !L BCF-55 CDD (C 04>

I 61 CONTAMINATION SURVE Q.2. 0~.1 7 u~l. ___ ___ _ INST 9t\ 114 Azaý.s I *V- VA 9_

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4*A,*I4 CoD EFF 10%

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= e zl"AAAC.

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INST SI COD K_

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• 15 T . I ___- AIR SAMPLE DATA 16 oDrt__ IFC NT cd Z. 01 -7.G. z ý6e' I 17 4 C *1 ~~ L . Large Area Smear 18 NC = Not Counted 129 NA Not Applicable 20 NT = Not Taken Surveyor:(Prlnt Name)

JI,,- ., # :=Gamma G.A. (@= Smear t*% 1tC-0:* 1 # B = Beta DF - Direct Frisk AlN= Neutron X-X or- - = Rad Bout

/-L, #1#=Contactl30cm ## _Betay Con Hd =ý ý, Oh Chest, Kn Knee, W = Waist #B/#t PBy ## Beta / y 30cr All dose rates In mrem/hr unless otherwise noted

<.2. 2 .4.,- 2, L ,24z. .X No BetaO letected Unless Otherwise Noted rNo Beta Readings Taken I L-- ,resholdValues: HSM Dose Rate Tech Soec Limits: Routine Surveys:

~ tre 4 N~Tc:r LLCOPTAC.... 0d'*e -9AAT)4 l Natural phenomena affecting a leaded cask CONFINEA tENT BOUNDARY tKz o400 merrn/hrat 3 feet from the HSM y7and in, dose rate surveys on contact normal. OR surface and I ft from the loaded HSMs.

as indicated by on contact radiation reading > 10 times General area and fence line as tENT BOUNDARY <100 mremhr HSM door an center line necessary to venty postings. Gross normal. OR of DSC wipe contamination suiey.

IJ 3 Any condition in the opirnon of the Emergency Director t[hati ndicAtes loss <20 mrenmhr end shield -Nall extericr of loaded fuel storage cask CONFINEMENT BO UNDARY.