ML20211P998

From kanterella
Jump to navigation Jump to search
Summary of 990816 Meeting with Saxton Nuclear Experimental Corp & Gpu Nuclear Corp in Saxton,Pa to Continue Discussions Started at Meeting on 990701,about Resubmission of License Termination Plan.List of Attendees & Briefing Matl Encl
ML20211P998
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 09/08/1999
From: Alexander Adams
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9909140156
Download: ML20211P998 (23)


Text

I @ UGg

/1

  • 4 UNITED STATES g ) (. [ NUCLEAR REGui ATORY COMMISSION WASHINGTON, D.C. 20666-0001

% g #- ,

be tember 8, 1999 LICENSEES:' Saxton Nuclear Experimental Corporation (SNEC) and GPU Nuclear Corporation (GPUN)

FACILITY: Saxton Nuclear Experimenta Pacility (SNCF)

SUBJECT:

SUMMARY

OF MEETING BETWEEN E NEC, GPUN AND THE NRC STAFF On August _16,1999, representatives of the NRC staif met at the Saxton Volunteer Fire Department Hall in Saxton, Pennsylvania with representatives of SNEC and GPUN, the licensees for the SNEF. Enclosure one is a list of meeting attc idees. Enclosure two is the L briefing material provided by the licensees at the meating.

The purpose of the meeting was to continue discussionniarted at a meeting on Jui/1,1999, between the licensees and NRC staff. about resubmission of the license termination plan (LTP) for the SNEF.. The LTP wer !nitially submitted on February 23,1999. After an acceptance' review, the staff concluded thet there was not sufficient information in the LTP to initiate a detailed review. The licensees were informed of this in a letter dated April 27,1999, that contained a general discussion of areas where the staff needed more information. The licensees plan to addrt<ss these areas and resubml; the L',P Wr this year. The primary topic for this meeting was dose modeling.

The licensees noted in their opening remarks, that es a result of the historical site assessment, they recently located and entered the discharge tunnel for the old coal steam plant that was next to the containment vessel (CV). The tunnel was built in the 1920s and was abandoned with the river er.d blocked off in the 1970s when the steam plant was torn down. During the 1963s and early 1970s liquid discharges from the reactor facility mixed wM the discharge from the steam plant and flowed to the river. Radioactive material above '060Kground levels was found ir. ruidue and sediment in the tunnel. The licensees are early in their evaluation of the tunnei and .idditiona' nformation will follow on this issue.

The licer, sees gave a presentation on their progress in the area of dose modeling including survey units, dose assessment scenarios, the development of derived concentration guideline levels (DCGLs), the select.'On and use of the computer code that performs pathways analysis calculatiorr, and background studies. The licensees have determined that for outdoor areas 1 they will no: 3djust radiation measurements to account for background radiation. This will result in calculated doses to members of the public from residual radioactive material on site to be t higher than the true values. The NRC staff stated that based on the presentation, the ,

licensees' approach in this area appeared sound.

. Thsre were discussions about some items of interest icant.fied at the L9st meeting. The hD t

liwnsees tantinue to explore the use of historical survey data taken during removal of the outbuildings. The NRC staff is still considering the method to be used to . * . changes to the

Contact:

Alexander Adams 301-415-1127 [ go hh h hkh 990914Gih6 990908 PDR ADOCK 05000146 P PDR

<T 2-LTP after NRC approval. At the last meeting there was a discussion about the condition of the CV at the time of license termination. The licensees are considering leaving the CV intact at the time of license termination as opposed to removing the upper CV prior to license termination. The NRC staff stated that the dose assessment model the licensees used should j match the condition of the CV at the time oflicense termination.

At the end of the meeting, the NRC staff answered questions from members of the public.

Concern was expressed about the planned phase-out of the local public document room. The NRC staff stated that the NRC was moving towards electronic storage of documents and that all documents about the SNEF would be available through the NRC internet site. Another question was asked about the basis of the licensees' DCGLs and the licensees' ability to change the basis. Some of the licensees' proposed DCGLs are based on meeting a 4 mrem /yr limit from groundwater, similar to the Environmental Protection Agency's safe water act's limit, for water pathways. The staff answered that any effort by the licensees beyond the regulatory requirements was not binding on the licensees and could be changed if the NRC staff did not use the information as the basis of their license amendment approval. Licensee commitments that the staff depends on for amendment approval usually are placed in the technical specifications.

Original signed by Alexander Adams, Jr., Senior Project Manager Events Assessment, Generic Communications and Non-Power Reactor Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-146

Enclosures:

As stated cc w/ enclosures:

See next page Distribution: E-mail h G o (6 0 4 4'6 f LMarsh DMatthews REXB R/F PUBLIC SNewberry AAdams OGC NRC Participants EHylton All outside Participants MTschiltz (MDT)

DOCUMENT NAME: G:\REXB\ ADAMS \146 meet 4 sum.wpd To receive a co sy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy OFFICE PM:REXB LA:REXB C:REXB j NAME AAdams LMarsh DATE / /99 7 d/99 i/6/99 OFFICIAL RECORD COPY

f~; e

+

2

' t.TP after NRC approval.- At the last meeting there was a discussion abcut the condition of the

- CV at the time of license termination. The licensees are considering leaving the CV intact ist the time of license termination as opposed to removing the upper CV prior to license termination. The NRC staff stated that the dose assessment model the licensees used should match the condition of the CV at the time of license termination.

At the end of the meeting, fhe NRC staff answered questions from members of the public.

Concern was expressed about the planned phase-out of the local public document room, The NRC staff stated that the NRC was moving towards electronic storage of documents and that all documents about the SNEF would be available throcgh the NRC internet site. Another question was asked about the basis of the licensees' DC.GLs and the licensees' ability 10 change the basis. Some of the licensees' proposed DCGLs are based on mee+Jng a 4 mrem /yr limit from groundwater, similar to the Environmental Protection Agency's safe water act's limit, for water pathways. The staff answered that any effort by the licensees beyond the' regulatory requirements was not binding on the licensees and could be changed if the NRC s#4 did not use the information as the basis of their license amendment approval. Licensee commitments

' that the staff depends on for amendment approval usually are placed in the technical

specifications.

NA .

Alexander Adams, Jr., Seni roject Manager Events Assessment, Generic Communications and Non-Power Reactor Branch

' Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-146

Enclosures:

As stated ~ 4 cc w/ enclosures:

See next page -

1

)

4 a

.Saxton Nuclear Docket No. 50-146 Experimental Corporation (PAGE 1 OF 2) cc:

James Fockler, Chairman Mr. Arthur Rone Saxton Citizens Task Force Vice President Nuclear- 1505 Liberty Street Safety and Technical Services Saxton, PA 16678 GPU Nuclear Inc.

1 Upper Pond Read Dr. Rodger W. Granlund

- Parsippany, NJ 07054 Saxton Independent inspector Radiation Science and Engineering Center Mr. Manuel Delgado The Pennsylvania Ststa !)niversity 2799 Battlefield Road Breazeale Nuclear Reactor Fishers Hill, VA 22626 University Park, PA 1C8102-2301 Mr. Eric Blocher Mr. Gareth McGrath 216 Logan Avenue . ,

Altoona Mirror Wyomissing, PA 19610 301 Cayuga Avenue l

Altoona, PA 16603 David i.ewis, Esquire Shaw, Pittman, Potts, and Trowbridge D. P. Bladassari 2300 N Street, NW President SNEC Washington, DC 20037 2800 Pottsville Pike Reading, PA 19640-0001 Mr. David Sokolsky '

1000 King Salmon Avenue Mr. G. A. Kuehn, Jr Eureka, CA 95503 .

Program Director SNEC Facility GPU Nuclear, Inc.

Mr. Gene Baker 2574 Interstate Drive 50116th Street Harrisburg, PA 17110

! Saxton, PA 16678 George W. Busch Mr Dick Spargo Nuclear Safety Assesement 1004 Main Street Oyster Creek Nuclear Generph:rg Station Saxten, PA 16678 GPU Nuclear Inc.

P.O. Box 388 Mr. Tom Strnad Forked RNer, NJ 08731-0388 TLG Services 148 New Mil ford Road East Dr. William Vernetr.on Bridgewater, CT 06752 . Director of Nuclear T6 ilities Department of Nuclear Engineering

Charles Bar,.er Sciences RD 1 Box 163 University of F:orida James Creek, PA 16657. 202 Nuclear Sciences Center Gainesvillet, FL 32611 f

E, Saxton Nuclear Docket No. 50-146 Experimental Corporation (PAGE 2 OF 2) cc:

Mr. Michael P. Murphy, Nuclear Engineer Carbon Township Supervisors Bureau of Radiation Protection ATTN: Penny Brode, Secretary Department of Environmental Protection R. D. #1, Box 222-C 13* Ficer, Rachel Carson State Saxton, PA 16678 Grfice Building P.O. Bcx 8469 Hopewell Township Supervisors Marrisburg, PA 17105-8469 ATTN: Sally Giornesto, Secretary -

RR 1 Box 95 Mr. Jim Tydeman James Creek, PA 16657-9512 1402 Wall Street Saxton, PA 16678 Mr. D. Bud McIntyre, Chairman Broad Top Township Supervisors Mr. James H. Elder, Chairman Broad Top Municipal Building Concerned Citizens for SNEC Safety Defiance, PA 16633 Wall'i'treet Ext.

Saxton, PA 16679 Mr. Don Weaver, Chairman Liberty Township Supervisors Mr. Ernest Fuller R.D.#1 R.D. #1 Saxton, PA 16678 Six Mile Run, PA 16679 U.S. Army Corps of Engineers Saxton Borough Council l

Baltimore District J ATTN: Peggy Whited, Scretary ATTN: S. Snarski/P. Juhle 1 9* and Spring Streets P.O. Box 1715 Saxton, PA 16678 Baltimore, MD 21203 Ms. Norman ickes, Chair The Honorable Robert C. Jubelirer Bedford County Commissioners President Pro-Temp Senate of County Court House Pennsylvania 203 South Juliana Street 30* District Bedford, PA 15522 State Capitol Harrisburg, PA 17120 Mr. Larry Sather, Chairman Huntingdon County Commissioners Dennis P. Kelly County Court House Nuclear Safety Assessment Huntingdon, PA 16652 -

Oyster Creek Nuclear Generating Station P.O. Box 388 Saxton Community Library Forked River, NY 08731-03888 Front Street Saxion, PA 16678 i

I l

1

.y e

'4 Mc 9

s sf a u n - e n ,v Mm

~

-3 b

r. W om -
sg &

'l Rbbedb. ./-le/nes~ G9tuV s- eks1 -

d/7E G- fe;7 - AO20 7Nror#,#//wi

s. L %~ - uec
9. - Co . 7M CTi~

ro C.J w , W al ats T3 T 6 M i . B u t Sro ds a 1

swsc jf, hY savt ac.k Q - 6&M A)-

l3.&Arld ,}lLIN G Peu n % u re /(/ 9 - C W 16' L.(3. Hon - Htw

. k- $ jb $D*^ Y 5 n - ,

, . *I

1. -

m l$ cAnf/Ywd{ , ff $*W to k k 9a k SwN b Y  ; drf n a - a,ma sa n.ns n J'.. 2K

?y .

& GPM ^l D4 CLOSURE 1

p.,

an*

x Sp 30 ce-v A6- 89 b A 7, 7%. & y ,GMM se + ~ a - m W, n . ure e

)

l L.

e O

SNEC Facility Dose. .

Modeling l

I SNEC/GPU Nuclear - NRC 1 i

August 16,1999  !

l l

ENCMSURE 2 j

i l

Guidance Documents NUREG 1700 - Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans NUREG 1549 - Decision Methods for Dose Assessment to Comply with Radiological Criteria for License Termination l NUREG 1575 - Multi-Agency Survey and Site Investigation Manual 1

Regulatory Guide DG-4006 -

Demonstrating Compliance with Radiological Criteria for License Termination NUREG/CR 5512 - Residual Radioactive Contamination From Decommissioning

w e

l Dose Modeling Software RESRAD - Version 5.82, Developed by. Argonne ,

National Laboratory Environmental Assessment Division

- DandD -Interim Release 1.0, Developed by Sandia National Laboratories for the NRC.

O Areas to be Modeled l

Containment Vessel (CV) 1 Open Land Areas Miscellaneous Site Structures

- Garages (if applicable? 1

- Tunnels

- Decommissioning Support Facility i:DSF)

See Site Map 1

l i

4 e

e 2

PROPERTY MAP -

SAXTON SITE 4

W

/ /  !

I L-

==

h ~

/ gf -

i

-+ ' ' -

..w--

g o_

6 v [ /

I == 's j '

\ '

s s I

, ~

s x ', 1 s s v l 3 ' s l

3 ) \  %

, hEGJN , ) /fl fa/ '

/'

v

~ & // ,

/

s ,a

~ -

c: ,

j SNEC FACILITY SITE BOUNDARIES (No Scale)

,/ .

Treller Complex

/ *

\.

Sub Statton s Radioactive Waste Storage

\

[/ s SNEC CV Area M s PENELEC LINE SHACK Current Trailer Complex Parking Ares y _

4 DSF 9 ;\ -

x

/ ,- \

g ,e% 1

,Y Garage ,

\* l N -

/ i \ i i Current Site 3

Access Road I

\

Outer Fence

Survey Units (Impacted Areas)

Class Structure / Floor Areas Land Areas I

2 2 1 Up to 100 m Up to 2000 m I

2 2 2 100-1000 m 2000-10000 m 3 No Limit No Limit

Dose Assessment Scenarios Resident Farmer (Most Conservative)

Urban Construction Recreational i 1

i

- Re-use of subsurface building structures not considered practical due to flood plain and high groundwater level.

- Per 10CFR20.1402 dose limit is 25 mrem / year for most applicable scenario.

Derived Concentration Guideline Level (DCGId Basis I l

Survey Unit Size Type of Scenario (pathway models)

Hydrogeology Parameters Contaminant Zone (s)

Nuclide Specific

- Cs-137 predominant nuclide

RESRAD Inputs for Open Land Areas 1 Radiation Dose Limit - 25 mrem /yr j Times for Calculations from 0-1000 years Contaminated Zone Inputs

- 10,000 m 2area

- Thickness - 1 meter l

-- No cover material Nuclides (35 related to SNEC)

Active Pathways i

- External gamma

- Inhalation (w/o radon)

- Meat ingestion l

- Milk ingestion

- Aquatic foods

- Drinking water

- Soilingestion

RESRAD Inputs for Open Land Areas (cont.?

Distribution Coefficients (K d values) from NUREG/CR 3332, Table 3.2 and RESRAD default parameters Hydrogeology inputs in accordance with recommendations by Haley & Aldrich Ingestion rates inputs from Reg Guide 1.109, Table E-5 (maximum exposed individual) & RESRAD default parameters l

l l

I 1

S\ EC Ooen _anc Voce DEPTH FROM GROUND SURFACE (METERS)

WELL 0 -

0.91 ' - -

j ,g . ................

UNSATURATED ZONE (SEASONAL) l 1.52 i

SATURATED ZONE 3

I SILSTONE BEDROCK  !

4 SNEC Land Area DCGLs (pCilg)

Nuclide 10000 m' 2000 m 2 Ag-108m 1.4

  • 1.4*

Ag-110m 1.9 2.3 Am-241 20.7 20.8 Am-243 15.5 15.5 C-14 3.2 7.9 Ce-144 155 155 Cm-243 22.8 22.9 Cm-244 38.1 38.2 Co-60 3.0 3.1 Cs-134 4.3 4.7 Cs-137 9.7 11.2 Eu-152 7.8 7.8 Eu-154 7.1 7.1 Eu-155 280 280 Fe-55 42430 91550 H-3 222* 222*

l-129 5. 7

  • 5.7
  • Mn-54 9.6 9.6 Nb-94 1.5* 1.5*

Ni-59 4620 7062 Ni-63 1680 2570 Np-237 0.9 0.9 Pu-238 23.9 24.1 Pu-239 21.6 21.7 Pu-240 21.6 21.7 Pu-241 691 695 Pu-242 22.7 22.9 Ru-106 0. 9

  • 0.9
  • Sb-125 6.1
  • 6.1

U-235 6.6* 6.6*

U-238 30.7* 30.7*

Zn-65 4.1 6.4 Comments:

  • Denotes those nuclide DCGLs dependent on meeting the 4 mrom/yr EPA limit.

s 9 3 3 2 3 5 3 3 9 8 7 1 0 1 1 1 1 1 1 2 2 2 1 1 1 1 0 1 0 1 2 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2

3 )m - - - - - - - - - - - - - - -

2lg / /- / /- /- /- / /- / / /- / / / / / / / / / /

i

+ + + + + + + + + + + + + + + + + + + + +

hc T (p 1 2 6 4 8 2 2 9 1 5 9 7 8 0 3 7 6 1 4 9 9 1 7 8 5 0 1 1 0 1 1 0 7 8 - 1 6 0 9 4 9 9 0 0 0 0 0 0 0 0 0 0 0 9 -

9 9

1 y 8 1 4 5 6 4 5 6 5 7 5 9 7 5 6 5 4 5 4 6 9 1 d 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 t

u 6 2 )m - - - - - - - - - - - - - - - - - - -

2rg /- /- / / / /

S i

/

+

/

+

/

+

/

+

/

+

/

+

/

+ + +

/

+

/

+

/

+

/

+

/

+

/

+

/

+ +

/

+ + + +

d ac -

R (p 3 4 6 6 8 7 8 4 3 4 3 7 2 3 4 7 8 3 2 9 8 n

2 2 8 1 u 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0

o r

g 44 k

c 2 8 2 4

,9 j

a 2 0

6 0

7 0

3 0

3 0

4 0

1 0

4 0

2 0

6 0

6 0

4 0

2 0

3 0

3 0

2 0

3 0

3 0

6 0 :3 B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 rO l

i 7

3 )m A - - - R o 1 gr D / - / - / - / - / - / - / - / - / - / - / / - /- / - / - -

/

/ / /

S sc i

M + + + + + + + + + + + + + + + + + + + t e./ K C

E C (p <

2 4

0 0

8 5

0 2

7 0

3 0

3 3

0 5

2 0

5 5

0 0

9 1

0 2

1 0

5 2

0 6

5 0

3 0

6 4

0 0

1 3

0 1

3 0

2 1

0 8

2 0

9 5

0 0

5 0

o8

,.0 2. _

N g S ,

5 9 6 9 ~

8 7 4 9 5

) 2 0 1 0 0 2 2 1 3 1 1 4 2 2 0 0 1 0 1 0 1 0 m g - - - - - - - - - - - /

4l / /- /- /- / / / /- / /- / / / / /- /-

+

/

+

/

+ +

/- /-

+ +

i

+ + + + + + + + + + + + + + +

Kcp ( 2 5 1 8 2 7 6 5 6 1 1 7 8 7 2 7 4 5 2 3 4 2 9 1 4 9 1 1 1 2 1 1 3 1 1 8 6 1 4 1 9 1 E E E E E E E E E E E E E E E E E E E E 1 2 3 4 5 6 7 8 9 0 1 2 3 4 5 6 7 8 9 0 _

0 0 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 2 E _

n 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 G i

o 0- 0 0 0- 0 0 0 0- 0 0- 0- 0 0 0 0 0- 0 0-A t

a L L- L L L L- L- L L L L- L L L- L- L- L- L L- L R c S- S- S- S- S- S- S- S- S- S- S- S- S- S- S- S- S- S- S- S- E _

o 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 V -

L 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 A X X X X X X X X X X X X X X X X X X X X -

S S S S S S S S S S S S S S S S S S S S

1 .-

1.-

3 4

h I

1 GRAPE

. S 1 1. 0 " . . .. ._. - . . . .

. - s S01L

.....-.......-,......-.......--....-~......,.;... . . ~ . . . . . . , y - '- - - . - . . . . . -- - C A P 808'0" '..*'. -

~

D:.. . . .

~

,.t.'.3 .. .

5 ' .",' .re -

,.:..*; . <.a .

s.

.,, ,. , -- g , ,, -

...e...

-4 .. ..

.d

.s . ., .

)

  • s. .e .

. , ,. .. - ./,. ,0 ;,,..

.e

.a. , - ,

4  :

. ~e . .ar.c..,.,, r. .

s.

+ 4. ,,

-. . , 4..

.a s ., t .e .

.'. ;Q - -

-r *

. ,i

..f.. . - .

- FILL t 'st. *

". 9;.,f'g

. , .? ., . ,

e

., .. *'.. . i,

,,, , p;;. .:lA 8... .

.,', r.,

/

3 "' r*

'. v. h.p*01..e.

s e .- ,,3 *. +

<: *,,,:..,s..

. .<. 4

.+ . . - . , , , - .

, .S. . , . .

. , .. . i

- , .3 c .-c........

-.....~..',

. :~rl:,

,r .

4 , .g.

,s. ,: , ;4.  ;, l t ..

. u .q *. . .P i:*;::

-,*.. ' 6t-

~ ~

.  : 4, a, q, ::2. 4 1.

., . i:.!.  ;- . . .

. * * ? },, ,m.:....:.y..g..i,..,;,.s a  ;.: - ;m 1 4.:" ; . ' '

< a

' ., , _. .C.-* CONCRETE I llJ: 4*:.

.i . , ,

'

  • 4-7 .' ) .i .. DEBRIS

' l

\

65'8" 6 ." b ".? . ** 'd " '

' - **'. ' N,' '

'=l L.. '. l';:. l :.)j; .i.9':t::p.,-ly ;iQ;i.:, K e7 j

. ,..,"i., . . ..,

  • . .v. .. ;. w., . . , ..

.....*4:.'.',..A."* . is.,

. ....m.

r., : , . . , ..  :, . ,  ; .>.-. .!.. . . .

- s-s ...

Containment Yessel, SeeHonal View hnp '?

Post DemollHon scau: (r m )

I I

i: \

i.

l l

Open Ouestions i

Limitations of Software  !

- How to evaluate concrete annular ring of CV.  !

l

- Evaluating contaminant zone inside saturated zone.

Concrete Leaching Study i l

Results Site Classifications  !

Background Variability Scan Measurements ,

!