ML20076K388

Forwards Proposed Confirmatory Survey Plan for Reactor Bldg, Shoreham Nuclear Power Station,Brookhaven,Ny,For Review & Comment

ML20076K388
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	10/20/1994
From:	Vitkus T OAK RIDGE ASSOCIATED UNIVERSITIES
To:	Fauver D NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9410310248
Download: ML20076K388 (17)

Text

a ~

6. . g e

4 M

. ORISE '

. CAK RlLKat tr 4 5fl T Ui t' IOR SCIF NCE AND E DUC AT K >N October 20,1994 Mr. David Fauver Division of Waste Management - NMSS .

U.S. Nuclear Regulatory Commission ,

One White Flint North 11555 Rockville Pike Rockville, MD 20852 SUlUECT: PROPOSED CONFIRMATORY SURVEY PLAN FOR TIIE REACTOR BUILDING, SIIOREIIAM NUCLEAR POWER STATION, BROOKIIAVEN, NEW YORK [ DOCKET FILE NO. 50-322] ,

Dear Mr. Fauver:

Enclosed is the subject document for your review and comment. Comments you may have will be incorporated into the fm' al plan. Attachment A of the document contains the spending plan for this project. Please do not hesitate to contact me at (615) 576-5073 should you have any -

questions.

Sincerely, Timoth itkus Environmental Project Leader ,

Environmental Survey and Site Assessment Program TJV:rde Enclosure cc: R. Uleck, NRC/NMSS/TWFN 7F27 D. Tiktinsky, NRC/NMSS/TWFN 8A23 c. . ,,._ . . ,.

L. Pittiglio, NRC/NMSS 7F27 - '"

R. Nimitz, NRC/ Region I PMDA, NRC/NMSS/TWFN 8A23 J. Beck, ORISE/ESSAP E. Abelquist, ORISE/ESSAP File /273 9410310248 941020 PDR Apock c5000322 W PDR P O. BOX 117, OAK ROGE, TENNE 55EE 378310117 Monoged ond operovd by Ook Ridge Associated Universaes for the U S. Department of Energy j

l PROPOSED CONFIRMATORY SURVEY PLAN FOR TIIE REACTOR BUILDING SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVFN, NEW YORK INTRODUCTION v

The Long Island Lighting Company (LILCO) constructed a boiling water reactor known as the Shoreham Nuclear Powar Station (SNPS). The plant was designed to provide a gross electrical output of 849 Megawatts and achieved initial criticality in February 1985. The U.S. Nuclear Regulatory Commission (NRC) License No. NPF-82 (NRC Docket File No. 50-322) issued for the facility allowed reactor operations at power levels not to exceed 5% of full power. Iow power testing in accordance with the license then commenced in July 1985 and continued intermittently until January 1989, at which time power generating operations were terminated.

The total reactor operating history was equivalent to 2.03 effective full power days of fuel exposure. The irradiated fuel, which was a standard low enrichment (2 to 3% uranium-235) uranium fuel, was subsequently removed from the reactor vessel and placed into the spent fuel poolin August 1989.

Various reactor components, piping systems, and other equipment became radiologically contaminated as a result of reactor operation. The primary contaminants which have been identified during characterization studies include iron-55, cobalt-60, nickel-63, and smaller quantities of tritium, carbon-14, nickel-59, manganese-54, zinc-65, and europium-152.2 The Long Island Pawer Authority (LIPA) was established to decommission the facility and release the site for r.nrestricted use. The LIPA Decommissioning Plan was approved for implementation by the NRC in June 1992 and willinclude ' decontamination or removal of Prepared by the Environmental Survey and Site Assessment Program, Energy / Environment Systems Division, Oak Ridge Institute for Science and Education, under interagency agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S.

Department of Energy.

Renaw INMeg October 20.1994 hhp \pinwohouhamercham.003

contaminated portions of the reactor and other plant systems and equipment. A major consideration of the decommissioning plan is to maintain the integrity, when possible, of plant structures and systems. The decommissioning and termination surveys are being conducted in phases. Phase 1 included the termination survey of the internal components of the main turbine, the Turbine Building, site grounds, and exterior site structures. Phases 2 and 3, included the Reactor Building Suppression Pool, Phase 2 systems and the Radwaste Building. Phase 4 addresses the remaining portions of the Reactor Building.

The NRC Headquarters' Division of Waste Management has requested that the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conduct confirmatory c diological surveys of t1e SNPS decommissioning project. ESS AP has completed the confirmatory survey of the turbina internal components, the Turbine Building, site grounds, exterior site structures, Radwaste Building, Suppression Pool, and Phase 2 systems. The results of which are the subject of separate final or in process reports.2.3 1

SITE DESCRIPTION l

The SNPS is located in the Town of Brookhaven, New York on the north shore of Long Island, approximately 80 km (50 mi) east of 12 Guardia Airport and the confluence of the East River and Long Island Sound (Figure 1). The SNPS is located on a 32.4 ha (80 ac) portion of a larger 202 ha parcel ofland owned by the LILCO. The site is bounded on the north by Long Island Sound, on the east by the Wading River Marshland, on the west by other LILCO property, and on the south by Route 25A. A cyclone fence encloses the 8 ha site secured area. Within this boundary are the buildings and grounds classified as the Restricted Area, also known as the power block, where radiological controls were necessary (Figure 2). Each of the buildings that have been or will be addressed during the confirmatory process are located here and are shown on Figure 2 as the Turbine Building, the Reactor Building, and the Rad Waste Building.

Construction of the Reactor Building is predominately structural steel and concrete. Total floor space of the building is approximately 7,800 m2 (84,000 ft )2 divided among 8 levels at elevations 8'-0", 40'-0", 63'-0", 78'-0",112'-0",128'-9",150'-0", and 175'-0". The Reactor Building Reactar bklass October 20,1944 2 h:\essaptplanninhoreham\shorcharn 003

j I

housed the nuclear steam supply system which included the Reactor Pressure Vessel and its associated auxiliary and safety systems. Major structural components included the primary containment system, spent fuel storage pool, dryer / separator pool, polar crane and building  !

sumps. The major auxiliary and safety systems included the reactor core isolation cooling, high pressure coolant injection, core spray, stand by liquid control, reactor water cleanup, fuel pool cooling and clean-up, and primary containment atmospheric control systems.

LIPA has classified plant systems and building surfaces into two categories which are basal on the potential for residual contamination. The two area categories referred to as affected or unaffected are defined as follows: "affected areas are those areas of the SNPS that are potentially contaminated or have known contamination, or a system which circulated, stored or processed radioactive materials such that they could become contaminated, or experience, neutron activation, or where records indicated spills or other occurrences may have resulted in contamination; unaffected areas are ' hose portions of the SNPS that are not expected to contain residual radioactivity." Area classification was determined by radiological use history, environmental monitoring activities, and the results of a previous characterization survey.

Affected and unaffected areas are further subdivided into survey units. Survey units are categorized as structures (Hoors, walls, ceilings, and exterior surfaces of piping and equipment),

plant systems (equipment and piping internals), and outdoor areas (grounds and building exteriors). In addition, affected survey units also have sub-classifications as suspect or non-suspect, and may also be classified as alpha affected if i-volved with fuel handling or storage.

OIUECTIVES The objectives of this confirmatory survey are to provide independent document reviews and radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's procedures and termination survey results.

ww w ...a

• 2o.nm 3 monw.u m**m an

RESPONSIBILITY Work described in this survey plan will be performed under it airection of Jack Beck, Acting Program Director and Tim Vitkus, Project Leader of ESSAP. The cognizant site supervisor has the authority to make appropriate changes to the survey plan with the approval of the NRC site representative. Deviations to this survey plan will be documented in the site log book.

DOCUMENT REVIEW ESSAP will review LIPA's release records for those survey units selected for confirmatory survey. Review of additional release records will be dependent upon findings as the surveys progress. Documents will be reviewed for adequacy, accuracy, completeness, and consistency.

Data will be reviewed for appropriateness of et .ulations and interpretations relative to the guidelines.

PROCEDURES A survey team from ESSAP will perform independent visual inspections, measurements, and sampling of survey units associated with the Reactor Building. Table 1 lius the survey units selected for confirmatory surveys. Of the total,11 were selected randomly and 19 were selected by the NRC site representative. Field survey activities will be conducted in accordance with the applicable sections of the ESSAP Survey Procedures and Quality Assurance Manuals. Spo-!C procedures are listed on pages 8 and 9 of this plan. The foilowing procedures apply to survey units selected for independent confirmatory surveys. Additionalinformation regarding selection of confirmatory survey units and the implementation of this plan may be found in the general site confirmatory survey plan.'

I l

I Remt.w hkims - (Atoher 70.1994 4 h:\casse splannsahoreham\shoreham 003

1 SURVEY PROCEDURES 1

Reference System The reference systems established by LIPA will be used by ESSAP for referencing measurement and sampling locations. The grid size or reference interval established by LIPA for a given survey unit was dependent upon the classification of the survey unit (affected vs. unaffected) and surface (floor, lower wall, upper wall, ceiling, or equipment).

Surface Scans Surface scans for alpha, beta, and gamma activity, will be performed over 100% of floor and lower wall surfaces and up to 50% of equipment surfaces, within each structural survey unit.

Additional scans will be performed over portions of upper wall, ceiling, and system surfaces as well as locations, such as drains, where material may have settled or accumulated. Locations of elevated direct radiation detected by scans will be marked for further investigation. Scans will be performed using gas proportional, GM, ZnS, and/or Nal detectors coupled to ratemeters or ratemeter-scalers with audible indicators.

Surface Activity Measurements For each structural survey unit, ESSAP will perform a minimum of thirty direct measurements for total beta surface activity. ESSAP will also perform additional direct measurements at locations of elevated direct radiation detected by surface scans. At measurement locations, where the average NRC surface contamination guideline is exceeded, the size of the contaminated area and the average activity in the contiguous 1 m2 area will also be determined. ,

1 Total alpha surface activity measurements will also be performed at each direct measurement l l

location when a selected survey unit is classified as alpha affected or if alpha contamination is identified by surface scans. Measurements will be performed using GM, gas proportional, and/or ZnS detectors coupled to ratemeter-scalers. A smear sample for determining removable activity level will be collected from each direct measurement location.

I I

kcador ikddmg Omh 20, im 5  %,s w.wmu-wmumm e

)

Exnoste_Itate Measurements Exposure rate measurements will be performed within each survey unit, excluding system interiors, at each accessible floor direct measurement location. All exposure rates will be measured at 1 m above surfaces using a pressurized ionization chamber (PIC). Background exposure rates were previously determined during the confirmatory survey of the Turbine Building.'

DATA EVALUATIONS AND COMPARISONS The results of each survey unit sampled will be statistically tested. The goal of the test is to determine, with a given confidence level, that the LIPA survey data is not biased low compared to ORISE. The null hypothesis will be that in a survey unit, surface activities as calculated by LIPA are greater than or equal to those determined by ESSAP, i.e., H : #UPA b MI3 SAP. This hypothesis will be tested at the 95% confidence level (0.05 level of significance). If the hypothesis is rejected at that confidence level, the alternative hypothesis will be accepted i.e.,

H:3 MurA < #iwe. The test statistic, t, will be calculated using the following equation:

l Xg -X i t= 1 2 f (ng-1)S2 (y _3)3 NE+NL

\ NE*NL ~2 g NEL i where:

Xt Is the LIPA surface activity mean for a survey unit X, Is the ESSAP surface activity mean for the same survey unit nt. Is the number of LIPA direct measurement data points nn Is the number of ESSAP direct measurement data points Si , Su Are the standard deviations.

Rem 1or IMkims Ocder 70. IM 6 h:Venapplansuhorehambhoreham.003

1 l

i The calculated i is then compared to the critical value of Student's t-distribution (one-tailed) for l the appropriate degrees of freedom at the 95% confidence level (0.05 level of significance). If the Ho: Fura h Frm, is rejected, then ESSAP will evaluate additional options and alternatives i and confer with the NRC as to the recommended approach.

GUIDELINES The applicable Regulatory Guide 1.86 guidelines are those for beta-gamma emitters and the alpha contamination guidelines are those for uranium and associated decay products. The beta-gamma guidelines are:

Total Activity 5,000 B-y dpm/100 cm2, averaged over 1 m 2 15,000 B-y dpm/100 cm2 , maximum in a 100 cm2 area Removable Activity 1,000 B-y dpm/100 cm2 The alpha guidelines are:

Total Activity 5,000 a dpm/100 cm2, averaged over 1 m2 15,000 a dpm/100 cm2 , maximum in a 100 cm2 area Removable Activity 1,000 a dpm/100 cm2 1

The NRC has approved site-specific allowable surface contamination guidelines for H-3 and Fe-55, particularly in activated concrete and steel.3 These guidelines are: l nea,, w . c%,2o. im 7 a:se p# i w .es.m . sores.m s 003

Total Activity 200,000 dpm/100 cm2 , averaged over 1 m 2 600,000 dpm/100 cm2 , maximum in a 100 cm2 area 4 Removable Activity 1,000 dpm/100 cm 2 The evposure rate guideline currently being used by the NRC is 5 R/hr above background, measared at 1 m above the surface.'

TENTATIVE CONFIRMATORY SCIIEDULE Phase III: ' Reactor Br.ilding Surveys Document Review October 1994 Confirmatory Survey October 31 through November 11,1994 Sample Analysis November 1994 l

Draft Report January 31,1995 l

LIST OF CUR. RENT PROCEDURES TO BE USED IN TIIE SURVEY Applicable procedures from ORISE ESSAP Survey Procedures Manual (Revision 8; December 31,1993) include:

Section 5.0 Instrument Calibration and Operational Check-Out 5.1 General Information i 5.2 Electronic Calibration of Ratemeters 5.3 Gamma Scintillation Detector Check-Out and Cross Calibration 5.4 Alpha Scintillation Detector Calibration and Check-Out i 5.5 GM Detector Calibration and Check-Out 5.6 Proportional Detector Calibration and Check-Out 5.7 Pressurized Ionization Chamber Calibration and Check-Out 5.8 Floor Monitor Check-Out 5.10 Field Measuring Tape Calibration Reactor IWidmg - (X1ober 20,1944 8 h: \essap\planserchamuhoreham.003

Section 7.0 Scanning and Measurement Technigres 7.1 Surface Scanning 7.2 Alpha Radiation Measurement 7.3 Beta Radiation Measurement .

l 7.4 Gamma Radiation (Exposure Rate) Measurement j l

Section 8.0 Sampling Procedures 8.7 Determination of Removable Activity 8.9 Sample Identification and Labeling i

l Section 9.0 Integrated Survey Procedures

]

9.2 General Survey Approaches and Strategies I

Section 10.0 Health and Safety and Control of Cross Contamination Section 11.0 Quality Assurance and Quality Control l

l I

l l

wm www . aw,2o. im 9 uwei.,.ww w mma,. om

SHR15 (2)

1. YORK L.-

.NP S I

^

...:.9

83 emx AGUARDIA .'. ..-

/ AIRPORT

• J- 25 9'

e3 e5

[. 4 .

e7 c 9 CITY

}'

'::AltA TIdNCOS..

N Ji h

d DME M S 0 20 C

MILES FIGURE li Location of the Shorehon Nuclear Power Station Reackw DuMmg Odober 20, im 10 h%=apiplann\shord.am\shoreham 003

SHR31' (1, l t.... .....

M INTAK Y ^^.-- -

fg 3 x 3 EJ r ] ,-

(k l

I Ko"&

gg -Drrtr

, 00 T k TURB!NC l -- BUILDING an m<<

B r E uuuui

/

Ll e v v  :<

u;5]1ng*

83 o

II I

) }1( [*A g o' I

%b r_

fl ll~ __

[f I

I ===

0 '

f o N.fr E' \ '

l VATER v v v SECURED AREA

BOUNDARY FENCE h

~

POVER BLOCK BUILDINGS TO I _ BE ADDRESSED BY CONFIRMATORY h SURVEYS NOT TO SCALE I FIGURE 2: Plot Plon of the Shorehan Nuclear Power Station umwwww-awr2o,w e 11 6%,1,ww%s mm3

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ . 1

TABLE 1 REACTOR BUILDING SURVEY UNITS SELECTED FOR CONFIRMATORY SURVEY SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK Survey Affected (A)/ Structure /

Survey Unit Name Unit / Component Unaffected (U) System PC004 Primary Containment - 63' NW A structure

.PC005 Sub-Pile Room A structure PC007 Primary Containment - 78' NE A structure PC008 Primary Containment - 78' SE A structure PC011 Primary Containment - 109' NE A structure RB004 Reactor Building - 8' SE A structure RB006 Reactor Building - 8' SW A structure I RB014 Reactor Building - 40' SW A structure RB037 Reactor Building - 78' SW A structure RB038 West Accumulator Aisle A structure RB057 Fuel Pool Clean-up Pumps Room A structure RB061 RWCU Regen /Non-Regen HTX's Room A structure RB068 Spent Fuel Storage Pool A structure RB071 x01 Reactor Cavity - 150' A structure RB072 x01 Dryer / Separator Storage Pool A structure RB073 x02 Bioshield Wall Blocks (Concrete) A structure RB073 x03 Bioshield Wall Blocks (Steel) A structure RB103 Reactor Building - 175' A structure RB106 Reactor Building - 175' A structure RB109 Polar Crane A structure i l

SU001 Reactor Assembly Lower Bowl A system i SU002 Nuclear Boiler Main Steam Relief Valve A system  !

1B21-RV-095G Reaitor Ihumg October 20,1m 12 h:se pipleru\shoreham\shortham.003

i TABLE 1 (Continued) j 1

RE.kCTOR BUILDING SURVEY UNITS SELTETED FOR CONFIRMATORY SURVEY S!10REHAM NUCLEAR POWER STATION BROOKHAVEN, NEW YORK  ;

Surver Survey Unit Name Anected (A)/ Stmetud Unit / Component Unaffected (U) System SU004 CRD Hydraulic Control A system SUO14 x05 #953 Misc. Embedded Drain Piping A system 1G11-TK-190 SUO14 x12 RB Porous Concrete Sump #19 or 20 A system SUO23 Misc. Building Storm Drains A system SUO58 Reactor Primary Containment A system SUO60x09 Fuel Pool Cooling Room A system SUO60x 13 RWCU Valve Chambers Room A system SUO60x23 Reactor Building Air from Drywell A system IT46-ADV-039A SUO60x24 Reactor Building Vent Dump A system I

i l

1 l

Reecw NMag - (ktober20, 1994 13 h w r,i horch aorch.- oos

REFERENCES

1. Long Island Lighting Company, "Shoreham Nuclear Power Station Site Characterization Program Final Report," May 1990.

2. T. J. Vitkus, ORISE, " Confirmatory Survey of the Turbine Internal Components, Shoreham Nuclear Power Station, Brookhaven, New York," July 1993.

3. T. J. Vitkus, ORISE, " Confirmatory Survey of the Turbine Building, Site Grounds, and Site Exteriors, Shoreham Nuclear Power Station, Brookhaven, New York," September 1994.

4. Ixtter from T. J. Vitkus, ORISE to D. Fauver, U.S. Nuclear Regulatory Commission,

" Final Confirmatory Survey Plan from the Shoreham Nuclear Power Station, Brookhaven, New York [ Docket File No. 50-322]," November 4,1993.

5. Ietter from C.L. Pittiglio, U.S. Nuclear Regulatory Commission, to A.J. Bortz, Iong Island Power Authority, subject " Approval of a Modification of Facility Release Criteria for Tritium and Iron-55 Surface Contamination at Shoreham Nuclear Power Station, Unit 1," June 7,1994.

6. U.S. Nuclear Regulatory Commission, " Guidance and Discussion of Requirements for an Application to Terminate a Non-Power Reactor Facility Operating License," Revision 1, September 1984.

i I

)

hw hum,- m.her 20. Iw4 14 ha pyw,hms w,ch.m om

~e, & -- - A.. - am a sna-m

1. E 9

0 6

P ATTACIIMENT A i

I

(

Ratt IMkir.g - Octadwr 20.1W h:\esesp\planswhorehamercharn 003

e

?

i I

p l PERFORMANCE PERIOD

{

.i SPENDING PLAN From To

} Name of Laboratory: Oct-94 Mar-95 Oak Ridge institute for Science and Education RFTA Est. Project Cost Title of Project 93-02 $176,150.00 Shoreham Reactor Building NRC Fin Number ORISE Number A9076 1286.02 fWten2???&s@%n952%%221M%i%W9%f1%<%si5 ; 3 o'929&??%%Pmk%M999??%MW*MN*sWhl 5 COST ELEMENTS Oct-94 Nov-94 Dec-94 Jan-95 Mar-95 Direct Costs $37,950.00 $83,250.00 $6,500.00 $700.00 $1,500.00 Indirect Costs-(G&A, DOE Factor) $13,500.00 $29.650.00 $2,350.00 $250.00 $500.00 Total Estimate Costs $51,450.00 $112,900.00 $8,850.00 $950.00 $2,000.00 Project Completion 27.53 % 92.53 % 98.21 % 98.83 % 100.00%l w

I E

t l

{

. . - - - _ _ - - _ _ - _ _ _ _