ML20128P645
| ML20128P645 | |
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| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 02/28/1993 |
| From: | LONG ISLAND POWER AUTHORITY |
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| NUDOCS 9302250052 | |
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Text
g LJ THE SHOREHAM NUCLEAR POWER STATION (SNPS)
DECOMMISSIONING PROJECT TERMINATION SURVEY FINAL REPORT FOR THE STEAM TURBINE SYSTEM (N31) 1
& LONG ISLAND POWER AUTHORITY I (,
l February,1993 l
l DR ADO OO 22 I W PDR l
L-TERMINATION SURVEY REPORT FOR TURBINE SYSTEM (N31)-
FOR THE DECOMMISSIONING OF THE SHOREHAM NUCLEAR POWER STATION (SNPS)
TABLE OF CONTENTS P3L42
1.0 BACKGROUND
INFORMATION
1.1 INTRODUCTION
1 1.2 MANAGEMENT APPROACH 1 1.3 OWNERSHIP 2
2.0 DESCRIPTION
OF SURVEY AREA 2.1 SITE DESCRIPTION 2 2.2 SITE CONDITION FOR TERMINATION SURVEY 2 2.3 SCOPE OF SURVEY 3
2.4 DESCRIPTION
OF MAIN TURBINE 3 3.0 OPERATING HISTORY OF TURBINE 3.1 TURBINE OPERATION 7 3.2 PROCESSES PERFORMED 7 3.3 WASTE DISPOSAL PRACTICES 7 4.0 DECOMMISSIONING ACTIVITIES FOR THE TURBINE 4.1 OVERVIEW OF SNPS DECOMMISSIONING 7 4.2 DECOMMISSIONING OF TURBINE 9 5.0 PROCEDURES FOR THE TERMINATION SURVEY OF THE TURBINE 5.1 SAMPLING PARAMETERS 10 s
5.2 BACKGROUND
/ BASELINE LEVELS IDENTIFIED 11 5.3 MAJOR CONTAMINANTS IDENTIFIED 12 5.4 GUIDELINES ESTABLISHED 12 5.5 EQUIPMENT AND PROCEDURES SELECTED 13 5.5.1 Instruments and Equipment 13 5.5.2 Survey Procedures 18 5.6 QUALITY ASSURANCE 20 5.7 TERMINATION SURVEY ORGANIZATION 20 6.0 TERMINATION SURVEY RESULTS FOR THE TURBINE SYSTEM 6.1 TECHNIQUES FOR REDUCING / EVALUATING DATA 20 6.2 COMPARISON OF FINDINGS WITH GUIDELINE VALUES AND CONDITIONS 20 7.0
SUMMARY
22 APPENDICES A. SURVEY MAPS B. SURVEY PROCEDURES C. TERMINATION SURVEY PROGRAM DESCRIPTION D. TERMINATION SURVEY PLAN ATTACHMENTS Release Record for Turbine System N NQA Surveillance Activities Instrument Control Charts
l Termination Survey Report for Turbine System (H31)
1.0 BACKGROUND
INFORMATIOf!
1.1 INTRODUCTION
This report presents the details and results for the survey of the-Shoreham Nuclear Power Station Turbine System (N31). A complete survey was performed of the high pressure stage of the main turbine. This survey of the system was performed in accordance with the survey methodology, equipment, procedures, controls, and data base analysis described in the Termination Survey Program Description (attached as Appendix C.), Termination Survey Plan (attached as Appendix D.), and the associated Termination Survey Implementation procedures (attached as Appendix B) and applicable Instrument procedures.
This report represents a complete description of the turbine survey design and results, but also includes general information to describe the Shoreham Nuclear Power Station site, operating history, and termination survey methodology as background context information.
1.2 MANAGEMENT APPROACH -
f Due to the specialized nature and magnitude of this project a
/7 Program Descriptio:'. was developed specifically for the performance V of the Termination Survey. The principal objective of the " Program Description for the Shoreham Decommissioning Termination Survey" (PDXOM-01) is to describe the Termination Survey Organization and the Lanagement control mechanisms for the Termination Survey Program. The Program . Description describes responsibilities in support of the Termination Survey Program, provides an overview of management's approach for successful completion of the survey and establishes the basis for developing the Termination Survey Program implementing procedures. A companion document to the Termination Survey Program Description is the Termination Survey Plan. The Termination Survey Plan describes the technical methods to be used to complete the Termination Survey and provides guidance for planning and designing the multiple radiation and contamination surveys which are needed to successfully demonstrate that the facility meets residual radiation guidelines, so that the current NRC license can be terminated.
The termination survey is performed on a section level within the Radiological Controls Division, however, management responsibilities for the performance, support, and oversight of the termination survey exists at all levels throughout the Long Island Power Authority (LIPA) organization.
Termination Survey Report for Turbine System (N31) 1.3 OWNERSHIP The steam turbine system, although _ located on LIPA property, remains under the ownership of the Long Island Lighting Company (LILCO). As a high value asset, the equipment is maintained in a salable condition; available for possible reuse.
2.0 DESCRIPTION
OF SURVEY AREA 2.1 SITE DESCRIPTION The Shoreham Nuclear Power Station site is located in the Town of Brookhaven, Suffolk County, New York on the north shore of Long Island. The site is approximately 50 miles east of the confluence of the East River and Long Island Sound which is near La Guardia Airport. The developed portion of the site comprises 80 acres, and is located within a larger parcel of 499 acres owned by the Long Island Lighting Company (LILCO). Under the Asset Transfer Agreement, approximately 11 acres of the site which include the power block, adjacent office and support buildings and connected roadways have been transferred to LIPA for conduct of the
, decommissioning. The 499 acre parcel is bounded on the north by Long Island Sound and on the east by the Wading River marshland. It D is bounded on the west by a parcel of approximately 429 acres known (V as the Shoreham West property, also owned by LILCO, and on the south by highway Route 25A. The 499 acre SNPS site property is divided across its midsection in the east-west direction by North Country Road which branches of f Route 25A about three miles west of the site and rejoins 25A about three miles east of the site. North Country Road is about 1,500 ft. south of the Reactor Building at its closest point to the developed area of the site.
2.2 SITE CONDITIONS FOR TERMINATION SURVEY The Shoreham Facility will be largely left intact following Decommissioning. Dismantlement is confined to small pc.rtions of the Reactor, Radwaste and Turbine Buildings. Removal has been for purposes of removing contaminated structures and to provide paths for removal of contaminated piping and equipment. As described in the LIPA Decommissioning Plan, most of the radioactive piping and-equipment will be dismantled and removed from the facility and disposed of as radioactive waste at a licensed radioactive waste disposal facility. This includes reactor vessel internals and major portions of the plant systems that were characterized as being-radioactively contaminated. It is estimated that greater than 75 percent of the piping and equipment on site during the time of reactor operation will remain after Decommissioning is complete.
I Termination Survey Report for Turbino System (N31) f 2.3 SCOPE OF SURVEY The Shoreham f acility and environs have been evaluated to identify the areas to be covered in the Termination Survey. The Termination Survey focuses on the area within the Secured Area fence. The area, (approximately 20 acres), contains the Reactor, Radwaste and Turbine buildings, and other buildings, ft.:ilities, and grounds within the Secured Area fence. The Secured Ares is described in the Shoreham Nuclear Power Station Termination Survey Plan. The area within the Secured Area fence coincides with the Restricted Area defined in Shoreham radiological control procedures as the area where access has been controlled and raa oactive materials controlled for purposes of protection of indi c daals from exposure to radiation. Following completion of Shoreham Decommissioning and removal of the irradiated fuel from the site, areas outside the Restricted Area may be added to the Survey i'f used for temporary storage or handling of irradiated fuel or other radioactive materials.
Major attention in the Termination Survey is given to the areas most affected by reactor operations and by decommissioning activities. The area covered by the Termination Survey has been divided into approximately 450 individual " survey units" - f or f management of the Survey. Each survey unit is classified as "af fected" or "unaf f ected" f or survey implementation. An "af f ected"
('
\ area as defined in draft NUREG/CR-5849 and used in this interin termination survey report is a designation used to indicate that an area (survey unit) has a potential for containing residual radioactive contamination. An " unaffected" area is one which is not expected to contain residual radioactivity based upon the operating history, decontamination history, and previous radiological surveys. Affected areas are largely confined to the Reactor and Radwaste buildings, and portions' of the Turbine building. Table 2.1, Shoreham Termination Survey Classification Summary, summarizes the breakdown of the f acility into af fected and unaffected areas and is an update to a similar table contained in the Termination Survey Plan, (Appendix D). The Turbine Building, Code TB, on elevation 63'-0" houses the Turbine, which is considered as a single survey unit in this Termination Survey Report.
2.4 DESCRIPTION
OF MAIN TURBINE The Steam Turbine System (or Main Turbine System), (N31), consists of a General Electric 1800 rpm tandem compound turbine with one high pressure (HP) and two low pressure (LP) turbine sections. The main turbine is located on elevation 63' of the Turbine Building.
L Termination Survey Report for Turbine System (N31)
I Ly
\# The purpose of the main turbine is to convert heat energy in the high pressure steam from the reactor to mechanical rotation energy.
The HP turbina acetion, IN31-TU-001C, of the main steam turbine consists of seven reaction stages in each of two flow paths. It has a single shell, with a flanged joint along the horizontal center line dividing it into upper and lower halves. The diaphragms are fixed, and are divided into upper and lower halves, fitting closely into special recesses in the shell.
The fixed diaphragms direct the steam onto the moving buckets at an angle. The diaphragms have close-clearance packing rings at the turbine-wheel inner and outer bucket diameters and at the turbine spindle. These packing rings prevent bypass steam flow and provide increased efficiency.
Steam enters the HP turbine through four 24" steam legs which are connected to the turbine by flanged joints. Each steam leg has a control valve in it and supplies a partial-arc nozzle box which covers one-quarter of the first stage circumference.
Steam extraction lines are provided after the seccnd turbine stage (to supply the first stage of the reheater), and after the fourth
/ turbine stage (for the first point feed heaters). The outer ends
[,] of the HP turbine form high pressure exhaust hoods which direct the
'v steam downward into four 42" " cold reheat" lines; one line from each HP hood is supplied to each reheater (four lines, total).
The steam exhausting from the HP turbine is 12-13% wet at rated load. Special provision is made to drain the last three (fifth, sixth and seventh) turbine stages into the exhaust lines. Higher pressure turbine stages are drained to the extraction pipework.
The turbine shaft seals are " clean"-steam sealed to prevent leakage. The seals are serviced by the Steam Seal System.
The HP turbine glands are four-stage sealing units consisting of multiple close-clearance packing rings. Steam is exhausted to the third point feed heater after the first sealing stage and to the '
main condenser after the second sealing stage. " clean" steam from the gland steam-seal system is supplied to the third stage. The-fourth stage is exhausted to the gland steam exhauster. The packing rings and spindle have special provision to remove moisture condensed in the glands.
The cold reheat lines (HP turbine exhaust) have extraction lines to the second point feed heater and discharge into the underside of the reheaters into an axial distribution space. The reheater /
- Termination Survey Report - for 'larbine ;Sistem - (N31)
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- separators are horizontal. cylindrical _ units consisting-- ofL.a moisture separation stage and two reheat stages.-.The reheat steam-
- passes-through the chevron type moisture separators,- in which the combination of reduced velocity and direction changes provide an-effective moisture-removalisystem.- The steam then passes over the:
first and seco'nd stage reheat tube bundles:and discharges through" two 42" hot reheat lines from each reheater.:
The first stage reheat tube bundle' receives _ extraction steam from-the HP turbine. The pressure -and temperature of this steam is proportional to turbine load. The second-stage reheat tube bundle" .
receives high pressure steam from the high pressure steam manifold. '
Steam flow is controlled by a pressure-reducing valve during startup and at low turbine loads. -At high loads full steam header.
pressure is applied to the second stage tube bundle and_ steam-flow is a function of-the condensation rate that produces reheat steam 25'F below HP steam temperature (514 F) .
The moisture removed by the noisture separator section and the first and second reheater-stages is collected in three separate drain collecting tanks for each reheater- (six total). The collecting tanks have-air-operated drain control _ valves in their -
drain-lines,-which maintain a working level while permitting.the-c drain. water to_be-" cascade" drained-to the-feed heating system.
Emergency drains, directly to the main' condenser, are provided in--
the event of' failure of the normal drains.
The combined intercept valves (CIV-1, 2, 3, 4) (intermediate stop and intercept) are located adjacent to the low-pressure turbine which they serve. They discharge into full-arc nozzle 1 boxes at -
horizontally opposite-inlet ports located in the-lower-midsection of the LP__ turbines.- The hot reheat lines.have extraction-points for the reactor feed pump turbines._ Each of-these four lines has a pressure relief valve, located before - the combined - intercept valves, which discharges to the main condenser. 'These valves are set to protect the reheaters and the-turbine from over-pressure.
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Termination Survey Report for Turbine System (N31)
Table 2.1 Shoreham Termination Survey Classification Summary Total No. No. of Affected No. of Unaffected DESCRIPTION CODE of Survey Units Survey Units Survey Units STRUCTURES Reactor Bldg. RB 100 100 Drywell PC 21 21 Suppression Pool SP 13 13 Turbine Bldg. TB 103 12 91 Radwaste Bldg RW 74 74 Control Bldg CB 4 4 (b
'%)
O & S Bldg OB 4 4 O & S Bldg Annex AB 4 4 i
i Other Site Bldgs OS 9 3 6 l
Structure Totals 332 223 109 OUTSIDE AREAS Site Grounds SG 7 7 Stmeture Exteriors SE 14 14 i
Outside Area Totals 21 21 PLANT SYSTEMS SU 84 38 46 l TOTALS 437 261 176 I
Termination Survey Report for Turbine System (N31)
(
3.0 OPERATING HISTORY OF TURBINE 3.1 TURBINE OPERATION As described in the attached Release Record for the Turbine System (N31), the Shoreham nuclear plant achieved initial criticality in February 1985. Low power testing was performed intermittently at power levels not exceeding 5% of full power from July 1985 until June 1987. The total fuel burnup corresponds to approximately two ef fective full power days. The turbine was rolled using main steam on three occasions. The first two occurred on August 20, and 26, 1986. The final time the turbine was on line was from June 4- 5, 1987.
3.2 PROCESSES PERFORMED No chemical processes were performed to the Turbine during its life.
3.3 WASTE DISPOSAL PRACTICES No radioactive waste was generated during the Turbine System g operation.
) 4.0 pECOMMISSIONING ACTIVITIES 4.1 OVERVIEW OF SNPS DECOMMISSIONING The following discussion is a brief overview of the SNPS decommissioning activities to the present time.
LIPA selected the DECON alternative for the decommissioning of the Shoreham plant. The DECON alternative is defined by the NRC in NUREG-0586 as follows:
i "DECON is the alternative in which the equipment, structures, and portions of the facility and site containing radioactive contaminants are removed or decontaminated to a level that permits the property to be released for unrestricted use shortly af ter cessation of 1
operations."
l Termination Survey. Report for Turbine System (N31) e The major decommissioning following work categories:
activities were divided into t;'
(1) System and Structure Decontamination and Dismantlement.
(2) Segmentation of the Reactor Pressure Vessel (RPV) and Internals.
(3) Radwaste Management.
(4) Area cleanup and Decontamination.
There has, however, been no need to apply any of these decommissioning techniques to the Main Turbine System because the Site Characterization Study demonstrated the absence of any contamination of this system above the release limits.
System and Structure Decontamination and Dismantlemeat.- LIPA is proceeding to decontaminate and dismantle Shoreham's plant systems and structures to the extent necessary to assure the removal of the Shoreham plant irrevocably from service as a nuclear generating
( facility and to permit release of the facility for unrestricted use. LIPA has used a wide range of decontamination and dismantlement techniques to achieve this objective. However, the
[O large majority of Shoreham decommissioning work was accomplished through dismantlement and removal of equipment.
The limited decontamination techniques used by LIPA are consistent with those used routinely throughout the nuclear industry. In-situ high pressure water lancing, and a variety of manual techniques I have been used by LIPA during the course of Shoreham's decommissioning. In addition, LIPA has extensively used off-site decontamination services to volume reduce contaminated equipment and structures removed from the site.
LIPA has applied industry-accepted and field-proven processes for the dismantlement of certain plant systems and structures. Such techniques ranged from simple, manually operated power bandsaws used to sever small bore piping through more sophisticated techniques such as pipe r.ounted rotary milling machines which were
?
used to sever all large bore piping. The selected options of available technology reflected careful consideration of the radiological conditions associated with their application.
Termination Survey Report for Turbine System (N31)
Secimentat ion of the Reactor Pressure Vessel and Internals-Radiological characterization of the Shoreham site revealed that the majority of radioactive material resulting from the plant's limited period of operation was contained within the reactor internals. The RPV and internals were decontaminated to the extent practicable, and hava been segmented, packaged and shipped for use by others, or for off-site disposal. The bottom head of the RPV remains for either further decontamination, or removal for offsite disposal.
Segmentation of the highly activated reactor internals was performed using underwater, semi-automatic plasma are equipment.
The RPV was severed into ring sections using a platform mounted rotary milling machine inside of the RPV. The ring sections were then cut into pieces appropriately sized to permit their safe and efficient handling, packaging and shipping using a thermal cutting technique.
Radwaste Manacement- LIPA had initially estimated that approximately 80,000 cubic feet of low level radioactive waste (LLRW) would be generated as a result of Shoreham's accommissioning. LIPA has processed, packaged, shipped and g disposed of Shoreham's radwaste in accordance with applicable federal and state regulations.
Volume reduction is a key aspect of LIPA's management of Shoreham's radwaste. Through an aggressive campaign of decontamination, waste segregation and other industry-proven vaste processing techniques, LIPA has consolidated Shoreham's radwaste so that only a small fraction of the 80,000 cubic foot estimate will require disposal at a licensed radwaste burial facility.
Area Cleanuo and Decontamination- Various areas throughout the plant were affected by the decontamination and dismantlement activities and were decontaminated, and surveyed, as required, following the completion of decommissioning activities.
Precautions have been taken to preclude the spread of contamination to the vast majority of plant areas which are clean.
4.2 DECOMMISSIONING OF TURBINE No decommissioning activities were performed on the Turbine.
Termination Survey Report for Turbine System (N31) i h
O 5.0 PROCEDURES FOR THE TERMINATION SURVEY OF THE TURBINE 5.1 SAMPLING PARAMETERS Due to the short operating period and low power levels-(below 5%)
at which the Shoreham plant operated, radioactive contamination was found in only several structures and fourteen systems. These structures and systems are the focus of the planned decommissioning-activities. In addition, the final radiation survey includes those areas (indoor and outdoor) that may potentially have been contaminated due to Shoreham plant operations but were determined to be uncontaminated during the site characterization program, and any area ar system that could potentially become inadvertently contaminated during the decommissioning activities. The final radiation survey of each system, structure and area are scheduled to ensure that surveyed areas, structures and systems are not recontaminated by subsequent decommissioning operations.
The Termination Survey is implemented at the individual survey unit level. Three categories or types of survey units have been established: 1) structures, which include building interiors,
- 2) plant systems, and 3) outdoor areas. These categories combine survey units into groups with similar physical characteristics. The
( Survey is planned for measurements to be taken for each survey unit independently. The measurement intensity of each survey unit is based upon its classification as affected or unaffected.
The Termination Survey planning and implementation process f or each survey unit involve.c the following steps: 1) initial classification; 2) history file preparation and classification review; 3) turnover for Termination Survey; 4) walkdown; S) survey design; 6) preparation of modification packages (primarily for plant systems surveys); 7) preparation of Maintenance Work Pequests (MWR) and scheduling; 8) preparation of final survey instructions;
-9) physical support activities such as erection of scaffolding, system tagout and system breaches for system surveys;
- 10) performance of the survey; and 11) post survey restoration and control of surveyed areas (isolation of systems after survey completion). These steps are described in detail in the Termination Survey plan.
After survey measurements have been taken, reviewed and approved,.
and quality control (QC) verification survey measurements have been completed in system survey units, the system is restored and components are replaced as specified in the applicable Maintenance Work Request (MWR) . If indicated in the MWR, the system is isolated to protect against recontamination. Isolation and control of plant systems af ter Termination Survey is performed under a specific l
Termination Survey Report for Turbine System (N31) approved procedure.
It is noted that many plant support and service systems will be returned to service after completion of Termination Survey measurements. Examples are: compressed air, heating and cooling, ventilation and fire protection. When a system is required to remain in service, administrative controls will be used to minimize the possibility of system contamination. These include, but are not limited to, surveillance activities to ensure that the system is not aligned or operated in a manner which could compromise Termination Survey results.
After measurements are completed, each area is posted and access is l controlled to prevent or minimize possible contamination. This is controlled by an approved station procedure.
l The Termination Survey is scheduled to be completed in several major phases which encompass distinct portions of the facility. I Upon completion of each phase the release records will be compiled and the survey units covered will be available for NRC verification surveys. All except the final phase of the Survey are scheduled for completion by October 1, 1993, with the final phase to be completed following removal of the irradiated fuel from the l
facility. The current schedule date for completion of fuel removal !
is November 1993.
5.2 BACKGROUND
/ BASELINE LEVELS IDENTIFIED Background count rates have been established for the detectors used for the turbine survey. For direct beta-gamma measurements, the HP260 GM pancake detector is used exclusively. Backgrounds have been established for conditions which apply during the turbine survey. The HP260 detector background is most strongly affected by the materials in the immediate vicinity of the detector. The turbine HP section materials are primarily carbon steel and stainless steel.
The HP260 background count rate used for the turbine survey was obtained from surveys of large bore piping from a plant system known to be free of contamination, (N44 Vacuum Priming, carbon steel). This value is 14 i 4 cpm, i.e., a mean value of 14 cpm with a standard deviation of 4 cpm.
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1 Termination Survey Report for Turbine System (N31) 5.3 MAJOR CONTAMINANTS IDENTIFIED Detectable radionuclides in plant piping surface contamination deposits which could contribute to turbine contamination are limited to a small number of radionuclides. An analysis of _ Shoreham Station piping system corrosion product samples shows that these are comprised largely of Co-60 and Fe-55, with an average Fe-55:Co-60 ratio of approximately 0.2, (0.21 1 0.13). When adjusted for radioactive decay to the estimated time of license termination in 1994, the ratio is reduced to 0.14.
. 5.4 GUIDELINES ESTABLISHED The Termination Survey is designed to demonstrate that licensed radioactive materials have been removed such that residual levels of radioactive contamination are below applicable Regulatory' Guide 1.86 limits. These are shown in Table 5.4.1, Acceptable Surface Contamination Levels. Radiation detection instrumentation requirements for the Survey are based upon the conclusion that the controlling radioactive species in determining compliance with Regulatory Guide 1.86 release limits are activation products dominated by Co-60. These are beta-gamma emitters as defined in g Regulatory Guide 1.86, hence the limits for beta-gamma emitters shown in Table 5.4.1, below, apply.
The applicable release limits for alpha emitters are also shown in Table 5.4.1. These are for Natural Uranium, U-235, U-238 and associated decay products. Though none has been datected in plant contamination deposits, the presence of the irradiate 9 fuel in the facility provides a potential source of alpha contamination.
Instruments and methods are being incorporated _ into the survey which are adequate to measure alpha surface activity at levels below the limits in Table 5.4.1.
Table 5.4.1 Acceptable Surface Contamination Levels l (dpm per 100 cm' )
l l Fixed Plus Removable Removable Activity Averace Maximum Beta-Gamma 5,000 15,000 1,000 Alpha 5,000 15,000 1,000 l
, Termination Survey Report for Turbine System (N31) f x 5.5 EQUIPMENT AND PROCEDURES SELECTED 5.5.1 INSTRUMENTS AND EQUIPMENT Radiation detection and measurement instrumentation for the Termination Survey has been selected to provide reliable operation and adequate sensitivity to demonstrate attainment of the release criteria. An evaluation has been conducted of instruments and detectors produced by several manufacturers. Detectors have been selected based upon detection sensitivity, operating characteristics and expected performance in the field under conditions of use. The detectors selected and their detection characteristics are summarized in this Section. Recording instruments (survey meters) ft,r use with these detectors have also been evaluated. Instrumentation to be used for gamma exposure rate measurements and special purpose measurements is also described.
Instrument Descrintdan- The principal instruments selected for Termination Surve; measurements are identified in Table 5.1, Termination Survey Instrument Summary. The detectors used for total surface contamination monitoring.will be for the most part operated with data logging survey meters. Several instruments have been selected for special purpose measurements. A portable gamma
) spectrometer has been c.aained for use in the Termination Survey.
/ It can distinguish between plant-derived residual activity and
( natural background source contributions to measured levels. This capability will be of value if unexplained high levels or other anomalies are encountered. A portable radon monitor will be utilized to evaluate building radon concentration effects on gamma background levels, if necessary.
Detection Sensitivity- The detection sensitivity of the detectors selected for surface contamination measurements has been evaluated.
These results are summarized in Table 5.2, Detector Sensitivities, which is an update to a similar table found in the Termination Survey Plan, (Appendix D.). The minimum detectable activities are calculated using equation 5.1. The minimum detectable activity, or MDA, is dependent on several factors: detector efficiency, background count rate, counting times for background and for background plus the sample count times. The results are shown for the principal instruments used for beta-gamma direct surface measurements. Smear counters for measurement of removable surface activity, of modern design (anti-coincidence low-backggound), have nominal beta-gamma MDAs of approximately p 100 dpm/100 cm , and alpha MDAs of approximately 20 dpm/100 cm.
(
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.. Termination Survey Reporu for Turbine. System (N31)
X The gamma exposure rate measurement instrument sensitivities in the normal. nodes of operation are:
Pressurized ion chamber: 1 #R/hr-Bicron micro Rem meter: 2 - 3 prem/hr.
The detection sensitivity of the pressurized ion chamber can be lowered, if necessary, by using the device in the integration mode.
- The minimum detectable activity for surface beta-gamma measurements is estimated using the following equation: ,
-~
(k-+k,) 5+5 (5.1) t* t*
MDA= '
E where:
k, or ka = Coefficient from the Normal frequency distribution-for the assigned IcVel of significance-(assumes probabilities of type I and type II errors are equal)at the 95% confidence interval, 4
/ S = Sample (plus background) count rate (cpm),
(
B = Background count rate (cpm),
t, = Sample count time (minutes),
tb= Buckground count time (minutes), and E = Instrument detection efficiency, corrected for dptector area, cpm / (dpm/100 cm ) .
The MDAs shown in Table 5.2 are calculated at the 95%-confidence-level. As discussed in the Table 5.2 footnotes,_ these MDAs-represent detection sensitivities under static conditions with fixed geometries. For scanning type surveys, the detection-censitivity is reduced. Threshold or practical detection limits have been empirically determined for each detector used in the scanning mode. This ~' was done via a series of measurements in a scanning mode whereby the detector was passed over ca? ' ated
. sources of various dimensions at an established scanning'spoed to determine an effective' scanning " efficiency". TheLscanning MDAs were then calcelated using equation 5.1 with the scanning efficiency substituted for.E, the efficiency term. These results are shown in Table 5.2 as the values in parentheses.
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, Termination Survey-Report for Turbine System (N31).
- fC)
U Calibration'and Maintenance- Instruments and detectors used in th'e Termination Survey are calibrated and maintained at Shoreham Nuclear Power Station as described in the Termination Survey Program Description and Terminetion-Plan, attached, and according-to approved Station procedures. Detectors for surface' beta-gamma measurements are calibrated using National Institute of Standards-and Technology (NIST) traceable Co-60 sources. Specialized instruments, for example, the pressurized ion chamber, are calibrated by the vendors.
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Tablo 5.1 Termination Survey Instrument Summary D
(V Purpose Type Manufacturer Detector Measurement Description Units ;
(Window area and density) i Direct GM Pancake LND, WBJ and 15.5 cm2 area counts per Surface others (2 mg/cm2 ) minute (cpm)
Beta-Gamma Hand held Aptec 126 cm2 area epm Direct large area GM (7 mg/cm2 )
Surface Hand held Aptec 252 cm2 area epm large area GM (7 mg/cm2 )
Floor Monitor Aptec 756 cm2 area cpm large area GM 3 detectors )
(7 mg/cm2 ) F Alpha Direct ZnS Scint. Eberline 59 cm2 area epm Surface (0.5 mg/cm2 )
I Removable Gas flow Canberra. 2 25.5 cm area epm O surface Beta-Gamma propomonal (Iow bkg.)
Tennelee thin window Removable Gas flo'.v Canberra, 25.5 cm2 area cnm surface alpha proportional Tennelee thin window Gamma Pressurized Reuter Stokes 8 liter sphere pR/hr #
exposure rate lon Chamber Gamma dose Scint. Bicron 1 in. plastic rem /hr rate detector scintillator Multi-purpose Data-logging Eberline multiple detector-survey r eters dependent Background Portable gamma Canberra 3 in. Nal epm and special spectroraeter scintillator measurements Radon levels Radon monitor Niton solid state pCill or working level l 1 l ~
l
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l Tablo 5.2
.I Detector Sensitivities l-Detector Detector Efficiency' Background $ MDA' Window Area (4 x cpm /dpm) (cpm) (dpm/100 :m')
(cm?)
Aptec OM 126 0.04 120 900 (0.02) (1800)
Aptec GM 252 0.06 230 800 (0.06) (800)
Aptec Floor 756 0.05 810 1900 Moriitor (0.05) (1900)
Pancake GM 15.5 0.07 26 1600 (0.03) (3700) g -_..
[N Notes:
- 1. Calibration sources used for these efficiencies are National-Institute of Standards & Technology (NIST) traceable. The sources consist of Co-60 uniformly deposited en a mylar surface (with a thin mylar protective cover).
- 2. The efficiency is determined by counting the source with the detector in a fixed position at one cm from the source.
Efficiencies shown in parentheses are " scanning" efficiencies obtained by moving the detector at 1 to 1.5 in./sec over the source.
- 3. Instrument backgrounds are determined by a 30 minute count.
- 4. Instrument MDAs are calculated using equation 5.1 and the appropriate efficiency, fixed or scanning. Scanning MDAs are shown in parentheses.
Termination Survey Report for Turbine System (H31) 5.5.2 Survey Procedures Instrument operatina Procedures- Each specific instrument used for Termination Surveys has written guidance in the form of implementing procedures for the operations and maintenance of the equipment. These procedures typically address the required pre-operational checks and control functions of the instrument.
Survey Instructions- Each Survey Unit has a comprehensive set of written instructions detailing the required measurements and specific locations. The survey instructions are designed specifically for the measur7ments required in the Survey Unit.
Termination Survev Unit Survey Packaue- Each Termination Survey Unit has a Survey Package prepared for it. The package consists of four components: Survey Instructions; Heasurement Documentation; Supportive Information; and a survey Control Form.
Survev Instructi2Dg- This part of the package provides the instruction for obtaining measurements and identifies the types of measurements needed for the survey. It is provided as General Instructions and Detailed Instructions. The General Instruction f Form provides written instruction for the. types of measurements which must be obtained. A brief description is provided with each
[D (b type of measurement for clarification specific details concerning-the methods to obtain the measurements.
A Detailed Instruction Form provides a summary of the types of measurements and a listing of the information provided on the General Instructions Form.
Measurement Documentation- The Termination Survey Package includes Termination Survey Data Sheets. The Data Sheets list each survey point by number and identify the Grid Map or Component Location.
As each measurement is obtained a check mark, or the actual value of the measurement is entered in the appropriate column of the Data Sheet.
When the "cata-Logger" is used to store the data, the first value for each type of measurement stored should be manually logged on the data sheet. From then on every fifth value is recorded. This manually entered data will be used to validate the data downloaded from the ESP-2 to the Computer Database before the dctabase is appended with the Survey Unit data.
Termination-Survey Report for Turbine System (N31)
[: .
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Exposure rate measurements must be manually logged on the Survey data Sheet. The exposure rate indicated values should be rounded to the nearest whole number and recorded with no decimal point.
In addition to the Survey Data Sheet is a Survey Comment Form. The Comment Form is used to document any comment associated with obtaining survey measurements. The comments provide a written summary of concerns and actions taken to overcome the concerns.
Succortive Information- Included in the Survey Package is supportive information including a Grid Map of a Structure / Outdoor Area Survey Unit or a Survey Map of a System Survey Unit. Grid Maps are designed with a consistent approach to minimize confusion in locating measurement locations.
Control Form- A Survey Control Form is maintained within each Survey Package. The Control Form is used to track completion of the various stages of the Termination Survey for each Survey Unit.
As each stage is completed the individual acknowledges completion by signing the " Performed By:" block of the form. Termination Survey Engineers perform a followup to verify the information and g documentation is present and complete. The Engineer acknowledges j this followup check by signing the "Appr/Verif By:" block.
The Survey Package is tracked using the Control Form until all stages of obtaining data for the Survey are completed. At that ooint the resalts form the survey package are used to prepare a release record for the Survey Unit and incorporate the-data into a '
Termination Survey Final Report.
Eberline ESP-2 Modes of Operation- The Eberline Smart Portable (ESP-2) is a data logging, micro-computer based, portable radiation survey instrument designed to operate with a variety of radiation detectors. The ESP-2 is used with field radiation detectors except the Bicron Micro-Rem Meter,
, The ESP-2s used for the Termination- Surveys are preset by the Instrumentation technicians and color coded for specific uses.
With the detector designated #1 attached to the ESP-2, the instrument is setup for a SCAN measurement. The Anstrument is~in the Peak Trap Ratemeuer Mode so the current rate will be displayed, but only the " PEAK" (highest) value will be stored in memory.
With detector /2, the instrument is setup _ for a FIXED POINT measurement. The ESP-2 is in the SCALER Mode and will request the user to store the value after each measurement.
V Termination Survey Report for Turbine System (N31)
{ \
\~' With detector /3, the instrument is setup to operate as a ratemeter. This Mode is not typically used when performing Survey Unit measurements.
5.6 OUALITY ASSURANCE General Provisions As indicated in the LIPA Decommissioning Plan and in the Termination Survey Program Description, quality assurance for the Termination Survey is subject to the provisions of the Decommissioning Program Quality Assurance Manual. In addition, the Termination Survey Program itself has established quality control measures.as described in the Termination Survey Quality Control Procedure, attached.
5.7 TERMINATION SURVEY SECTION An organization, identified as the Termination Survey Section of the Radiological Controls Division, has been created within the LIPA - Shoreham Decommissioning Project organization for planning and implementation of the Termination Survey. The organization and responsibilities of the Termination Survey Section and the interfaces and responsibilities for other elements of the Decommissioning Project Organization for the Termination Survey are
\ described in the Termination Survey Program Description and the attached conduct of Operations procedure.
6.0 TERMINATION SURVEY RESULTS FOR THE TURBINE SYSTEM 6.1 TECHNIQUES FOR REDUCING / EVALUATING DATA Measurements are converted to the appropriate units for. comparison with release criteria limit values. Surgace activity measurements are converted to units of dpm per 100 cm . These calculations are performed using equations given in Section 8.0 of draft NUREG/CR-5849. Averags values for each survey unit (and/or subunit) are compared with the release criteria values. Confidence intervals are for mean values of each survey unit (and/or subunit) at the 95%
confidence level.
- 6. 2 COMPARISON WITH RELEASE CRITERIA LIMITS The method outlined below is used to demonstrate attainment of the release criteria limits applicable to the turbine.
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Termination Survey Report _for Turbine System (N31).
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6.2.1 Attainment of Release Criteria for Surface Contamination-
- a. Average Surface Fixed plus Removable _ Contamination Individual measurements: Do not exceed 15,000 dpm/100 cm' (contaminated area not to exceed 100 cm' ) .
Population - Upper limit of confidence interval for the mean value is below 5000 dpm/100 cm'.
- b. Removable Surface Contamination-Individual measurements: Do nst exceed 1000 dpm/100 cm'.
Population Upper limit of confidence interval for the mean value is below 1000 dpm/100'cm'.
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Termination Survey Report for Turbine System (N31) 7.0
SUMMARY
The steam turbine system survey results are summarizod in the following table. Presented are the number of measurements; the !
minimum and maximum values for beta-gamma direct (no alpha direct i measurements were made), and removable measurements for alpha, beta ,
and gamma contamination; and corresponding statistics and i criterion. l 4
Summary of Turbine Survey Results beta gamma criterion alpha beta-gamma criterion direct removable removable No of 1091 30 108 2247 30 measurements minimum -588 NA -2 -179 NA maximum 1388 15,000 4 21 1,000 .
(r dpm/100 cm 2 dpm/100 cm' mean 216 5,000 0 -0 1,000 dpm/100 cm 2 dpm!!00 cm2 std dev 304 NA 1 21 NA confidence int 232 5,000 0 0 1,000 UL dpm/100 cm dpm/100 cm 2 satisfies yes -
yes yes -
criteria Based on the above results, the steam turbine system is acceptable for release for unrestricted use.
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Termination Survey Report for Turbine SY8 tem (N31)
APPENDIX A. SURVEY MAPS ROTOR STAGE WHEELS DIAPHRAGM COVER INSETS MISCELLANEOUS
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. Termination Survey Report for Turbine System (N31)
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'O APPENDIX B. SURVEY PROCEDURES SP NUMBER 67X001.01 TERMINATION SURVEY HISTORY FILE, CONTENT AND PREPARATION SP NUMBER 67X001.02 TERMINATION SURVEY PROCEDURE SP NUMBER 67X001.03 TERMINATION SURVEY QUALITY CONTROL SP NUMBER 67X001.04 UNIT TURNOVER AND CONTROL PROCEDURE SP NUMBER 67X001.05 DATA RECEIPT AND MANAGEMENT SP NUMBER 67X001.06 RELEASE RECORD CONTENT AND PREPARATION SP NUMBER 67X001.07 DOCUMENT CONTROL AND FILE MANAGEMENT SP NUMBER 67X001.08 SURVEY UNIT CLASSIFICATION DESCRIPTION SP NUMBER 67X001.09 BACKGROUND ASSESSMENT SP NUMBER 67X001.10 TERMINATION SURVEY DESIGN SP NUMBER 67X001.12 TERMINATION SURVEY SECTION CONDUCT OF OPERATIONS
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