Text

Partially Withheld Final Rept of Ad Hoc Investigation Committee for 870619 Release. Related Info Encl
	ML20236J737
Person / Time
Site:	Point Beach
Issue date:	07/01/1987
From:	Branam T, Gleason H, Knorr J; WISCONSIN ELECTRIC POWER CO.
To:	;
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ML20236J699	List: ML20236J696; ML20236J737;
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	FOIA-87-397 NUDOCS 8708060265
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FINAL REPORT l 1

0F THE AD HOC INVESTIGATION COMMITTEE FOR THE JUNE 19, 1987,_ RELEASE j i

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t i Timothy R. Branas, Chairman James E. Knorr Howard J. Gleason Information in this record was deleted :

in accordance with the freedom of Information Act, exemptions 0 F0lA F 7'"7 ,

July 1, 1987 l

87C9060265 870731 !

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I TABLE OF CONTENTS I. INTRODUCTION

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l II. SUt91ARY DESCRIPTION 02 EVENT III. COMMIITEE ACTIVITIES i 1

1 IV. MANAGEMENT OVERSIGHT AND RISK TREE (MORT) ANALYSIS I A. Description l

8. Conclusions !

C. Recommendations I V. APPENDICES A. Statements B. Question Bank ]

C. Chronological Listing of Facts D. Committee Charter and Preliminary Seport \

E. Completed tMTP 11.30, Associated Tageouts, i Discharge Permits, and Cbem-Nuclear Procedures 1 1

(CWSI DM-0P-015 and 028) l F. Shift compItsent and Station Logs )

G. Event RMS Data j H. RE-220.1&2RE-229 Calibration and Background Information I. EPIP-14 Form J. PPCS Printouts and MORT Chart j i

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1 I. INTRODUCTION On the morning.of June 19, 1987, an event occurred which involved the crossconnection of the chemical and volume control system (CVCS) 1

'and the service water system.

The event resulted in demineralized, diluted On June reactor coolant being released to the circulating water system .

event. 22, 1987,'a special consittee was appointed to investigate the I The committee members werer

7. R. Branam (Chairman), Maintenance Electrical Engineer J. E. Knorr, Regulatory Engineer H. J. Gleason, Training Coordinator The committee cossnenced work the morning of June I

22. 1987. Mr. Zach 1 confirmed his memorandum theofcommittee's June charter and documented the confirmation in 1 22, 1987. The charter is included in Appendix D.

The committee submitted a preliminary report on June 29, 1987.

The final report boa prepared after completion of the' Management I Oversight and Risk Tree Analysis. l The committee chose to include as i much supportive data as practicable as appendices to the final report.

II. S_1MMARY D,ESCRIPTION OF EVENT Personnel Involved in Event-Duty Shift Superintendent (Control Operator')uty Opersting Supervisor j Lontrol C Operator %

" Auxiliary Operator s

hen-Nuclear Technician i On the morning of June 19, 1987, membe a of the operations day shift !

were assigned to complete the discharge of "B" hol up tank in acco 11ance with %4f!'P 11.30, Revision 9, temporary change.

The tes'porsry procedure change was implemented to process the contents of the "B" boldup tank through a serica of Chen-Nelear deniaeraliser e pr. tor to discharge to the circulating water systse.

was complete, lefrP 11.30 required that a 500 gallors flush be performedOnce' the d using reactor makeup water supplied through the Unit'l blender. Due to incorrect manipulation of a CVCS *alve, the flush lineup allowed CVCS letdown water to be discharged to the circulative ' water system.

A chronology of the event is given in the following narrative, and a complete listing of chronological facts is givan t.n Appendie C. !

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'f F2NAL REPORT JUNE 19 6 1987, RELEASE July 1, 1987 Page 2 l

. TIME DATE NARRATIVE

.0700 06/08/37 WIP 11.30, Revision 9, with temporary changes, was first issued for discharge of the "B" WUT on this date. !

.Special Chen-Nuclear demineralisers were obtained for ]

the "B" NUT discharge. ;

These demineralizers were obtained early for use with a WNUT discharge.

0947 06/10/87 The first "B" Hlft. discharge was begun at this time !

(Release Penett No. 87 79). This HVT discharge was }

stopped at 1515 hours0.0175 days 0.421 hours 0.0025 weeks 5.764575e-4 months due to RMS alarms. The Clem-Nuclear beds broke through, as in(,1cated by RE-220 in alert at 1140 and high alans at 1442.

There was a seven-day time lag due to demineraliter bed changes. Changes were considered necessary to attempt to increase demineralization factors.

1003 06/17/87 The "B" HUT discharge was conusenced under Permit No. 87-82. HUT discharge was stopped at 1847 hours0.0214 days 0.513 hours 0.00305 weeks 7.027835e-4 months .

0720 06/18/87 "B" HUT discharge was begun at 0720.

"B" HUT was suspended at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months .

. The discharge of j 06$5 06/19/87

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f as assigned to recommence discharge of "B"

f. He ]was told to read the controlling procedure WTP 11.30 prior to starting the discharge. i 070006/19/87[ .has informed of the intended discharge b '

j 1 . ,fromthePAB.Thedischargepermitrequired -

10-50 1pm through RE-220. i j

0720 06/19/87 "B" WUT discharge was restarted.

0720 06/19/87 h ,[,", Encountered difficulty pumping the last portion of "B" NUT to the contractor desineralizers. P9 j

was cavitating. <

his influent by The contracto' was dire ed to throttle his P9 recirc va[lve' completely.

"E l,,1 ~ 7'kslecclosed Due to the i ased l pressure drop at the throttled influent valve i found it necessary to throttle the 650 SW supp va C ]lve -

1 to the spent fuel pool heat exchangers (allowed per Step 4.4.14 of MffP 11.30). He then opened the 660 and ;

661 valves wider to further reduce service water back pressure and maintain spent fuel pool heat exchanger '

cooling flow. Valve 650 was two to three turns open at that time, valve 660 was wide open,'and valve 661 was ,

4 partially open. These two actions unintentions11y virtually no flow conditions through RE-220.

C~i ' id look at the sig tglass in testion for

('.'sulted

-220. owever, unknown to g r-" the fispper was stuck in the up position (indicating flow cxisted). -

' FINAL REPORT - JUNE 19, 1987, RE1. EASE July !, 1987 Page 3 TIME DATE 1 WARRATIVE l

0829 06/19/87 The discharge of ('s" NUT was stopped since the tank was 1 empty. i P9 was stopped and BS-1126, CV-1119, CV-1112 were '

shut, and valves on Chem Nuclear demineralizers were alse tt:rottled. i 0830 06/19/87 Th lineu r the flush of the diseberge lines was made b

a per WifrP 11.30. The control operator FCV-110A. The borie acid integra'.or clicked several times. The control operator's conclusion was l

that berie acid recirculation Pump,1-PS26 was pumping boric acid through 365 via 1FCV-110A. !

1 0830 06/19/87 The contractor was informed by the A0 that the flush I would be performed with elean water. The contractor j

then proceeded to bypsas the deafneralizers for the flush evolution.

0835 06/19/87 read Step ee as told by

%.22 that that to M]

would w ter for fl Q ng th disc rge line.

and independently referred to the CVCS P&lD for etter unders tandirs of the flowpath. i 1CV-361A was shut, and 1-365 opened. 2RE-229 read l

-1.32E 06 pCi/cc and was in the normal status. '

0840 06/19/87 asked the Unit I control operator to start the P.tfD pump and asked the open the discharge valve, -Nuclear technician to by placing the control to started the blender intending to close 1FCV-110C, closed 1FCV-111ute'and start. F M ]

inadvertently.

0842 06/19/87 ITCV 110C was open at this time, releasing letdown directly to the service water system.

0845 06/19/87 RE-220 equaled 9.17E-04 pCi/ce, normal.1RE 229 equated 6.921-07 pCi/ce, normal. 2RE-229 equaled 1 11E-05 pct /ce, normal.

0846 06/19/87 2RE-229 reached alert status, as to valve 'ineup and flow ra was S.estioned '

was

informed that the demineralizers were bypassed. All concerned felt that the alert was due to the bypass condition.

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TIME DA_TE_ NARRATIVE 0850 06/19/87 2RE-229 reached a bigh alars due to noble gases in the effluent streas. A control room discussion resulted and attributed the alarm to possible excessive flow or water from a formerly dead leg of piping.

0851 06/19/87 1RE-229 went to the alert state. was told to shut ICV-365 to secure the flush.

0852 06/19/87 A VCT level decrease was noted on ICO3 trend by ( M 1 This was confirmed by checking IC04 and the PPC5' trend page, m

0854 06/19/87 to secure the flush.

Aa ti-5 calle ff the pump calle be Unit 1 control operator to shut ask the Chem-Nuclear technician to shut valves. 6 turned off the RMU pump'. % )

returned the b ender ontrol switch g auto and start; therefore, IIcV-110C closed. { M Jopened 1FCV-111.

0$$5 06/19/87 1RE-229 equaled 1.5E-05 pCi/ce, normal. 2RE-229 equaled 3.85E-04 pCi/cc, high alarm. RE-220 equaled 9.47E 04 pC1/ce, normal.

0855 06/19/87 A discussion was held among the DSS, DOS, an The conclusion reached was that letdown was (rel service water via if -110C and ICV-365. Control instructed o close ICV-365.

0858 06/19/87 2RE-229 began a trend down. verified and locked shut both spoolpiece valves leading to the special demineralized setup.

0900 06/19/87 informed HP and the Chen-Nuclear technician at e ush evolution was on hold.

0905 06/19/87 1RE-229 equaled 1.24E-05 pCi/cc, normal. RE-220 equaled 9.31E-04 pCi/ce, normal. 2RE-229 equaled 1.65E-04 pCi/ce, normal.

0910 06/19/87 consulted EPIPs. It was estimated that 235 ga one o letdown was released based upon the drop in the VCT level., A more likely amount was 160 gallons, which tecounted for the amount left in the piping.

0915 06/19/87 retarned to control with the procedure. HP performed's survey of the flush piping. RE-220 equaled

').23I-04 pCi/ec, normal'. 1RE-229 equaled 3,49E-06 pCi/ce, normal. 2RE-229 equaled 3.99E-05 pC1/ce, normal.

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0922 06/19/37 An Unusual Event was declared and de-escalated. 1RE-229 equaled 1.04E-06 pCi/ce, normal.

0954 06/19/87 NRC was notified. !

0700 06/24/87 RE-220 was decontaminated by a factor of 2 but was still ,

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III. COMMI"TTEE ACTIVITIES l

1. The first meeting of the consittee was held on June 22 a'.1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months . Mr. J. C. Reisenbuechler and G. J. Maxfield participated i

in setting the scope of the committee's investigation. The i remainder of the day was spent collecting documents, procedures, i permits, P&lDs, and written statements from the parties involved. '

2. On Tuesday, June 23, the committee reviewed the documentation and began the discovery process by building a chronologic .1 event data base and a questio bank. Interviews were held with ,

M. D. Mozaman, and [

'at the Site Boundary Co roi Center. 1 An event and causa- factor thee line was begun during the morning.

A detailed review of the procedure with correlation to the appropriate P& ids was completed. Mr. N.' Rand presented a short, detailed description of the boric acid b1 coder, valve, and pump interrelationships, i

3 On Wednesday, une 24, in rviews were held wit at i l

the ytant and -

, . at the Site Boundary ntro; Cedfer. l The two data ases contai og the facts and time line for the 4 2 vent were completed to the point where ressining outstanding !

questions could be identified. A detailed chronology of events was constructed based upon the facts known at the time. Those facts which could be verified were verified, and those that could not be verified were flagged for further resolution. -

R. J. Bruno, T. O. VandenBosch, and T. L. Ross were also contacted in Training for various pieces of information. C. Gray, G. Schleis, and G. J. Maxfield were' also queried.

4. on Thursday, June 25, L. J. Kamyszek was interviewed concerning '

the overall use of the procedure to control e work.,_ T_ his tory of the systems involved was also discussed. ______, ad M. D. Mosesan were consulted to clar fy vari s' outstand a questions. Chem-Nuclear technician . ~~ was inte rviewed to obtain information on the operation ol^t a specisi deafneralizer during the NUT discharge and flush evolutions. Committee members completed the first draft of the preliminary report.. The committee also began a detailed Partial MORT Analysis.

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5. On Friday,' June 26, the coussittee completed the MORT analysis and -

the preliminary report. Work was also begun on the final copy of the facts, the conclusions based on those facts, and the writing .;

of the final report. T. Tearpock was consulted for verification of various facts based upon PPCS computer loss. i

6. On Monday, June 29, the committee issued its preliminary report I and began work on the final report. An interview was held with l Mr. C. Gates. Recosamendations were draf ted based on 'the j conclusions reached from the facts. i

7. A presentation of the preliminary report was made to the Offsite Review Coassittee on June 30. A draft of the complete final report was assembled for review by the investigation committee.

IV. MANAGEMENT OVERSIGHT AND RISK TREE (NORT) ANALYSIS.

A. Description The inadvertent release of radioactive material into the 4 circulating water system which occurred on June 19,.1987, at i P8NP, was investigated using the Management Oversiaht and Risk !

Tree (MORT) technique. Facts were gathered from various. plant i process systems. Written statements were taken, and interviews were held with personnel involved in the event and personnel knowledgeable in the systems involved. Sixteen conclusions were.

reached supported by over 140 fsets (Appendix C). .Each fact was verified by the sources listed above. Fourteen recoassendations :

are provided. . A cross-reference matrix of facts, conclusions and recommendations is given in Table l. All materials and parent documents gathered or generated during the investigation are on-file at PRNP.

One fact that struck the cossaittee during the investigation was the professional manner in which all those involved conducted themselves during the event and~during our investigation. The overall emphasis of everyone was to get to the root cause of the matter by making sure the committee had all the facts concerning the event and the systems involved in the event.

It should be emphasized that a complete HORT analysis was not !

conducted for this event. -After the events and causal factors technique was used to scope the incident and help focus on the '

possible causes for the event, only those sections of the NORT tree which showed promise of producing a meaningful product were used.

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-July 1, 1987 Page 7 The MORT analysis identified six barriers which could have prevented the release of radioactive liquid to'the environment:

1. Operations procedures

2. Direct supervisica

3. Radiological monitoring system

4. Training ,

5. Personnel actions

6. Engineered protective functions It should be noted that during the discharge of the holdup tank and the subsequent flush of the lines used, the operator and his control of one valve was the only barrier between the reactor coolant systen and the lake. This fact was not known -to the i

operator. See Figure 1 for the discharge and flush flowpath. i In this event all six barriers failed fully or ic part. All of the conclusions and recommendations are related to the failure of I these barriers. The committee concluded that had these l reconnenistions been implemented collectively or individually, the '

event could have been prevented.

5. Conclusions Procedural Deficiencies 1

1. WMTP 11.30 gave incomplete detail for a safe method of flushing the discharge lineup.

2. WMTP 11.30 did not provide precautions for consequences of incorrect valve alipament.

3. The technical review of WWTP 11.30 does not appear to have included a complete review of the interaction of the flow levels and pressures between systems. A review of the effect of the throttling of SW-650 and the operability of RE-220 does not appear to have occurred. The evaluation of the consequences of valve miss11gament with a pressure differential between the letdown portion of the CVCS system and that portion of the CVCS being used for the discharge, does not appear to have occurred. That is, IFCV-110C had not been considered as a boundary valve between letdown and the service water system. ,

4. Twenty-six pen and ink changes were made to this procedure, resulting in less than optimal readability and flow.

Trainium Deficiencies

5. Operators are not trained concerning the consequences of valve mispositioning during abuormal lineups.

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6. It is not common knowledge that there is no low-flow alarm on RE-220. This is based on discussions with four Sk0s and one RO as well as training personnel, l

7. Operators are not aware of the interrelationships of positioning of service water supply valves to the spent fuel pool heat exchangers and their effects on flow through RI-220.

8. Blender operation has been defined as a procedure adequate task.

However, use of the system for non-unit related tasks is not {

proceduralized, j i

Equipment /Systes Deficiencies l

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9. RE-220 has an excessive length of piping in its supply flow path and is sized such that operability under certain service water system conditions is suspect.

10. !

The RE-220 installation is not conducive to easy decontamination ;

by Health Physics personnel. As a consequence of flushing .

difficulty, when RE-220 does become contaminated, it remains so I for an extended period of time. This necessitates alert setpoint l

ebanges which approach alarm setpoints due to spurious alert alarms. i This in turn results in lack of RE-220 alarm credibility in the '

minds of the operators. Therefore, operators consider RE-220 to be only a crude indication of service water radiological. conditions.

Additionally, the alarm setpoints for RE-220 appear to be low such that upon an alarm on RE-220, little or no indication is received on 2 or 1RE-229. The lack of an RE-220 alora prior to or concurrent with 2 or 1RE-229 alarms contributed to the leasth of discharge.

The operators were not certain of the discharge source.

It should be noted that if the gas stripper had been on line, the tie of the CVCS to service water system may not have been discovered until either the downward trend in the VCT level ww-observed or an actual VCT low level alarm was received. This is because 1 and 2 RE-229 would not have alarmed with noble gases removed from letdown. 3 j

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11. The speciel discharge flange location on the service water heat anchanger inlet header is in a location which promotes the collection of discharge particulate mattee in the heat exchangers. -

The flange location is also in an area which requires an operator l to work off a step ladder or set up scaffolding for the flenge l spoolpiece and hose connections. Reference Modification 83-125 l installing service water flange. '

12. An automatic valve actuated by an RMS (RE-220) monitor would have sitigated the release.

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13. RE-220 requires some DP across SW-660 and SW 661- . The present flow iridicatoc for RE-220 is inadequate.

Personnel Perforisance

14. .The control operator considered the operation of 1FCV-110C as strictly routine.and did not verify valve positionsfaiter his actions. The control operator should not have considered the CVCS valve lineup as routine.

15. The control-operator is expected to perfore sultiple complex tasks-in the same time frame. IA steam generator level control troubleshooting detracted from the attempt to close 1FCV-1100.

The. stese generator level control system was of primary importance to the operator at this time.

Supervisory Communications

16. A pre-job discussion was not conducted between the A0 holding the procedure and the control operator on the job. A copy of the discharge procedure was not available in the control room for reference by control room personnel. A discussion did take place between the auxiliary operator and the DOS.

It should be noted that during the procedure implementation .the control operator and auxiliary operator did consult prints independently to ensure that the proper lineup was being considered.

The control operator asked the A0 to read some of the steps verbatie over the phone.

C. Recommsendstions

1. Ensure that all future discharge fivwyeths provide for automatie isolation initiated by appropriate RMS input. MORT 44.c21.c22.c25, 19.b2, 33.c13, 17.c5

2. Reevaluate the location of the service water flanged influent connection to determine the extent of heat exchanger contamination..

Include the personnel safety aspects of having to install a spoolpiece and hose at this flange. MORT 49.c40,c43, 46.b11.

3. Include in Modification 85-067 an evaluation of the adequacy of sample flow to the RE-220 det6ctor well and the present method of flow indication if future plant. discharge flowpsthe are to employ RE-220 as a radittion monitor. HORT 49.c39 c41,c40, 25.c1, 49.c42, 25.c2.

.5 FINAL REPORT - JUNE 19, 1987, RELEASE July 1, 1987 Page 10 1

4. Add a " flush" position to the blender control switch if continued use of the CVCS blender is intended for discharge purposes. In addition, hardpipe the interconnection and implement appropriate administrative and procedural controls. The modification process should consider the desirability of crossconnecting the CVCS and service water systems. That is, evaluate installation of a discharge header which then interfaces between plant process tanks and the service water system. MORT 49.e42, 29.b3, 19.c2. :

5. Where two process monitors are utilized in series for discharges, adjust the upstream monitor high alarm setpoint to closely correspond with the alert alarm setpoint of the downstream (discharge) monitor. This should improve the credibility of 4

upstream monitor indications and alarms. MORT 17.b3, 44.c23, '

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6. teinforce the importance of pre-job discussions, particularly for non-routine procedures. MORT 30.c10, 29.c8, 29.e2. 1

7. Provide multiple copies of a procedure with the master copy remaining in the control room during the course of procedure implementation. MORT 18.b3, 33.c13, 47.d18,d12.

8. Include an independent engineering review of new procedures and procedure revisions in the present review process. MORT 41.el,c15, 42.c3,c4.

9. Reinforce procedure precautions and limitations by restating them I immediately before the applicable step (s) in the procedure. MORT l 47.d18,d12,d14, 49.d15.

10. Review training materials for non-routine operations and include precautions where applicable. Where existing saterials do not discuss non-routine operations, these materials should be upgraded.

MORT 33.e15, 48.c36.

11. Revise the control operator training program to ensure that non-routine use of the CVCS blender is clearly presented and evaluated. MORT 33.e15, 48.c36.

12. Cancel MfTP 11.30. Review and implement the four draft procedures presently under development by Crew A to replace WMTP 11.30. -

Additionally, ensure that CV-1100, as a minimum, has its control switch red tagged closed during future discharge lineups.

M0kT 47.d18,412,414,d16, 47.c23, 17.ct , 18.b3, ' 47.d17.

13. Train licensed operators on the interrelationship between S9 supply characteristics, STP beat exchangers, and the operational characteristics of RE-220. MORT 49.c42, 33.e15, 48.c35.

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Page 11 1 14 Evaluate the adequacy of shift complement for the' implementation of non-routine evolutions,-i.e., provide additional personnel to assist in the monitoring / performance of non-rvutine evolutions. ,

MORT 34.e22, i

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3UMt1ARY OF OPERATIONS. INCLilDING SIGlJIFICANT PLAf4T EVENTS:

I n ad ver t en t li qtti d rel eane into Lake Michigan - Preliminar y l Notificatiott issued.

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rmu J. J. Each DME June 24, 1987 j

tuotet WEEKLY

SUMMARY

REPORT - POINT BEACH NUCLEAR PLANT PERIOD JUNE 17 THROUGH JUNE 24. 1987 I J

@vTo J. W. Boston, R. W. Britt,-Sol Burstein, C. W. Fay, A. M. Gemer, !

J. H. Goetuch, G. M. Krieser, E. J. Lipke, R. A. Nuwton, )

.K. E. Wolters, J.-J. Each l

}

Unit 1 operated at approximately 496 MMe n61 throughout the .)

period with no load reductions. Evaluations have indicated the 1 prencisture separator modification has caused no notable increase j

'in plant efficiency. Pri6hry-to-secondary leakage was stable at. l a detect.cble rate.' l Unit 2 operated at approximately 497 MWe net throughout the period with no load reductions. Primary-to-secondary leakage was less than ten gallons par day. Unit'2 surpassed 53 billion i kWhz on June 17. ;

The effici.ency and generation output of both units have diminishfid clight,1y due to warmer lake temperatures.

On June.19 an Unusual Event was declared when 160 gallons'of ,

radioactive coolant frbm the Unit 1 letdown system was. released l to Lake Michigan via the Unit 2. service water system. Although 1 l initial quantifications of the radioactivity released indicated '

that radioactive release limits were exceeded, it was determined f rom subsequent sdnpling that the actual radioactive release citly amounted to about three percent'of the release limit.

Investigations are underLway to determine the causes for the improper valve lineup which initiated the event.

On June 24, 3D emergency diesel failed to start during a bimonthly test when' operators failed to " valve in" starting air after checking the engine turnover. The diesel started succecafully af t er the air valve was opened. a contractor. work-performni during the period included continued hesith physics, training., and modification engineering support work, insulation r?ork, Appendix R modifications, Unit 2

~

prmnoisturp separator modification preparation work, and ,

p' ppg,7gponstructionofthenorthservicebuilding.

ihere are approximately 108 contract personnel on site. Fo2 4-17-39/ '

'J P (i fir 7 -

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!- t at ,104 2994 L _

m

i I

l liARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unft Name Point Beach Unit 1 Date July 3, 1987 Completed By C. W. Krause Telephone 414/221-2001 1

Unit I commenced the period at 20% power in a post refueling {

condition to acclimate the turbine.for overapeed testing. On 1 June 1 at 0103 hours0.00119 days 0.0286 hours 1.703042e-4 weeks 3.91915e-5 months , the generator was taken off line to conduet overspeed tests and it was returned to service 25 minutes later.

The unit was administrative 1y restricted to 38% power for the next two days while operations improved the secondary system water chemistry. Power was ramped to 88% (approximately 435 MWe) to condition the nuclear fuel for another two days. The unit achieved post-outage full power, approximately 195 MWe, for the a' first time on June. 7. It continued at that power level to the end of the period.

On June 19, an Unusual Event was declared when 160 gallons of radioactive coolant from the Unit 1 letdown sys tem was released to Lake Michigan via the Unit 2 service water system. Although initial quantifications of the radioactivity released indicated that radioactive release limits were exceeded, it was determined from subsequent sampling that the actual. radioactive release only '

amounted to about 3% of the release limit. Investigations are underway to determine the causes for the improper valve lineup which initiated the event.

On June 24, 3D emergency diesel failed to start during a bimonthly test when operators failed to " valve in" starting air, after checking the engine turnover. The diesel started successfully af ter the air valve was opened. .

l Maintenance completed during the period included-repairs to "B" main feedwater regulating valve controller.

, * * * * *

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4 4 * * :4 PO10T BEACH DEMiNERALI ZER F).U5M LINE LAMPLE SAMPLE DATE: X-JUN-97 13:00:00 SAMPLE IDENTIFIf7 1C,N: 97-253 g, 5 d "^ '

TYPE OF SAMPLE: LIDUID SAMPLE OUANTITY: 40=.'.0000 gUNITS: ML

]

SAMPLE GEOMETRY: L1SOO EFFICIENOV FILE NAME: VANEFF.L1500 , I

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i ACQUIRE DATE: 26-JUN-87 A. . ': 44

FWHM(1332.> 2,299 ;

P; RESET TIME (LIVE' 900 :.EC

SENSITIVITY: 5.000 ELAPSED HEAL TIME: 90T. SEC

SHAPE FAPAMETER : 10.O % 1 ELAPSED LIVE TIME: COO. SEC +- N5r< ITERATIONM 10, 4

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DETECTOR: NRC GE 80 :+ LIBRARY: 0JUCL . MA 5 TER CAL'iB DATE: 26-JUN-07 10:30 59

ENERG'i TOLERANCE: 0.900KV I KiiV/CHNL : 0.4599891 4 HAL F- LIFE RATIO: 6.00 i OFFSET: O . 38 .7 30e. KEV + ABUNDANCE LIMIT: 80.00% l

0. COEFF. : -1.467E-07 KEV /C4+2 4 )

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f 1 511.46 1687. 6B5. 2.79 1111.08 1101 2c 1.37E 00 B.2 2.96E 00

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i PUL5E-PILE--UP C0FREC TED DAT A. CORRECTION = 1.001 l UrKDRP. LIVE TIME: DOO.CORFECTED LIVE TIME: 8*%.

PV IT ENERGi ARE4 BUGNE CWHM CHANNEL LEFT PW C T 5/5EC %ERF 1 1 V.. 77 b. r. . . .~. ~ % C. . . .' . M. b..sc . D. b.. ". 9 1 .~.' e' . ~/ 4 E - n. 1

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.i x. i.i . 4 c.. s s. i . e.,1 9 . 1. . n. . A g e.,. c. 4 s..a. n-. l . (. 11E -4.1 . 'v' . S, 8 1 391.'/9 165. 404 2.07 851.36 847 13 1.84E-01 2o.~

9 1 oc '. 45 3 c. 3 . 471. !.86 10B0.67 10"? I5 4.37E-01 13.7 10 1 511.4,i le87. 685, 2.79 1111,09 1101 24. 1.88E 00 E.2 11 1 <-

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13 1 756.90 450. 231. 1.84 1644.71 1635 17 5.01E-01 9.6 14 1 765.89 72'G: . . 19. 1.97 1664.26 1655 17 8.10E-01 6.3 15 1 810.89 3573. 237. 1.93 1762.11 1752 22 3.93E 00 2.!

16 1 874.8? 136. 125. 2.39 1814.15 1809 11 1.51E-01 19.I 17 1 884.52 73. 3.12. 1.73 1922.20 1918 10 S.14E-02 29.9 3 ;:..

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NUCulDE LINE ACTIVITh PEPORT '

PAGE 1 ELAPTED LI;/E TIME: 899. (PILE- UP C ORREC1ED)

F13$10N GA9 l 1 5IGMA NJCLIDE SBHF ENERGi AREA BPGND %ABN */.EFF UCI / UNIT ERROF KR-88 FG 1 h. 32 0. G. 26.00+ 0.000E-01 0.000E O 0.000E 0 534.83 13L. 125. 13.00 3.485E-01 4.096E 5 7.829E 4 1529.77 0. O. 10.90 0.000E-01 0.000E O 0.000E 0 2195.84 0. O. )3.20 0.000E-01 0.000E O 0.000E 0 2392.11 0. v. 34.,60 0.000E-01 0.000E 0 0.000E 0 KE-133 FG 90.99 16622. 4 1 3 e.. o;.704 1.202E 00 4.829E -4 5.757E -s 1 1

l AC T I VAT I Ot' PRODUCT l

\

1 SIGMA !

NUCLIDE SENR ENERGY AREA BUGND %ABN %EFF UCI / UNIT ERROF -j F-18 AP 511.00 JA87. 685. 96.734 5.344E-01 2.088E 11 1.078E 10 l CR-51 AP 320.08 551. 519. 9.834 8.076E-01 5.772E -5 5.461E -e MN-54 OP B34. c:3 136. 125. 9'".98+ 3.485E-01 2.960E -6 5.656E ~7 CO-58 AE 810. / e, 3533. 237, 99.404 3.573E 7.780E -5 1.603E -6 '

CO-60 AP 1173.22 1918. 83 100.00 2.618E-01 5.516E -5 1.464E -6 1332.45 1759. 12. 100.004 2.357E-01 5.e19E -5 1.407E -d AG-110M AP 657.75 0. 0. 94.40+ 0.000E-01 0,000E O 0.000E 1:

677.61 0. O. l ' :' . 68 C.000E-01 0.000E O 0.000E !

I e.86.99 0. O. 6.47 0.000E-01 0.000E O 0.000E O i 7 0c . 6 ~' O. . 12.6G 0.000E-01 0.000E O 0.-000E / l 763.9:. v. "% v.000E-01 0.000E 0 0.On0E 0 l 518.02 0. '.

7.30 0.000E-01 0.000E O ~0.000E G l 884.67 73. 112. 72.60 3.317E-01 2.310E -6 6.910E -T I 5.37.48 0, 0. 34.27.. 0.000E-01 0.000E- 0 0.000F ^ '

1384.27 0. O. 24.26 0.000E-01 0.000E O 0.000E 0 1505.00 0. O. 13.06 0.000E-01 0.000E O O.000E O M4LG1EN PI:5ICN FRODUCT j 1 LIGMA NUCLIDE 5BHF ENEPGY AREA BUGND %ABN *<.E F F UCI / UNIT ERROR I-134 WFP 5:/5.36 0. .. 11.40 0.000E-01 0.000E 0 0.000E O l 221.~9 0. O. 10.60 0.000E-01 0.000E O 0.000E 0 i 1

84 , . v 3 v. ?. 95. 4 ) v 0.000E-01 0.000E O .000E 0 ;

..0. 4 . v. .~. -.

/2 1 1.,. e ...c. w o.:.4 - E-v1 4. o .. 6E , ,-

1 -..E-av:

1072.55 0. O. 15,30 0.000E-01 0.000E O 0.000E ^

1 FISSION PRODUCT 1 5IGMA NUCLIDE SBHR ENERGY' AREA BRGND %ABN %EFF UCI / UNIT ERROR 2R 05 FP 724.18 425. 179. 43.70 3.939E-01 1.937E -5 1.706E -6

756.72 430. 231. 55.304 3. 792E--01 1.6855 -5 1.625E -6 NE-95 FP 765.79 728. 219. 99.81+ 3.753E-01 1.582E -5 '1.001E -6 RU-103 FP 497.08 393. 471. 89.004 5.477E-01 6.502E ~6 8.633E -7 610.33 0. G. 5. e.0 0.000E-01 0.000E O 0.000E 0 RU-105 FP 316.50 0. O. 11.70 0.000E-01 0.000E O 0.000E O 469.40 0. O. 17.50 0.000E-01 0.000E O 0.000E 0 676.40 0. O. 16,70 0.000E-01 0.000E 0 0,000E O 724,50 425. 179. 49.00+ 3.939E-01 6.035E 1 5.314E G

NUCLIDE LINE ACTIVITY REPORT -PAGE 2 ELAP5ED LIVE TIME: 890 . (F ILE-UP CORRECTED)

FISSION :'RODUCT '

1 SIGMA NUCLIDE SBHF ENERGi AREA E4GND %ABN %EFF UCI / UNIT- ERROA

$N-123 CP 255.12 0. O. 1.93 0.OOOE-01 0.000E O O. OOOE- 0 391.69 165. 404. 64.904 6.765E-:1 2.901E -6 7.79iE -7 BA-13: -P 81.00 16622. 4136. 33.00 1.202E :O 3.154E -4 T.760E -6 302.84 0. O. 17.80 0.OOOE-:1 O.OOGE O O.GO0E /

35c. , 00 O. O. 60.00* 0.000E-01 0.OOOE O O.GOOE 0 CE-141 CF 145.44 55?. 766. 48.404 1.417E 00 6.677E -6 6.'981E -7 CE-144 FF 80.11 O. O. 1.60 0.000E-i:1 O.OOOE O O.000E O 133.54 503. 620. 10.804 1.456E 00 2.426E -5 2,461E -s.

l i

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O

UNKNOWN LINE REF0FT PAGE 3 ELAPI.ED LIVE Tif1E 899. (PILE-UP CORRECTED)

LINE9 NOT LISTED IN LIERAR'r Pt:: IT- ENEPGV AREA BKGND FWHM CHANNEL LEFT. PW CTG /SEC 74 ERR %EFF i 1 30.73 6 0 '.: . 2390. 2.04 65.96 59 12 6.74E-01 16.6 0.OOE-01 2 1 35.22 3 c. ' . 1469. 1.60 75.73 71 10 4.11E-01 20.4 0.OOE-01 e 1 159.3G 2:1. 755. 1.78 345.64 339 12 2.91E-01.22.8 1.36E 00 11 1 696.53 60. 287. 2.03 1513,46 1503 18 6.71E-02 67.7 4.07E-01 LINE5 NOT MEETING $UMMARi CRITERIA FF. NUCLIDE ENEFGv HALFLIFE DECAY UCI / UNIT ABNDIFF FAILED 3 B A-133 61. O': 1.050E 01 1.OO1E O 3.154E -4 29,78% ABN 10 F-13 511.00 1.097E O2M 8.508E 15 2.088E 11 100.00% DC'.

12 RU-105 724.5' 4.440E OOW ?.64*E 6 6.035E 1 51. 63.' DCY , ABN 14 F .R- 95 834.ST :.84CE COH 1.816E 10 4.096E 5 13.31% DEY,ABN .,

17 AG-110M 984.67 . 499E O2D 1. 01.1 E O 2.310E -6 24.05% ABN l 17 I-134 554.07 5.260E 0)M 1.715E 33 4.356E 27 32.96% DC'.*'BN I 1

I 4

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E.UMMAPN OF NUCL.IDE AC T IVITY PAGE 4 TOT A!, . LINES IN SPECTRUM 19 j LINE5 NOT tI5TED-IN LIBRARY 4 .k IDENTIFIED IN SUMMA;i REPORT 13 68.425 l

'l i

FISSION GA?

1-SIGMA NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR % ERR XE .133 FG 1.259E 02H 1.704 4.329E -4 5.757E -6 1 19 .1

)

{

i ACTIVATION PR0 DUCT ,i 1-51GMA j NUCLIDE SBHR HALFLIFE DECAY UCI / UNI ~ ERROF % ERR l CR-51 AP 2.770E 01D 1.106 5.772E -5 5. 461 E -6 9.46 i MN-54 AF 3.127E 02D 1.009 2.960E -6 5.656E -- 7 19.11 {

CO-56 AP 7.080E 01D 1.040 7.780E -5 1.603E -6 2.06 l CO-60 AF 1.925E 03D 1.001 5.619E -5 1.407E -6 2. Su 1 l

FISSION PRODUC~

1-5IGMA NUCLIDE 5BHR HALFLICE DECAV UCI / UNIT ERROP %ERE ZR-95 FP 6.402E 31 D 1.035 1.685E -5 1.225E -6 9.65 NB-95 FP 3.50sE 01D 1.093 1.582E -5 1.OO1E -6 6. 33 PU-103 FP 3.935E 01D 1.074 6.502E -6 8.633E -7 13.28 1

$N-113 FP 1.151E O2D 1.025 2.901E -4 7.799E -7 26.89 l CE-141 F; 3.250E 01D 1.090 6.6 7E -6 6. 4:1E -7 10.45 CE-144 FP 2.843E O2E' 1.010 2.426E -5 2.461E -6 10.15 1

1

. g .c + + 4: + + . 4 * +:+ 4 4.

26-JUN-87 15812:09 *****+****+++**++-

- :* o .S 47.# *

4. r * + + + + + + + + + + + + + + + + + .c * * + + 4: * * + + + *

e 4 + + + + w+ n + + + + * * * + +

POINT BEACH DEMINERALIZED FLUSH LINE SAMPLE RECOUNT SAMPLE DATE: 22-JUN-87 ' 13: 00; 00 -

- SAMFLE. IDENTIFICATION: 87-253 TYFE OP. SAMPLE: LIQUID

'/' M " ,.

SAM"LE OUANT ITY: E ^'? MN,. g -

UNITS: ML-SAMF LE GEOMETR < : L1500 .

j EFFICIENCY FILE NAME: VANEFF.L1500.. !

.++++ n ,e++$4++ ,#44+ n # ,$4::e+ n $ o n 4:4.n+, $$ ++ + 4.#,$ $ ##:4 ,# # ##:#uS 4

ACQUIRE DATE: '26-JUN-87 14: 10:38

FWHM(1332) 2.299 PRESET TIME (L.IVE): 3600. SEC 4 SENSITIVITY: 5.000 l ELAPSED REAL TIME: 3615. SEC

SHAPE PARAMETER : 10.O % l ELAPSED LIVE TIME: 3600.-SEC

NBR ITERATIONS: 10.

4

- - - t*4:*:+ 4 4+*+4 444 g+4 ++4 44:+ +y4 4+ 44 44 *44 444 4444444 44 44444 44444 DETECTOR: NRC GE 80 4 LIBFARY:NUCL.MASTEF l CALIE DATE: 26-JUN-87 10:30:59

ENERGY TOLERANCE: 0.900KV KEV <CHNL: C.4590891 + . HALF LIFE RAT 10: 8.00 OFFSET: 0.3867306 VEV 4 ABUNDANCE LIMIT: 80.00%

0. COEFF. : -1.467E-08 MEV/C**2 4

+

4 t a +.* 4 ;4 t:, :+:.r*4 :< 4 4 4 4 + :+ 4 4 + ++ + 4 4 0 4.+ .,4 4 4 :ygg 4 4 4 9 4 4 n 44 f:gg 4,.# 44 4 4 4 4;4 4

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s.4.4 + 4.:4+ + 4 4 + f:4 ., $ 4 4.4.:44 444 p44 p44.p 4: p4 44.p p 7444 4f 4 44 SPECTR,lM FILE NAME: SAMPLE.PBDEM1 .

+:4 e r4 *.c u+ +$ , u .:4.ut v e4: :$4 $ n u tu St e-p e n,ucen u et y ,n4. y g t I

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9 C____________________

PK,2T ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 1 1 30.70 1383. 7372. 1.74 65.90 62 9 3.84E-01 11.7 1.36E 00 2 1 35.14 1205. 5933. 1.78 75.56 71 10 3.35E-01 12.6 3.35E-01 3 1 63.53 637. 8767. 1.53 137.26 134 7 1.77E-01 24.5 s.49E-01 4 1 81.26 66655. 16331. 1.44 175.83 167 17 1.85E 01 O.6 3.84E 01 5 1 133.81 2155. 3902. 1.55 290.06 283 14 5.99E-01 6. 6 7. 79E-01 6 1 145.78 2499. 3434 1.46 316.08 309 13 6.94E-01 5.3 2.36E 00 7 1 159.27 940. 2586. 1.68 345.41 341 11 2.61E-01 11.1 1.25E 00 8 1 320.46 2140. 2551. 1.52 695.85 689 15 5.04E-01 5.6 1.90E 00 9 1 392.05 365. 1317. 1.49 851.48 847 10 1.01E-01 19.4 3.66E-01 10 1 49/.oo 1681. 1527. 1.60 1080.37 1075 12 4.67E-01 5. 3 1.77E 00 11 1 511.48 6628. 2604. 3.03 1111.15 1100 21 1.84E 00 '2.3 5.87E 00 '

12 1 602.86 305. 1565. 1.92 1309.80 1304 12 8.47E-(2 26.5 8.01E-01 13 3 657.97 405. 829, 1.63 2 14'9.62 1421 24 1.12E-01 14.5 7.95E-01 ,

14 3 661.62 236. 841. 1.88 1437.57 1421 24 6.55E-02 26.2 15 724,35 16 1

1 756,84 1494.

1814.

754.

752.

1.88 1.88 1573.95 1644.58 1566 1438 15 15 4.15E-01 4.9 1.14E 00 5.04E-01 4. 3 2. 42E '0

)l 17 1 765.95 2812. 909, 1.85 1664.39 1656 17 7.81E-01 3.1 1.08E 00 18 1 810.87 1354'2. 922. 1.85 1762.06 1753 18 3.76E 00 1.0 1.38E 00 19 1 834.90 461. 685. 1.88 1814.32 1806 16 1.28E-OJ 14.1 1.03E 00 20 1 884.89 31E:. 567. 2.21 1923.00 1918 11 8.84E-02 15.6 2.68E 00 21 1 1173.07 7576. 454. 2.08 2549.59 2537 24 2.10E 00 1.4 3.2SE 00 22 1 1332.15 696 ?. 163. 2.21 2895.47 2884 22 1.93E 00 ~1. 3 1.33E 00 23 1 1383.69 E. 41. 2.50 3007.55 3000 15 2.32E-02 22.1 7.49E-01 24 1 1460.24 75. 45. 2.39 3173.99 31e8 16 2.08E-02 22.1 2.17E 00 25 1 1690.43 124. 19. 3.36 3674.Se ooos 17 3.44E-02 12.5 1.84E 00

~6 2 1 1763.65 64. 11. 3.08 3833.74 3823 22 1.79E-02 25 O 5.54E-01 27 1 2202.1v oo. 14. 2.84 4787.17 4774 20 1.01E-02 32.6 3.60E-01 28 1 2504.11 57. O. 3.21 5443.94 5434 22 1.60E-02 12.2 1.20E 00 29 1 2612.97 48. 4. 2.43 5680.70 5669 22 1.34E-02 15.E 5.19E-01 j PEAK SEARCH CUMPLETED (REV 15.li PULSE-PILE-UP CORRECTED DATA. CORRECTION = 1.002 UNCORR. LIVE TIME: 3600. CORRECTED LIVE TIME: 3594 PF IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR 1 1 ov a 1383. 7372. 1.74 65.90 62 9 3.85E-01 11.7 2 1 35.14 1205. 5933. 1.78 75.56 71 10 3.35E-01 12.6 3 1 63.53 637. 8767. 1.53 137.26 134 7 1.~7E-01 24.5 4 1 81.20 66655. 16331. 1.44 175.33 167 17 1.85E 01 0.6 5 1 133.81 2155. 3902. 1.55 290.Oo 283 14 6.00E-01 6.6 6 1 145.78 2499. 3434. 1.4o 316.08 309 13 6. 95E- 01 5.3 7 1 159,27 940. 2586. 1.68 345.41 341 11 2.61E-01 11.1 8 1 320.46 2140. 2551. 1.52 695.85 o89 15 5.95E-01 5.6 9 1 392.05 365. 1317. 1.49 851.48 847 10 1.02E-01 19.4 10 1 497.33 1681. 1527, 1.60 1080.37 1075 12 4.68E-01 5.3 11 1 511.48 6628. 2604. 3.03 1111.15 1100 21 1.84E 00 2.3 12 1 602.8e o05. 1565. 1.92 1309.?O 1304 12 8.49E-02 2o.5 13 3 657.97 405. 829. 1.43 1429.62 1421 24 1.13E-01 14.5 la 3 661.62 236, 841. 1.88 1437.57 1421 24 6.56E-02 26.2 15 1 724,35 1494. 754, 1.88 1573.95 1566 15 4.16E-01 4.9 16 1 756.84 1814. 752. 1.88 1644.58 1638 15 5.05E-01 4.3 17 1 765.95 2812. 909. 1-. 8 6 1664.39 1656 17 7.82E-01 3.I 18 1 810.87 13542. 922. 1.85 1762.06 1753 18 3.77E 00 1.O 19 1 834.90 461. 683. 1.88 1814.32 1806 lb 1.28E-01 14.1 20 1 884.89 318. 567. 2. '21 1923.00 1918 11 8.85E-02 15.6 21 1 1173.07' 7S76. 454. 2.08 2549.59 2537 24 2.11E 00- 1.4 22 1 1332.15 2 696'. 163. 2.21 2895.47 2884 22 1.94E 00 1.3 23 1 1383.69 83. 41. 2.50 3007.55 3000 15 2.32E-02 22.1 24 1 1460,24 75. 45. 2.30 ~ 3173.99 3168 16 2.08E-02 2'2.1

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' NUC L I DE IDENTIFICAT10N SYSTEM '(REV 12/84)

JJUCLf DE LINE ACTIVITY REPORT PAGE 1-ELAP5ED LIVE TIME: 3594. (PILE-UP CORRECTED)

FI5SION GAS 1 SIGMA j NUCLIDE SBHP ENERGY APEA BEGND *(ABN %E F UCI / UNIT ERROR- !

FR-88 FG 196.32 O. O. 26.00+ 0.000E-01 0.000E O O.OOCE O 685.

834.83 461. 13.00 3.485E-01 4.312E 5 6.064E 4 i 1529.7/ v. O. 1O.90 O.OOOE-01 O.000E O O.000E- 0 l 2195.84 O. O. 13.20 0.000E-01 0.000E O 0.GOOE 0 i XE-133 FG 2392.11 80.99 66655.

0.

16331.

O. 34.60 0.000E-01 0.000E 0 O.000E O' l 3 6 . 7 0:+ 1.202E 00 4.865E -4 2.872E :6 j l

1 ACTIVATION PRODUCT 1 SIGMA NUCLIDE EBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR F-18 AP 511.00 6628. 2604 96.73+ 5.344E 2.860E 11 6.643E 9 i CR-51 AP 320.08 2

'140. 2551. 9.83* 8.076E-01 5. 611E - 5 3.134E -6

-MN-54 AP 834.83 461. 685. 99.98* 3.485E-01 2.512E -6 3.533E -7 CO-58 AP 810.76 13542. 922. 99.40+ 3,573E-01 7.459E -5 7.586E -7 CO-60 AP 1173.22 7576. 454. 100.00 2.61SE-01 5.450E -5 7.664E -7 ;

1332,49 W62. 163. 100.00* 2.357E-01 5.562E -5 7.177E -7 FAG-110M AP 657.75 405. 829. 94.4O* 4.282E-01 1.903E -6 2.763E -7 677.61 0. O. 10.68 0,000E-01 0.000E O O.000E O l 686.99 0. O. 6.47 0.000E-01 O.00CE O O.OOOE O l ve.o< 0. O. 16.68 0.000E-01 0.000E O 0.000E O 763.93 v. 0. 22.28 O.000E-01 0.000E O 0.000E O 818.02 0. ,O. 7.30 0.000E-01 O.000E O O.000E O 884.67 318. S c. < . /2.60 3.316E-01 2.513E -6 3.922E -7 l 937.48, G. O. 34.20 0.000E-01 0.000E O 0.OO0E O ]

1384,27 '33 . 41. 24.26 2.285E-01 2.863E -6 6.325E -7 1505.00 C. O. 13.06 0.000E-01 0.000E O 0.000E O l

l HALOGEN FISSION PRODUCT 1 8IGMA NUCLIDE 5BHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR I-134 HFP 595.36 O. O. I1.40 0.OOOE-01 0.GOOE O O.OOOE O 621.79 0. O. 10.60 0.000E-01 0.000E O O.000E O 847.03 O. O. 95.41* O.OOGE-01 0.OOOE O O.OOOE O 884.09 318. 567. 65.30 3.316E-01 9.357E 27 1.460E '7 2 1072.55 O. O. 15.30 O.OOOE-01 0.000E O O.000E O FI$$1ON PRODUCT 1 SIGMA NUCLIDE 98HR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR I RB-89 FP 657.71 405. 829, 10.00 4.282E-01 2.455E109 3.565E108 947.69 0. O. 9.20 .O.000E-01 O.000E O 0.OOGE O

?031.88 0. O. 58.00* O.000E-01 O.OOGE O O.000E O 1248.10 0. O. 42.00 0.000E-01 0.000E O 0.000E O 2196.00 O. O. 13.30 O.OOOE-01 0.OOOE O O.OOOE O l 2570.14 0. A. 9.90 0.000E-01 O.000E O 0.000E O

ELAPSED LIVE TIME: 3594. (PILE-UP CORRECTED)

FISSION PRODUCT m

1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR SR-92 FP 241.52 0. O. 3.00 0. OOOE--01 O.OOOE O O.000E -

430,56 0. O. 3.30 0.OOGE-01 O.GOOE O O.OOOE i:

953.32 0. O. 3.60 O.OOGE-01 O.OOGE O O.OOOE <

1142.30 0. O. 2.90 O.OOGE-01 0.OOOE O O.OOOE O 1383.94 83. 41. 90.00* 2.285E-01 5.391E 4 1.191E a ZR-95 FP 724.16 1494. 754. 43.70 3.939E-01 1.70e.E -5 8.396E

'/56.72 1814. 752. 55.30* 3.792E-01 1.700E -5 7.242E NB-95 FP 76% 79 2912. 909. 99.814 3.753E-01 1.529E -5 4.757E NB-97D FP 657.9i . 405. 829. 98.09* 4,282E-01 9.947E -5 1.444E -5 1024,50 'O. O. 1.08 0.OOGE-01 0.OOOE O O.OOGE i: )

RU-103 FP 497.OS 1681. 1527. 89.00* 5.478E-01 6.966E -6 3.674E I

616.33 O. O. 5.60 O.OOOE-01 0.OOOE O O.000E v -l

'RU-105 FP 316.50 0. O. 11,70 0.000E-01 O.OOOE 0 0.OOOE -

l 469.40 0 .. O. 17.50 0.OOOE-01 O.000E O O.OOOE ': 1 i

676.40 0. G. 16.70 O.GOOE-01 0.GOOE O O.OOGE I 724.50 1494. 754 49.00* 3.439E-01 6.099E 1 3.OO2E _

SN-113 FP 255.12 0. O. 1.93 O.000E-01 O.000E O 0.OOOE 7 4 391.69 365. 1317, 64.90+ 6.765E-01 1.602E -6 3.112E l

SB-124 FP 602.71 305. 1565. 97.87* 4.622E-01 1.329E -6 3.517E -7 645.85 O. O. 7. '2 6 O.OOOE-01 O.OOOE O O.OOOE O i 722.78 0. O. 11.10 O.000E-01 O.000E O O.OOOE C 1691.02 '124. 19. 49.00 1.943E-01 2.561E -6 3.195E -7 eCS-137 EA-133 FP FP d61.65 236. 841. 85.15 4.262E-01 1.222E -6 3.203E -7 i 81.00 6.:. 655. 16331. 33.00 1.202E 00 3.162E -4 1. 867E -6 l 302.84 O. O. 17.80 O.OOOE-01 0.OOOE O O.OOOE C 356.00 0. O. 60.00* O.OOGE-01 0.GOOE O O.OOGE O CE-141 FP 145.44 2499. 3434. 48.40* 1.417E 00 7.473E -6 3.955E

~

CE-144 FP 80.11 O. 0. 1.60 0.OOOE-01 0.090E O O.OOOE 0 133.54 2155. 3902. 1O.80* 1.456E 00 2.601E -5 1.705E -6 l NATURAL FRODUCT 1 SIGMA NUCLIDE :BHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROF V-4O NP 1460.81 75. 45, 10.67* 2.107E-01 6.038E -6 1.336E ~6 RA-226 NP 166.21 O. O. 3.28 O.OOOE-01 0.OOOE O O.OOOE 0 241.08 0. v. /.49 G.OOOE-01 0.OOGE O O.OOOE O 295.21 0. O. 19.20 0.OOOE-01 0.OOOE O O.OOOE O 351.92 O. v. o/.20 0.OOOE-01 O.000E 0 0.OGOE 0 609.31 0. O. 46.30* O.OOOE-01 O.OOGE O O.OOOE C 1120.29 0. O. 15.1O O.OO0E-01 O.000E O O.OOOE C 1238.11 O. O. 5.94 O.OOGE-01 O.OOOE O O.OOOE O 1764.49 64. 11. 15.80 1.878E-01 4.073E -6 '1.017E -c 2204.22 O. O. 4.98 0.OOOE-01 O.OOOE O O.OOOE C

N y e m y 1

a NUCLIDE IDENTIFICATION SYSTEM (REV 12/84) ]

.UNENOWN LfNE REPORT PAGE 3 J ELAPSED LIVE TIME 3594 (PILE-UP CORPECTED) d LINES NOT LISTED IN LIBRARY 4

i PK IT ENERGv' AREA BI:GND FWHM CHANNEL-LEFT PW CTS /EEC % ERR %EFF 4

h 1 1 30.70 1383. '372. 1.74 65.90 62 9 3.85E-01 11. 7 O. 00E-01 I 2 1 35.14 1205. 5933. 1.78 75.56 71 10 3.35E-01 12.6 O.00E-01 i 3 1 43.53 637. 87o7. 1.53 137.26 134 7 1.77E-01 24.5 8.89E-01 '

7 1 150.27 940. 2586. 1.68 345.41 341 11 2.61E-01 11.1 1.36E 00 l 27 1 2202.10 36. 14, 2.84 4787.17 4774 20 1.01E-02 32.6 1.58E-01 l 2B 1 2504.11 5/. u. 3,21 5443.94 5434 22 1.60E-02 12.2 1.43E-01 29 1 2612,97 48. 4 2.43 5680.70 5669 22 1.34E-02 15. 8 O. 00E-01 l

LINES NOT NEETING

SUMMARY

CRITERIA FK NUCLIDE ENERGY HALFLIFE DECAY UCI / UNIT ABNDIFF FAILED a BA-133 81.00 1.050E 01Y 1.OviE O 3.162E -4 29. 78.' ABN

1 F-18 511.00 1.097E 02M 1.186E 16 2.860E 11 100.00% DCY 13 RB-89 657.71 1.544E 01M 1.383E114 2.455E109 7.02% DCY,ABN 13 AG-110M 657.75 2.499E O2D 1.011E 0 1.903E -6 63.35% ABN 15 RU-105 724.50 4.440E 00H 4.190E 6 6.099E 1 51.637. DCY,ABN 19 KR-88 834.83 2.840E OOH 2.252E 10 4.312E 5 13. 31. DCY 3 ABN

~.0 AG-110M 884.67 2.490E O2D 1.011E O 2.513E -6 63.35% ABN 20 I-134 884.09 5.260E 01M 3.387E 33 9.357E 2/ 22,98% DCY,ABN 23 SR-92 1383.94 2.71OE 00H 7.065E 10 5.391E 4 87.55% DCY 23 AG-110M 1384.27 2.499E O2D 1.011E O 2.863E ~6 63.35% ABN 24 RA-226 1764.49 1.600E 03Y '1.OOGE O 4.073E -6 10.17% ABN i

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NUCLIDE IDENTIFICATION SYSTEM (REV 12/84) j.UMMARY OF NUCLIDE ACTIVITY PAC,E 4 TOTAL LINE? IN SPEC TRUM 29 8..INES NOT L15TED IN LIBRARY 7 IDENTIFIED IN 6UMMAR', REPORT 18 6 2 . 0 7.

FI52. ION GAE 1-916MA NUCLIDE 9BHF HALFLIFE DECAY UCI / UNIT ERRUR %ERP YE-133 FG 1.259E O2H 1.712 4.2465E -4 2.872E -6 0.59 AC TIVATION PRODUC T

/ 1-SIGMA NUCLIDE 5BHR HALFLIFE DECAY UCI / UNIT ERROR % ERR CP-51 AP 2.770E 01D ,

MN-54 1.107 5.611E -5 3.134E -6 5.59 If*V6~C' AP 3.127E O2D 1.009 2.512E -c 3.533E -7 14.06 A d i d 6-o "'

CO-58 AP 7.080E 01D 1.041 7.459E -5 7. 586E -7 L. fog 6- # '

1.02 CO-60 AP 1.925E 03D 1.001 5.562E -5 7.177E ~7 1.29 4/. B S, 6.o i' FI55 ION PRODUCT 1-SIGMA NUCLIDE SBHP HALFLIFE DECAY UCI / UNIT ERROR ?. ERR ZF-95 FP 6.402E 01D 1.045 1.700E -5 7.242E -7 4.26 i - @ 3 C- ~ 1 NE-95 FP 3.506E 01D 1.084 1.529E -5 4.757E -7 NE-97D FP 3..11 1. 3 3 'l 6-* ',

1.c.90E 01H 54.938 9.947E -5 1.444E -5 ;142,2J 8. b h F -ok Rt.-103 FP 3.935E 01D 1.074 3. 674E - 7 GN-113 FP 6.966E -6 5.28 L 094 6-OL 1.151E O2D 1.025 1.602E -6 3.112E -7 19,43 1 5 f I C~ ~# '

55-124 FP 6.020E 01D 1. 04Ci 1.329E -6 3.517E -7 l8fi 6-#"

C5-137 FP 26.47 3.017E 01Y 1.000 f'72fE7 3.203E -7 26.20 EE-141 FP 3.250E 01D 1.091 f.ov b 6 o' 7.473 -6 3.955E -7 5. 2'i' I,. ft E, 6 - o '-

CE-144 FP 2.843E O2D 1,010 2.601E -5 1.705E -6 6.56 l a t.q 6-. f A

NATURAL PRODUCT 1-SIGMA NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR % ERR K-40 NP 1,277E 09Y 1.000 6.038E -6 1.336E -6 22.13

% 91h GC) W % AOl ~^"

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I.AMF LE DATE: 19 .JUN-87 09:45:00 SAMPLE IDENTIFICATION: 87-254 TYPE OF SAMFLE: LIOUID h8 SAMPLE QUANTI TV: 501.0000 UNIT 9: ML SAMPLE GEOME TP y : L15GO EFF!CIENCY FILE NAME: VANEFF.L1500.,

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4 ACOUIRE DATE: 26 .JUN-87 15:22:35 4 FWHM(1332) 2.299 PRE 9ET TIMEiLIVE): 57600. SEC + SENSITIVITY: 5.000 ELAPSED REAL TIME: 57612. SEC

SHAPE PARAMETER : 10. 0 '. I ELAPSED LIVE TIME: 57600. EEC

NBR ITERATIONS: 10, 4

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DETECTOR: NRC GE 80 4 L I BR ARY : NUCL . MAS T ER CALIB DATE: 26 .JUN-F:7 10:30:59 + ENERGY TOLERANCE: 0.900EV I L EV/C HNL : O.4599891 o HALF LIFE RATIO: 8.00 i OFF5ET: 0. 3867-'06 UEV 4 ABUNDANCE LIMIT: 80.00*4 O. COE F. -

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- ENERGY' WINDOW 4.99 TO 2759.33 q FC IT ENERGY (REA BEGND FWHM CHANNEL LECT PW CTS /SEC '4 ERR FIT r ,

1 1 63.58 156. 1483. O.94 137.37 135 7 2.72E-03 42.1 4.D4E-01 l 2 1 92.95 453, 1760 1.75 201.32 198 8 7.87E-03 12.7 2.48E 00 l 3 1 18e.06 501. 2256. 2.00 403. 6c. 397 12 8.70E-03 19.3 1.39E 00 I 4 1 239.27 433. 1921. 2.85 51a.32 514 11 7.52E-03 20.3 3.23E 00 5 1 511.45 3166. 2043, 2.86 1111.08 1101 2

'4 5.50E-02 4.3 1.57E 00 6 1 558.96 1056. 944 1,66 1214.37 1209 12 1.83E-02 6.8 2.23E 00 7 1 583.60 144 609 t.66 1767.94 12A4 9 2.51E-03 32.8 4.73E-01 8 1 609.83 456. 1305. 2.01 1324.97 1314 18 7.91E-03 19.2 8.04E-01 1 9 1 e.5 1 . 6 5 330. 760. 2.88 1415,89 1409 12 5.73E-03 17.5 3.50E 00 l 10 1 911.63 330. 449. 2.54 1981.14 1976 11 5.73E-03 14.3 4.34E 00 !

11 1 1120.64 522. 768. 2.45 2435.59 2424 23 9.07E-03 14.9 6.29E-01 12 1 1238.31 299. 525, 2.35 2691.44 2683 19 5.19E-03 19,7 6.22E-01 13 1 1377.84 239. 314. 2.El 2994.82 2989 15 4.14E-03 17.3 8.46E-01 14 1 1460.85 Ro4. 419. 2.44 3175.33 3163 25 1.55E-02 7.8 1.79E 00 15 1 1764.44 78-1 216. 2.60 3835.50 3825 22 1.36E-02 5.9 1.25E 00 16 1 1846.00 106. 171. 2.27 4014.76 4009 13 1.84E-03 26.8 1.44E 00 1~ 1 2203.76 304. 94 3.04 4790.78 4783 19 5.28E-03 10.8 1.25E 00 18 1 2222.98 141. 11/. o.03 4832.58 4824 18 2.46E-03 20.9 6.97E-01 li 1 2613.89 585. 104. 3.09 5682.70 5670 26 1.01E-02 5.8 1.51E 00 i

i PEAU EEARCH COMPLETED (REV 15.1) !

PUL5E-PILE-UP CORRECTED DATA. CORPECTION = 1.000 UNCORR. LIVE TIME: 57600. CORRECTED LITE TIME: 5'7395.

Pf IT ENEPGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR !

1 1 63.58 156. 1483. O.94 137.37 135 7 2.72E-03 42.1 2 1 92.99 453. 1709. 1.75 201.32 198 8 7.87E-03 16.7 3 1 186.06 501. 2256, 2.00 403.66 397 12 8.70E-03 19.6 4 1 :39.27 433. 1921. 2.85 519.32 514 11 7.52E-03 20.3 5 1 511.45 3166. 2043. 2.86 1111.08 1101 24 5.50E-02 4.3 6 1 558.96 1056. 944. 1.66 1214.37 1209 12 1.83E-02 6.8 1 583.60 144. 609. 1.66 1267.94 1264 9 2.51E-03 32.8 8 1 609.83 356, 1305. 2.01 1324.97 1314 18 7.91E-03 19.2 9 1 651.65 a30. 760. 2.88 1415.89 1409 12 5,73E-03 17.5 1' 1 911.e3 330. 449, 2.54 1981.14 1976 11 5.73E-03 14.3 11 1 1120.64 522. 768. 2.45 2435.59 2424 23 9.07E-03 14.9 12 1 1238,31 299. 525. 2.35 2691.44 2683 19 5.19E-03 19.7 13 1 1377.84 239. 314, 2.81 2994.82 2989 15 4.14F-03 17.3 14 1 1460.85 894. 419. 2.44 3175.33 3163 25 1.55: -02 7.8 15 1 1764.46 784. 216. 2.60 3835.50 3825 22 1.36E-02 5.9 16 1 1846.90 106. 171. 2.27 4014.76 4009 13 1.84E-03 26.8 17 1 2203.76 304 94. 3.04 4790.78 4783 19 5.28E-03 10.8 18 1 2222.98 141. 117. 3.03 4832.58 4824 18 2.46E-03 20.9 19 1 2613.89 585. 104. 3.09 5682.70 5670 26 1.01E-02 5.8 PILE-UP CORRECTION COMPLETED (REV 2) i l

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(JUCLIDE .. IDENTIFICATION SYSTEM (REV 12/84)

NUCL"IDE LINE ACTIVITY REPORT PAGE 1

' ELAF BED LIVE TIME: 57505. (PILE-UP CORREC TEin l l

J AC T I VAT I ON PROE.UCT 1 SIGMA NUCLIDE SCHR ENERGY AREA BiGND %ABN *EFF

. UCI / UNIT ERROR ;

i 18 AP 511.00 3166. 2043. 96.73+ 5.344E-01 1.316E 23 5.678E 21 I SC-46 AP 889.25' O. O. 99.98 O.OOOE-01 O.OOGE O O.OOGE 0 1120.51 522. 768. 99.994: 2.719E-01 1.916E -7 2.863E -8 t

.AS-76 AP 559.10 1056. 944 44.704 4.941E-01 5.311E -5 3.617E.-6 l 1216.02 0. O. 3.84 6.000E-01 0.'OO0E O O.OOOE O ) i 1

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FI$? ION PRODUCT 1 1 SIGMA l NUCLIDE 3BHR ENERGY AREA BRGND %ABN %EFF UCI / UNIT. ERROR {

PU-103 FP 497.08 0. O. 89.00+ 0.OOOE-01 O.OOOE- 0 0.OOOE O 61O.33 456, 1305. 5.60 4.576E-01 1.903E '

3.652E -7 i I,

NA7 URAL PRODbCT 1 1 SIGMA {

NUCLIDE SBHR ENERGN AREA BVGND %ABN %EFF UCI / UNIT FRROR l E-AO NP 1460.81 894 419. 1 0 . 6 7 +- 2.186E-01 3.592E -6 2.820E -7 RA-226 NP 156.21 501. 2256. 3.28 1.242E 00 1.152E -6 2.255E -7 241.98 O. O. 7.49 0.000E-01 0.OOOE O O.OOGE O 295.21 O. O. 19.20 O.000E-01 O.OOGE O O.GOOE O 3 351.92 0. O. 37.20 0.OOOE-01 O.GOOE O O.OOOE O '

609.31 456. 13,05. 46.304- 4.576E-01 2.015E -7 3.866E -6 1120.29 522. 768. 15.10 2.719E-01 1.192E -6 1.781E -7 1238.11 299. 525. 5.94 2.502E-01 1.885E -6 3.720E -7 1764.49 '84, 216. 15.80 1.877E-01 2.475E -6 1.453E -7 i 2204.22 304. 94. 4.98 1.576E-01 3.631E -6' 3.909E -7 l TH-232 NP 238.63 433. 1921. 44.60 1.032E 00 8.814E -8 1.787E'-8 338,32 O. O. 11.40 C.OOOE-01 0.OOOE O O.OOGE O 727.17 0. O. 11.80 0.OOOE-01 O.OOOE O O.OOOE O I 583.14 144. 609. 30.25 4.756E-01 9.406E -8 3.085E --8 911.07 330. 449 27.70 3.233E-01 3.449E -7 4.941E -8 I 969.11 O. O. 16.60 0.OOOE-01 O.OOGE O O.OOGE O 2614.66 585. '104, 35.86* 1.OOOE O2 1.527E -9 8.859E-11

NUCLIDE IDENTIFICATION SYSTEM (REV.12/84L -

UNVN8Whl LINE REPORT PAGE 2 l ELAPSED LIVE TIME 5'7595. (PILE-UP CORREC TED) 4 LINES NOT (_ISTED IN LIBRARY .

1 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR %EFF 1 1 63.58 IS6. 1483. O.94 1o..:< 135 7 2.72E-03 42.1 8. 90E- 01 2 1 92,99 453, 1709. 1.75 201.32 198 8 7.87E-03 16.7'l.36E 00 !

9 1 651.6S 330. /60, 2.88 1415.89 1409 12 5.73E-03 17.5 4.32E-01 13 1 1377.84 239. 314 2.81 2?94.82 2980 15 4.14E-03 17.3 2.29E-Oi I r. 1 1846.90 106. 171. 2.27 4014.76 4009 13 1.84E-03 26.8 1.81E-01 18 1 2222.98 141. 1i7. 3.03 4832.58 4824 18 2.46E-03 20.9 1.57E-01 1

i LINES NOT MEETING SUMMARv' CRITE91^, ',

J PK NUCLIDE ENERGY HALFLIFE DECAY UCI / UNIT ABNDIFF FAILED l' l 3 RA-226 186.21 1.600E 03Y 1.000E O 1.152E -6 58.86% ABN 4 TH-232 238.63 1.OOOE 10Y 1.000E O 8.814E -8 77.67% ABN 5 F-18 511.00 1.097E 02M ?.294E 29 1.316E 23 100.00% DCY 7 TH-232 583.14 1.OOGE 10Y 1.OOGE O 9.406E -8 77.67% ABN 1 8 RU-103 6 1 0 . 2 :. o.935E 01D 1.143E O 1.903E -6 5.92% ABN i 6 RA -226 609,31 1.600E 03Y 1.GOOE O 2.015E -7 58.86% ABN 10 TH-232 911.07 1.OOOE 10Y 1.OOOE O 3.449E -7 77.67% ABN 11 SC-46 1120.51 8.383E 01D 1.065E O 1.916E -7 50.00% ABN 11 RA-226 1120.29 1.630E 03Y 1.QUOE O 1.192E -6 58.86% ABN 12 RA-226 1238.11 1.600E 03Y 1.GOOE O 1.885E -6 58.86% ABN ,

15 RA-226 1764.49 1.600E 03Y 1.OOOE O 2,475E -A 58.86% ABN ]

17 RA-226 2204.22 1.600E 03Y '1.000E O 3.631E -6 58.86% ABN I 19 TH-232 2614.66 1.000E 10Y 1.OOOE O 1.527E -9 77.67% ABN i 4

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NUCLIDE.. IDENTIFICATION SYSTEM-(REV 12/84) PAGE 3 i SUMMAAY OF NUCLIDE ACTI'/ITY TOTAL LINES IN SPECTRUM 19 i LINES NOT LISTED IN LIBPARy 6 IDENTIFIED ItJ

SUMMARY

FEPORT 2 1 0 . r. r .

i, ACTIVATION PRODUCT I-SIGMA l NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR % ERR l

, z;; . o 4 4.. e47 5, 7. ; ; g 5 ;; g ; ; ,4_ g y,.g,4,,,g

46. - ;. A--

l NATURAL PRODUCT i I-SIGMA NUCLILE SBHR HALFLIFE DECAY UCI / UNIT ERROR %ERF !

I 3,592E 2.S20E -7 7,85 K-40 NP 1.277E 09Y 1.000 -6 l, c

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SAMPLE DATE: 22-JUN-87 13!00:00 SAMPLE IDENTIFICATION: 87-255 T'YPE OF SAMPLE: LIOUID SAMPLE QUANTITY: 450. SOO4L UNITS: ML 9 AMPLE GEOMETRY: L1500 EFFICIENCY FILE NAME: VANEFF.L1'50024

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j ACOUIRE DATE: 29-JUN-87 08:08:48 :+ FWHM(1332) 2.2Tv PRESET TIME (LIVE): 3600. SEC + SEN81TIVITY: 5.000 ELAPSED REAL TIME: 3613. SEC 4 SHAPE PARAMETER : 10.0 %

ELAPSED LIVE TIME: 3600. SEC + NBR ITERATIONS: 1O.

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4: 4 4 4 * + 4:4 4*:4 +:4 $$ $4:4 4 4 4

DETECTOR: NAC GE 80 + LIBRARY:NUCL. MASTER CALIB DATE: 26-JUN-87 10:30:59 + ENERGY TOLERANCE: 0.900KV REV/CHNL: 0.4599891 + HAL~ LIFE RATIO: 8.00 '

OFFSET: 0.3867306 KEV

ABUNDANCE LIMIT: 80.00%

0. COEFF. : -1.467E-08 KEV /C+t2 +

4 + + +:4 4 + 4 4 4 4 + 4 & :+ 4 t + 4 & 4.* :+.4 4 4 :+ 414 4 4. M + 4. t * *

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PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT q l

1 1 35.35 286. 2655. 1.16 76.02 74 7 7.96E-02 30.6 1.85E 00 2 1 81.25 19355. 7578. .1.45 175.78 167 1; 5.38E 00 1.3 1.56E 01 3 1 122.17 287. 2062. 1.18 264.76 263 7 7.96E-02 27.O 2.20E 00 4 1 133.96 2231. 3277. 1.47 290,16 283 12 6.20E-01 5.6 2.23E 00 i 5 1 145.83 2485. 3096. 1.38 316.19 311 11 6.90E-01 4.8 2 9.'0E-01 6 1 159.40 908, 2484. 1.40 345.69 342 10 2.52E-01 10.9 1.72E 00 7 1 320.50 2026. 2382. 1.64 695 93 689 14 5.63E-01 5.5 8.90E-01 ]

8 1 392.12 496. 1398. 1.79 851.64 946 11 1.38E-01 15.4 2.07E 00 9 1 49'7.57 1564. 1570. 1.68 1080389 1075 12 4.34E-01 5.6 1.32E 00 10 1 511.5o 6536. 2737. 2.90 1111.30 1101 22 1.82E 00 2.4 1.78E 00 11 1 603.22 571. 2360. 2.72 1310.60 1299 20 1.59E-01 21.7 2.02E 00 12 1 658.13 435. 866. 1.91 1429.97 1425 11 1.21E-01 14.4 8.17E-01 l 1

13 1 724.67 1580. 787. 1.85 1574.64 1568 15 4.39E-01 4.8 8.36E-01 1 14 1 757.17 1768. 892. 1.79 1645.30 1637 17 4.91E-01 4.6 1.46E 00 i 15 1 766.22 2983. 897. 1.92 1664.98 1656 17 n.29E-01 3.O 2.36E 00 {'

16 1 811.21 13791. 1037. 1.69 J762.79 1753 18 3.83E 00 1.0 3.48E 00 17 .1 835.10 509. 708. 2.11 1814.87 1806 16 1.41E-01 12.7 1.59E 00 18 1 885.le 316. 612, 2.16 1923.60 1919 12 8.79E-02 16.8 1.28E 00 j 19 1 1173.52 80 :to. 426. 2.07 2550.55 2539 22 2.23E 00 1.3 2.55E 00 {

20 1 1332.70 6847. 171. 2.20 2896.67 2887 19 1.90E 00 1.3 1.90E 00 21 1 1384;50 106. 59, 2.42 3009,29 2999 20 2.94E-02 21.7 1.71E 00 22 1 1460.93 88. 30. 2.35 3175.50 3169 15 2.44E-02 18.6 2.68E 00 l 23 2 1690,99 100. 19. 2.64 3675.75 3668 19 2.79E-02 17.4 3.58E 00 !

j- 24 1 1764.61 92. 7. 3.07 3835.84 3829 14 2.56E-02 14.2 6.88E 00 25 1 2612.98 58. 11. 3.74 5680.72 5673 20 1.60E-02 13.8 1.64E 00 PEAU SEARCH COMPLETED (REV 15,1) s PULSE-PILE-UP CORRECTED DATA. CORRECTION = 1.001 i UNCORR. LIVE TIME: 3600.CORRECTEO LIVE TIME 3595. I PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR 1 1 35.35 286. 2655. 1.16 76.02 74 7 7.97E-02 30.6 4 2 1 81.25 19355 7578. 1.45 175,78 167 17 5.38E 00 1.3 i 3 1 122.17 287, 2062. 1.18 264.76 26.3 / /.97E-02 27.O 4 1 133.86 2231. 3277. 1.47 290.16 283 12 6.21E-01 5.6 l 5 1 145.83 2485. 3096. 1.38 316.19 311 11 6.01E-01 4,8 l 6 1 159.40 908. 2484 1.40 345.69 342 10 2.53E-01 10.9 7 1 320.50 2026. 2382. 1.64 695.93 689 14 5.64E-01 5.5 8 1 392.12 496. 1396. 1.79 851.64 846 11 1.3GE-01 15.4 9 1 497.57 1564. 1570. 1.68 1080.89 1075 12 4.35E-01 5.6 10 1 511.56 6536. 2737. 2.90 1111.30 1101 22 1.82E 00 2.4 l 11 1 603.22 571. 2360. 2.72 131O.60 1299 20 1,59E-01 21.7 i

l l

12 1 658.13 435. 866. 1.91 1429.97 1425 11 1.21E-01 14.4 1 13 1 724.67 1580. 787. 1.85 1574.64 1568 15 4.39E-01 4.8 14 1 757.17 1768. 892. 1.79 1645.30 1637 17 4.92E-01 4.6 15 1 766.22 2983. 897. 1.92 1664.98 1656 17 8. 30E -01 3.O 16 1 011.21 13791. 1037. 1.89 1762.79 1753 18 3.84E 00 1.O )

17 1 835.16 509. 708. 2.11 1814.87 1806 16 1.42E-01 12.7 l 18 1 885.17 316. 612. 2.16 1923.60 '1919 12 8.80E-02 16.8 19 1 1173.52 8020. 426 2.07 2550.55 2539 22 2.23E 00 1.3 1 20 1 2 133'.70 6847, 171. 2.20 2896.67 2887 19 1.90E 00 1.3 l 21 1 1384.50 106. 59. 2.42 3009,29 2999 20 2.95E-02 21.7 I 22 1 1460.93 88. 30. 2.35 3175.50 3169 15 2.45E-02 18.6 I 23 1 1690.99 100. 19. 2.64 3675.75 3668 19 2.80E-02 17,4 24 1 1764.61 92. 7. 3.07 _3835.84 3829 14 2.57E-02 14.2 25 1 2612.98 58. 11. 3.74 5680.72 5673 20 1.61E-02 13.8 1 I

1 PILE-UP CORRECTION COMPLETED (REV 2) l t

j

NUCLIDE IDENTIFICATION SYSTEM (REV 12/84)

NUCLIDE LINE ACTIVf TY REPORT PAGE 1

". ELAP5ED LIVE TIME: 3595. (PILE-UP CORRECT EM FISSION GAS 1 SIGMA NUCLIDE SDHR. ENERGY AREA BEGND %ABN %EFF UCI / UNIT ERROP UR-98 FG 196.32 0. O. 26.00+: O.000E-01 0.OOOE O O.000E -

834.83 509, 708. 13.00 3.484E-61 4.078E 12 5.171E 11 1529.77 O. O. 10.90 0.OOOE-01 0.OOGE O O.OOGE 0 2195.84 O. O. 13.20 0.000E-O! O.OOOE O O.OOOE O 2392.11 0. 0. 34.60 0. OOOE-O'i O.GOOE O O.OOOE O i XE-133 FG 80.99 19355. 7578. 36.70:+ 1.202E 00 1.772E -4 2.259E -f j i

ACTIVATION PRODUCT j 1 SIGMA i NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR I F-18 AP 511.00 6536. 2737. 96.73* 5.343E-01 1.772E 22 4.311E 20 CR-51 AP 320.08 '2026. 2382. 9.83* 8.075E-01 4.963E -5 2.753E -6 MN-54 AP 834.83 509. 708. 99.98+ 3.484E-01 2.432E -6 3.084E -7 j CO-57 AP 122.06 28/. 2062. 85.51* 1.481E 00 ?.775E -7 1.019E -7 <

136.48 0. O. 10,60 0.OOOE-01 O.OOOE O O.OOOE O CO-58 AP 13791. !

810.76 1037. 99.40+ 3. 572E- 01 6.808E -5 6.907E -7 i C0-60 AP 1173.22 8020. 426. 100.00 2.617E-01 5.037E -5 6.642E -7 l 1332.49 6847. 171. 100.00* 2.356E-01 4.776E -5 6.21SE -7 AG-110M AP 657.75 435. 866. 94.40+ 4,2815-01 1.800E -6 2.595E -7 677.61 0. O. 10.68 O.GOOE-01 O.OOOE O O.OOOE O 686.99 0. O. 6.47 O.OOGE-01 O.OOOE O O.OOOE O 706.6/ v. ,O. I6.68 O.OOOE-01 O.OOOE O- O.OOOE O 763.93 O. O. 22.28 O.GOOE-01 O.OOOE O O.COOE O l 818.02 O. O. 7.30 0.GOOE-01 0.OOGE O O.OOGE 0 684.6/ 316. 612. 72.60 3.315E-01 2.196E -6 3.685E -7 937.48 6 G. 34.20 0.OOOE-01 0.OOOE O O.OOOE 0 ;

1384.27 106. 59. 24.26 2.284E-01 3.196E -6 6.929E -7 1505.00 O. O. 13.06 O.OOOE-01 O.OOOE O O.OOOE C EU-152 AP 121.78 287. 2062. 2 8.40

' 1.481E 00 1.118E -6 3.017E '

344.27 O. O. 26.50+ 0.OOOE-01 0.000E 0 0.OOOE 0 778.89 O. O. 12.74 O.OOOE-01 O.OOOE O O.OOCE O 964.01 O. O. 14.40 0.OOOE-01 0.OOGE O O.OOOE 6 1085.78 0. O. 1O.00 O.OOOE-01 O.OOOE O O.OOGE O 1112.02 0. O. 13.30 O.OOOE-01 O.OOOE O O.OOOE O 1407.95 O. O. 20.70 0.OOOE-01 0.OOOE O O.OOOE O FISSION PRODUCT 1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR RB-89 FP 657.71 435. 866. 10.00 4.281E-01 3.419E186 4.929E185 947.69 0. O. 9.20 0.OOOE-01 O.OOOE O O.O^OE O 103J.SS 0. O. 58.00* O.OOGE-01 0.COOE O O.OOOE O 1248.10 0. O. 42.00 O.OOOE-01 0.OOOE O O.OOGE O 2196.00 O. O. 13.30 0.OOOE-01 0.OOOE O O.GOOE O 2570.14 O. O. 9.90 0.OOOE-01 O.OOOE O O.GOOE O

I l

NUCLIDE' IDENTIFICATION $YSTEM (REV 12/84)

NUCLIDE LINE ACTIVITY REPORT PAGE 7 l

ELAPSED L1VE TIhE ?595. (PILE-UP C ORRECTED)

M SSION PRODUCT 1 SIGMA: i NUCLIDE SBHR ENERGY AREA BKGND %ABN %EF" UCI / UNIT ERROR 5R-92 FP 241.52 0. O. 3.00 0.000E-01 O.000E 0 0.000E O 030.56 0. O. 3.30 0.000E-01 0.000E O O.000E 0 953.32 0. G. 33 60 O.000E-01 0.000E O O.000E O 1142,30 0. O. 2.90 0.000E-01 0.000E O 0.000E O 1 1383.94 106, 59. 90.00* 2.284E-01 1.271E 12 2.755E 11 ZR-95 FP 724.18 1S80. 787. 43.70 3.937E-01 1.621E -5 7.702E -7 !

756.72 1 -' 68. 892. 55.30* 3.791E-01 1,489E -5 6.840E -7 i NB-95 FP 765.79 2983. 897. 99.81* 3.752E-01 1.494E -5 4.509E -7 !

NB-9'7D FP 657.90 435. 866. 98.09* 4.281E-01 1.397a -3 2.015E -4 l 1024.50 0. O. 1.08' O.000E-01 O.000E O 0,000E O l MO-90 FP 122,37 287. 2062. 64.26 1.481E 00 2.407E 2 6.496E 1 257.34 0. O. 77.804 0.000E-01 0.000E O 0.000E O-RU-103 FP 497.08 1564. 1570. 89.00* 5.475E-01 5.933E -6 3.312E -7 610.33 0. O. 5.60 0.000E-01 O.000E O 0. 000E. O i RU-105 FP 316.50 0. O. 11.70 O.000E-01 O.000E O 0.000E O i 469.40 0. O. 17.50 0.000E-01 0.000E O 0.000E 0 676.40 0. O. 16.70 0.000E-01 O.000E O 0.000E O !

724.50 1580. 787. 49.00* 3.937E-01 1.670E 6 7.937E 4 i

$N-113 FP 255.12 0. O. 1.93 O.000E-01 0.000E O 0.OOOE O 391.69 496, 1398. 64.90* 6.763E-01 1.928E ~6 2.971E -7 SE:~ ; 24 FP 402.71 571. 2360. 97.87* 4.620F-01 2.241E -6 4.871E -7 645.85 0. O. 7.26 0.000E-01 0.000E O 0.000E O 722.78 0. O. 11.10 0.000E-01 U.000E O O.000E O 1691.02 100. '19 . 49.00 1.943E-01 1.872E -6 3.265E -7 BA-133 FP 91.00 19355. 7578. 33.00 1.202E 00 8.012E -5 1. 022E --6 l 302.54 0. 0. 17.80 0.000E-01 0.00GE O 0.000E O

! 056.00 0. O. 60.00* 0.000E-OL O.000E O O.OOOE O CE-141 FP 145.44 2485. 3096. 48.40* 1.416E 00 6.874E -6 3.299E -7 CE-144 FP 80.11 0. O. 1.60 0.000E-01 0.OOGE O O.OOCE O 133,54 2231. 3277. 10.80* 1.456E On 2.354E -5 1.335E -6 NATURAL PRODUCT NUCLIDE SBHR ENERGY AREA BKGND %AGN %EFF UCI / UNIT ERROR K-40 NP 1460.81 88. 30, 10.67* 2.186E-01 6,180E -6 1.150E -6 i l RA-226 NP 186.21 0. O. 3.28 0.000E-01 0.000E O O.000E O i 241.98 O. O. 7.49 0.OOOE-01 0.000E O O.OOOE O (

295.21 0. O. 19.20 0.000E-01 0.000E O 0.OODE O 351.92 O. O. 37,20 C.OOOE-01 0.000E O 0.000E O 609.31 0. O. 46.30* O.000E-01 0.000E O O.000E O l 1120.29 O. 0, 15.1O O.OOOE-O1 O.000E O O.000E O 1238.11 0. O. 5.94 0.OOOE-01 0.OOCE O 0.000E O 1764.49 92. 7. 15.80 1.877E-01 5.098E -6 7.249E -7 2204.22 0. O. 4.98 0.000E-01 0.000E O 0.000E O ;

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-NUCLTDE IDENTIFICATION. SYSTEM (REV 12/84)

UNyNOWrJ LINE REPC.RT PAGE 3 ;

' ELAPSED LIVE TIME 3595. (PILE-UP CORRECTED) !

LINES NOT LISTED IN L:BRARY

'l i

.PU IT ENERGY ARE/. BUGND FWHM CHANNEL LEFT PW CTS /SEC % ERR %EFF

. 1 1 1 35.35 28:. 2655. 1.16 76.02 74 7 7.97E-02 30.6 O.OOE-01 )

6 1 159.40 90E. 2484 1.40 345.69 342 10 2.53E-01 10.9 1.36E 00 25 1 2612.98 5F. 11. 3.74 5600,72 5673 20 1.61E-02 13.8 O.OOE-01 i

LINES NOT MEETING SUMPAP's CRITERIA f PK NUCLIDE ENERGY HALFLIFE DELAY UCI / UNIT ABNDIFF FAILED il 2 BA-133 01.00 1.050E 01Y 1.OO1E O 8.012E -5 29.78% ABN t

? MO-90 122.37 5.670E OOH 4.876E 8 2.407E 2 45.23% DCY.ABN l 7 EU-152 121,78 1.360E 01V 1.OO1E O 1.118E -6 22.53% ABN 10 F-18 511.00 1.097E O2M 8.547E 26 1.772E 22 100.00% DCY 12 RB-89 657.71 1.544E 01M 2.051E191 3.419E186 7,02% DCY,ABN 12 NB-97D 657.90 1.690E 01H 8.221E 2 1.397E -3 98.91's DCY 12 AG-110M 657,75 2.499E O2D {

1.019E O 1.800E -6 63.35% ABN '

17 RU-105 72t. 50 4.440E OOH 1.244E 11 1.670E 6 51.63% DCY,ABN 17 KR-88 834.83 2.840E OOH 2.213E 17 4.078E 1-2 13.31% DCY,ABN !

18 AG-110M 884.67 2.499E O2D 1.019E O 2.196E -6 63.35% ABN I 21 SR-92 1383.94 2.710E OOH 1.503E 18 1.271E 12 87.55% DCY l 21 AG-110M 1384.27 2.499E O2D 1. 01 'i'E O 3.196E -6 63.35% ABN i 24 R4-226 1764.49 1.600E 03Y 1.OOOE O 5.098E -6 10.17% APN I

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NUCLIDE IDENTIFICATION SYSTEM-(REV 12/84) --

SUMMARY

.OF NUCLIDE ACTIVfTY PAGE 4 TOTAL LINES IN SPECTRUM 25 LINES NOT LISTED IN LIBRARY 3 j IDENTIFIED IN

SUMMARY

REPORT 17 68.00% {

l s

FII.51DN GAS 1-SIGMA NUCLIDE SBMR HALFLIFE DEC Av UCI / UNIT ERROR % ERR XE-133 FG 1.259E'02H 2.462 1.772E -4 2.259E -6 1.28 ACTIVATION PRODUCT 1-SIGMA .

NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR % ERR ?

CR-51 AP 2.770E 01D 1.186 4.963E -5 2.753E -6 5.B5 l MN-54 AP 3.127E O2D 1.015 2.432E -6 3.084E -7 12.68 i CO-57 AP 2.709E O2D 1.018 3.775E -7 1.019E -7 ze.. ve CO-58 AP 7.080E 01D 1.069 6.808E -5 6.907E ~7 !

CO-60 AP 1.925E 03D 1.002 4.776E -5 6,218E -7 . v 1 'f 1.30 I I

FliiION PRODUCT 1-SIGMA l NUCLIDE GBHR HALFLIFE DECAY UCI / UNIT ERROR % ERR ZR-75 FP 6.402E 01D 1.077 1.489E -5 6.840E -7 4.59 NB ';5 FP 3.506E 01D 1.144 1.494E -5 4.509E -7 3.02 /

RU-103 FP 3.935E 01D 1.128 5.933E -6 3.312E -7 5.58

\SN-113 FP 1.151E O2D 1.042. 1.928E 2.971E -7 15.41 I

,SB-124 FP 6.020E 01D 1.082' 2.241E -6 4. 871 E --7 21.74 CE-141 FP 3.250E 01D 1.157 6.874E -6 3.299E -7 4.80 CE-144 FP 2.843E O2D 1.017 2.304E -5 1.335E -6 5.64 i

NATURAL PRODUCT 1-SIGMA NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR % ERR l K-40 NP 1.277E OoY 1.000 6.180E -6 1.150E -6 18.61 l t___._______________ _ _ _ _ _ _ _ _ _ _ _ _ _

*4 @MD$ 4 C * @@@@@@@**@ * *$@ $@ 4 * @*O* 4 DC@ * * * @ *@*@ t@t *@ *C@@@* @ @**@@ j

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,. POINT' BEACH DEMINERALIZED FL_USH LINE SAMPLE REFILLED BOTTLE SAMPLE DATE: 22 .JUN-87 13:00:00

i. AMPLE IDENTIFICATION: 87-256 / l TYPE ' OF SAMPLE: LIQUID g (

SAMPLE QUANTITY: 458.6000 UNITS: ML ,

/

SAMPLE GEOMETRY: L1500 EFFICIENCY. FILE NAME: VANEFF.L1500 . I

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r+ * * :4 4- FWHM(1332)

ACQUIRE DATE: 29-JUN-87 09:2n:10 2.299-PRESET TIME (LIVE): 3600. SEC + SENSITIVITY: 5.000 ELAPSED REAL TIME: 3601. SEC

SHAPE PARAMETER : 10.0 % .,

-ELAPSED LIVE TIME: 3600. SEC

NBR ITERATIGNS: 10.

* + * * * * :+: 4 * * * * * * * * *

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4, 4 4 DETECTOR: NRC GE 80 4 LIBR ARY: NUC L . MASTER 1 CALIB DATE: 2e..JUN-37 10:30:59

ENERGY TOLERANCE: d.900KV l

HALF LIFE RATIO: 8.00 j KEV /CHNL: 0.4599891

-OFFSET: 0.3067306 KEV

ABUNDANCE LIMIT: 80300%

0. COEFF. : -1.467E-08 KEV /r++2 +

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. ENERGY WINDOW 4.99 TO 2759.33 l

F4 1T ENERGY AREA BFGND FWHM CHANNEL LEFT PW CTS /?EC '4ERP FIT 1 1 30.87 281. 826. 1.54 6A.27 62 9 7. C 1E-CO 20.1 8.58E-01 l l

2 1 35.64 209. 599. 1.60 75,so /1 9 5.91E-02 22.8 1.37E 00 !

3 1 81.30 10694. 1671. 1.38 175.90 169 15 2.97E 00 1.3 4.8AE 00 l 4 1 320.46 148. 176. 1.61 695 $5 689 13 4.1;;E-02 21.3 3.27E-01 j 5 1 497.48 164. 190. 1.53 1000.70 1075 15 4.57E-02 19.4 2.59E 00 j 1 511.75 535. 182. 3.36 1111.73 1103 22 1.49E-01 8.0 1.66E 00 l 7 1 558.41 98. 72. 1.95 1213.16 1207 12 2.73E-02 21.O 1.64E 00 8 1 724.58 144. 69. 2.18 1574.45 1567 16 4.01E-02 15.4 1.83E 00 9 1 757.38 121. 43. 2.22 1645.76 1641 13 3.37E-02 14.9 2.25E 00 l 10 1 766.21 162. 94. 2.37 1664.96 1655 19 4.50E-02 14.7 1.62E 00 )

11 1 811.26 411. 77. 2.09 1762.90 1752 19 1.14E-01 7.3 '

.67E 00 j 12 1 1121.69 109. 17. 5.26 2437.86 2430 10 3.04E-02 11.5 1.79E 01 l 13 1 1173.61 187. 28. 2.64 2550.76 2544 15 5.19E-02 10.7 2.06E 00 !

1A 1 1238.36 39. 5. 2.53 2691.55 ?686 10 1.08E-02 18.3 4,14E 00 1 6 es s. -.r 1e

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.... i ..ws:..-e, 16 1 1460.87 68. 10. 2.54 3175.37 3169 13 1.90E-02 13<9 3.ISE 00 17 1 1598.31 1e. 3. 1.46 3474.22 3473 5 4.43E-03 26.d: 5.?2E-02 li 1 1764.77 60. 10, 2.54 3836.18 3827 19 1.'b7E-02 19.O 6.35E-01 10 1 2613.78 3/. 4 :. . a.51 5682,46 S674 22 1.02E-02 27.7 2.92E-01 l l

' \

4 PEAK 3EARCH COMPLETED (REV *5.1) 1 PULSE-PILE-UP CGRRECTEL DATA. CORRECTION = 1.000 UNCORR. LIVE TIMEi 3600.CORRECYED LIVE TIME: 3600. l l l l PL IT ENERGY 5,REA BUGND FWHM !HANNEL LEFT PW CTS /$EC % ERR I 1

i i 1 30.87 281. 826. 1.54 66.27 62 9 7.81E-02 20.1

. 1 35.04 209. S99. 1.60 75.oc e1 9 5.81E-02 22.8 3 1 81.30 10694 1671. 1.38 175.9C 169 15 2.97E 00 1.3 I 4 1 320.46 148. 176. 1.61 695.85 689 13 4.12E-02 21.3 1 5 1 497.48 164. 190. 1.53 1080.70 1075 15 4.57E-O& 19.4 l

e 1 511.75 565. 182. 3.36 1111.73 1103 22 1.49E-01 8.O l 7 1 558.41 96. 72. 1.95 12a3.16 1207 12 2.73E-02 21.O 8 1 724.5? I44. 69. 2.18 1574.45 1567 16 4. 01 E -02 15. 4 6

1 757.38 121, 43. 2.22 1645.76 1641 1o a.o7E-02 14.9 10 1 766.21 162. 94. 2.37 1664.96 1655 19 4.50E-02 14.7 11 1 811.20 411. 77. 2.00 1762.90 1752 19 1.14E-01 7.3 12 1 1121.69 109. 17. 5.26 2437.86 2430 10 3.04E-02 11.5 13 1 1173.61 107. 28. 2.64 2550.76 2544 15 5.19E-02 10.7 14 1 1 2 3 8 . e e. 09. 5. 2.53 S:691.55 2686 10 1.08E-02 18.3 15 1 1372.60 203. 12. /. 28 2896.45 2888 16 5.63E-02 8.7 16 1 1460.87 68. 10. 2.54 3175.37 3169 13 1.90E-O'2 13.9 17 1 1598.31 lo. a. 1.46 3474.22 3473 5 4.43E-03 26.8 15 1 1764.77 60. 10. 2.54 3836.,18 3827 19 1.67E-02 19.0 19 1 2613.78 37. 15. 3.51 5682.46 5674 22 1.02E-02 27.7 PILE-UP C ORRECTION COMPLETED (REV 2) l

NUCU DE IDENTIFICATION' SYSTEM (REV 12/84)

NUOLID'E LINE ACTIVITY REPORT PAGE 1 ELAF"iED LIVE TIME: 3600. /.F?LE-UP CORRECTED)

FISSICIN GAS 1 SIGMA NUCLIDE $bHR EtF.RGY AREA BMGND %ABN 2EFF UCI / UNIT ERROR "xE-133 FG S0.99 10694. 1671. 36.70+: 1.203E 00 9,833E -5 1.296E -6 j i

ACTIVATION PRODUCT 1 SIGMA NUCLIDE EBHP ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROC l F-18 AP 511.00 535. 182. 96.73* 5.341E-01 2.272E 21 1.828E.20 J CR-51 AP 320.08 148. 176. 9.83? 8. 076E -01 3.634E -6 7.748E -7 j CO-58 AP 210.76 411. 77. 99.40* 3.572E-01 2.029E -6 1.483E -7 l CO-60 AP 1173,22 187. 28. 100.00 2.617E-01 1.173E -6 1.254E -7 l 1332.49 203. 12. 100.00* 2.356E-01 1.411E -6 1.228E -7 ;

AS~76 AP 559.10 98. 72. 44.70* 4.945E-01 % 598E -5 1.175E -5 j 1216.02 0. O. 3.84 0.000E-01 0.000E O 0.000E o l l

FISSION FRODUCT 1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND %ABN 7.EFF UCI / UNIT ERROR ZR-95 FP 724.18 144. 69. 43.70 3.937E-01 1.479E -6 2.278E -7 756.72 121. 43. 55.30* 3.790E-01 f

1.020E ~6 1.524E -7 {

NB-95 FP 765.79 162. 94. 99.81* 3.752E-01 8.110E -7 1.190E -7 j RU-103 FP 497.08 164 190. 89.00* 5.476E-01 6.236E -7 2 1.'08E -7 )

610.33 v. ,0. 5.60 0.000E-01 0.000E O 0.000E O RU-105 FP 316.50 {

0. O. 11.70 0.000E-01 0.000E O 0.000E O '

469.40 0. O. 17.50 0.000E-01 0.000E O 0.000E O 676.40 0. O. 16.70 0.000E-01 0.OOOE O 0.000E O 724.50 144. 69. 49.00* 3.937E-01 1.833E 5 2.824E 4 BA-133 FP 81.00 10694. 1671. 33.00 1.203E 00 4.418E -5 5.821E -7 302.84 0. O. 17.80 0.000E-01 0.000E O 0.000E O 356.00 0. O. 60.00* 0.000E-01 0,000E O 0.000E O 4

NATURAL PRODUCT 1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR I K-40 NP 1460.81 68. 10. 10.67* 2.186E-01 4.804E -6 6.685E 'l !

RA-226 NP 186.21 0. O. 3.28 0.000E-01 0.000E O 0.000E O I 241.98 0. O. 7.49 0.000E-01 0.000E O 0.OOOE O 205.21 0. O. 19.20 0,000E-01 0.000E O 0.000E O {

351.92 0. O. 37.20 0.000E-01 0.000E O 0.000E O l 609.31 0. O. 46.30* 0.OOOE-01 0.000E O 0.000E O 1 1120,29 0. O. 15.10 0.000E-01 0.000E O 0.000E O ]

1239.11 39. 5. 5.94 2.502E-01 4.278E -6 7.848E -7 1 1764.49 60. 10. 15.80 1.877E-01 3.310E -6 6.286E -7 l 2204.22 0. O. 4.98 0.000E-01 0.000E O 0.000E O I

. l i

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1 3

NUCLIDE fDENTIFTCATION SYSTEM (REV 12/G4)

NUCLIDE'LINE ACTfVITY REPORT PAGE 2 ELAP5ED LIVE TIME: 3600. (PILE-UP CORPECTED) y;4TU;t,L PRODUCT 1 SIGMA MUCL IDE $8HR ENERGY AREA BKGND %ABN % Effs UCI / UNIT ERROR TH-2T2 NP 238.63 0. O. 44.60 O.000E-01 O.0002 O O.000E O ,

338.32 0. O, 11 40 0.000E-01 0.000E O O.OOOE 0 j 727.1/ o. O. 11.80 O.000E-01 O.000E O O.000E O 583.14 O. O. 30.25 0 000E-01

. 0.000E O 0.000E 0 911.07 O. O. 27,70 0.000E-01 O.000E O O.000E O 969.11 0. O. 1 c. 60 0.000E-01 0.000E 0 0.OOOE O 2614.66 37. 15. 35.G69 1.000E O2 1.684E -9 4.661E-10 i

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.J' NUCLIDE IDENTIFICATION SYSTEM (REV 02/84) -

UNUNOWN LINE PEPORT PAGE 3

' ELAPSED LIVE TIMF 3600. (PILE-UP CORRECTED)

LIf1ES NOT LISTED IN LIBRARY PK IT ENtiRGY AREA BKGND FWHM C HANNEL LEFT .PW CTS /SEC '4 ERR %EFF 1

1 1 1 30.87 281. 826. 1.54 66.27 c.2 9 7.81E-02 20.1 O.00E-01 1 2 1 35.04 209. 599. 1.60 75.33 71 9 5.818-02 22.8 O.00E-01 l 12 1 2 1l'1.69 109, 17. 5.26 2437.86 2430 10 3.04E-02 11.5 2.72E-01 17 1 1598.31 16. 3. 1.46 3474.22 3473 5 4.43E-03 26.8 2.03E-01 l

I LINES NOT MEETING GUMMARY CRITERIA )

Ft:: NUCLIDE ENERGY HALFLIFE DECAY UCI / UNIT ABNDIFF FAILED !

3 BA-133 81.00 1. 050E 01Y 1.001E O 4.418E -5 29. 7P*, A9N l 6 F-18 511.00 1.097E 02M 1.341E 27 2.272E 21 100.t.N.C. DCY l 8 RU-105 724.50 4.440E 00H 1.498E 11 1.83?E 5 51.63% DCY3ABN I 14 RA-226 1238,11 1.600E 03Y 1.000E O 4.278E -6 14.00% ABN l i 18 RA-226 1764.49 1.600E 03Y 1.000E O 3.310E ~6 14.00% ABN 1 l 19 TH-232 2614.66 1.000E 10Y 1.000E O 1.6S4E -9 20.12% ABN j l

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LyNUCLIDC IDENTIFICATION SYSTEi1 (REV 12/84) .)

SUMi%RY OF NUCLIDE ACTIVITY PAGE 4 i l

l TOTAL LINES IN SPECTRUM 19 -

4 LINE?. NOT LISTED IN LIERARY 4 l

'IDE~TIFIED IN

SUMMARY

REPORT 11 57.89% d i

FI.:3 ION GA9 1-SIGMA ]

NU.ulDE 5BER HALFLIFE DECAY UCI / UNIT ERRbR '4 ERR 1

@ 133 FG 1.259E O2H 2.479 9.893E -5 1.296E -6 1.32 'l l

1 ACTIVATION PRODUCT ;

1-SIGMA 1%CLIDE t

BfMN HALFLIFE DECAY UCI ' UNIT' ERROR % ERR C E -51 AP 2.770E i1D 1.18/ .:. . : 3 4 E -6 7.748E -I 21.32 i CO-35 AW- 7.05'E J 01D 1.070 2.029E -6 1.483F -7 7.31 l F O .i.O AP 1.925E 03D 1.002 1.411E ~6 1.228E -7 8.71 1

-._ : -- 7m ^ A r v h m 4- ;.. . 3 r, .;.E- -5 1_17sc .- s ^ O _ :< 3 A'! 4 6 '?

d ~)

l F155JON PRODUCT 1-SIGMA NUCLIDE SF4HR HALFLIFE DECAY UCI / UNIT ERROR %ERS ,

ZR-95 FP 6.402E 01D 1.077 1.020E -6 1.524E -7 14.94 I NB-95 FP 3.506E 01D 1.145 8.110E -7 1.190E -7 14.68 RU-103 FP 3.935E 01D 7,.129 6.236E -7 1.208E -7 19.37 N.:.TURAL PRODUCT '

l 1--SIGMA ;

l NUCLIDE ::.BHR HALFLUE DEC4Y UCI / UNIT EPROR .'/.E R P ,

l K-a0 NP 1.277E 09Y 1.000 4.004E -6 6. 685E --7 13.92 l l

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44..e+44*:v*c44ee+4 29_..JUN 87 13:29:37 ococetc e $c e-4too 64

.o . + 44 e e e + c + + c. 4 m e + 4 t .t + :, + + 4 e :c e 4 + + m c ecy +4 4.e v 4. +4 o m # + 44.v .t 4 6.c <

i POINT BEACH DEMINERALIZED FLUSH LINE SAMPLf' REFILLED BOTTLE l

SAMPLE DATE: 2 J - JUf ME:7 13:00:00 I SAMPLE IDENTIFIC ATION: 87-256 ?

f !'

TYPE OF SAMRLE: LIOUID lW.It /e SAMPLE OUANTITY: 458.6000 UNITS: ML /

SAMPLE GEOMETRY: L1500 EFFICIENCY FILE NAME: VANEFF.L1500..

t t + * * * * * * * * + 4 4 t

t 4 4 4 4 S $ 4 $ 4 * * * * + 4 4 4 4 4 4 *

4,+: 4 4 4 4 4.r t $ t * * + S 4 4 O

4 + 4 4

ACOUIRE DATE: 29-JUN-87 11: 28:_12._,

F WHM ( 1372) 2.299 PRESET TIME (LIVE): 7200. SEC

SENSITIVITY: 5.000 I ELAPSED REAL TIME: 7203. SEC

SHAFE PARAMETER : 20.0 % l ELAPSED LIVE TIME: 7200. SEC + NBR ITERATIONS: 10. l t

4 4 4 * * * * * $4 4 $ 4 4

t t t $ t t:+ * * * * *t t 4 4 04. . f..t t$ 4 4 4 $4 4 44$ 4 t t

4 t t a S + 4 $ $4 m l DETECTOR: NRC CE 80

LIBRARY NUCL. MASTER l CALIB DATE: 25 -JUN-87 10:30:59

ENERGY TOLERANLE: 0.900KV i

FEV/CHNL: 0.4599891 . HALF LIFE RATIO: 6.00 l OF 5ET: 0.3867306 KEV

ABUNDANCE LIMif: 80.00%

0. COEFF. : -1.467E-08 KEV /C442 4 4

i j 4 + . r 0 + + + 4 4 4 4 4 4 + + t + 4 4 4 * *4 4 4 + + + 4 4 t 4 + 4 4 + *

4 4 44 4 g 4 5;4.p 4 4 4 4 4 44 4

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.. . -. . .. ._.. ~..,.........._. ._

ENERGY WINDOW 4.99 TO 2759.31 E IT ENERGY AREA BUGND FWHM C HANNEL LEFT PW CTS /SEC % ERR FIT I 1 30.57 539. 2263. 2.16 65.66 60 12 7.49E-02 18.4 6.76E-01 2 1 34.94 307. 1225. 1.72 75.12 72 9 4.26E-02 22.0 1.67E 00

? 1 81.31 20928. 3494. 1.43 175.92 168 14 2.91E 00 0.9 1.43E 01 4 1 320.60 28/. 327. 1.48 696.15 691 11 3.99E-02 13.5 1.41E 00 5 1 497.54 409, 277. 1.92 1080.83 1074 15 5.68E-02 10.3 3.40E 00' 6 1 511.71 860. 413, 2.94 1111.63 1102 21 1.19E-01 6.8 1.29E 00 7 559.00 149. 207. 1.88 1214.45 1210 1 l'2 2.07E-02 21.8 1.96E 00 )

5 1 724.54 150. 115. 1.78 1574.35 1570 11'2.08E-02 16.4 1.28E 00 1 9 1 757.06 255. 116, 2.06 1645.07 1637 15 3.55E-02 11.7 8.58E-01 i 10 1 766.lo 347. 143. 2.18 1664.86 1659 19 4.82E-02 9.9 6.92F-01

{

.1 1 811.15 800. 129, 2.00 1762.67 1756 17 1.11E-01 4.8 1.99E 00 1 12 1 1173.46 390. 64. 2.27 2550.43 2542 17 5.42E-02 7.5 1.56E 00 l

!? 1 1332.5/ oo5. 61. 2.22 2896.39 2888 21 4.65E-02 8.2 5.81E-01 14 1 1377.85 80. 22. 3.63 2994.83 2987 15 1.11E-02 20.4 2.17E 00 15 1 1460.90 158. 26. 2.82 3175.4'2 3167 17 2.19E-02 11.6 1.16E 00 1 16 1 1764.23 121. 23. 2.65 3835.00 3829 13.1.68E-02 12.7 2.96E 00 !

17 2 2612,36 21. 12. 1.68 5679.36 5672 '24 2.95E-03 37.8 1.27E 00 l

18 2 2614.Se. 36. 7. 1.68 5684.81 5672 24 5.01E-03 24.7 j

PEAK SEARCH COMPLETED (REV 15.1) l l PULSE-PILE-UP CORRECTED DATA. CORRECTION = 1.000 1 UNCORR. L1VE TIME: 7200.CORRECTEL LIVE TIME: 7199.

IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR 1 1 30.59 339. 2263. 2.16 65.66 60 12 7.49E-02 18.4 2 1 34.94 307. 1225. 1.72 75.12 72 9 4.26E-02 22.0 3 1 81.31 20928. 3484. 1.43 175.92 168 14 2.91E 00 0.9 l 4 1 320.60 287. 327. 1.48 696.15 691 11 3.99E-02 13.5 l

5 1 497.54 409. 277. 1.92 1080.83 1074 15 5.68E-02 10,3 1 6

~'

1 S11.71 860. 413. 2.94 1111.63 1102 21 1.19E-01 6. 8 1 559.00 149, 207. 1.88 1214.45 1210 12 2'.07E-02 21.8

! 1 724.54 150, 115. 1.78 1574.35 1570 11 2.08E-02 16.4-9 1 757.06 255. 116, 2.06 1645.07 1637 15 3.55E-02 11.7 10 1 766.16 347. 143. 2.18 1664.86 1659 19 4.83E-02 9.9 11 1 t311.15 800. 129. 2.00 1762.67 1756 17 1.11E-01 4.8 l

1 l' 1 1173.4o o90. 64 2.27 2550.43 2542 17 5.42E-02 7.5 I l 13 1 1332.57 335. 61. 2.22 2896.39 2888 21 4.65E-02 8.2 14 1 1377.85 80. 22, 3.63 2

'994.83 2987 15 1.11E-02 20.4 15 1 1460.90 158, 26. 2.82 3175.42 3167 17 2.19E-02 11.6 16 1 1764.23 121. 23. 2.65 3835.00 3829 13 1.68E-02 12.7 17 2 2612.36 21, 12. 1.68 5679.36 5672 24 2.95E-03 37.8 18 2 2614.86 7.

36. 1.68 5684.81 5672 24 5.01E-03 24.7 I

PILE-UP CORRECTION COMPLETED (REV 2) l l

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1

1 NUCLf DE 7DENTIFIC ATION ' SYSTEM (REV 12/84) l NUCLIDE L2NE ACTIVITY REPORT PAGE 1

" ELAPSED LIVE TIME: 7199. (PILE-UP CORRECTED) 1 1

FISSION GAS i i SIGMA NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR XE-133 FG 80.99 20928. 3484. 36.70+ 1.203E 00 9.762E -5 8.957E -7 i

l ACTIVATION PRODUCT 1 SIGMA NUCL1DE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR F-18 AP S11.00 860. 413. 46.73* 5.342E-01 4.869E 21 3.326E 20 CR-51 AP 320.08 28/. c27. 9.834 8.073E-01 3.5'28E -6 4.779E -7 i CO-58 AP 810.76 800. 129 99.4O* 3.572E-01 1.975E -6 9.555E -8 l (0-60 AP 1173.22 390. 64. 100.00 2. 61'7E-01 1.2?4E -6 9.194E -e l 1332.49 335. 61. 100.00* 2.356E-01 1.166E -6 9.560E -8 l AS-76 AP 559.10 149 207. 44.70* 4.941E-01 4.549E -5 9.908E -6 1216.02 O. O. 3.84 0.OOOE-01 0.OOGE 0 0.COOE O

]

I FISSION PRODUCT !

\

1 SIGMA i NUCLIDE SBHR ENERGY AREA ,BKGND %ABN %EFF UCI / UNIT ERROR )

ZR-95 FP 724.18 150. 115. 43.70 3.938E-01 7.V'OF -7 1.262E ~7 )

I 756.72 255. I16. 55,30* 3.791E-01 1.075E -6 1.253E -7 NS-95 FP 765.79 347. 143. 99.81* 3.752E-01 8.717E -7 8.672E -8 RU-103 FP 497.08 409. 277. 89.00* 5.476E-01 7.771E -7 8.035E -8 610.33 0. ,G. 5.60 0.000E-01 0.000E O O.OOOE O PU-105 FP 316.50 0. O. 11.70 0.OOOE-01 0.000E O' O.OOGE O 469.40 0. O. 17.50 O.OOOE-01 0.OOOE O o.OOGE O !

67o.40 0. O. 16.70 0.000E-01 0 000E O 0.OOOE O 724.50 150. 115. 49.00* 3.938E-01 1.432E 5 2.352E 4 BA-133 FP 81.00 20928. 3484. 33.00 1.203E 00 4.323E -5 3.966E -7 302.84 0. O. 17.80 O.000E-01 0.OOOE O O.000E O 356.00 O. O. 60.00* O.OOGE-01 0.000E O 0.000E O NATURAL PRODUCT 1 SIGMA j NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR i K-40 NP 1460.81 138, 26. 1O.67+ 2.186E-01 5.541E -6 6.402E -7 l RA-226 NP 186.21 0. O. 3.28 0.000E-01 0.GOCE O O.OOGE O 241.98 O. O. 7.49 0.000E-01 0.GOCE O O.OOOE O 295.21 0. O. 19.20 0.GOOE-01 O.OOOE O O.000E O 351.92 0. O. 37.20 O.000E-01 0.000E O O.000E O 609.31 0. O. 46.30+ 0.000E-01 0.000E O 0.000E O 1120.29 0. O. 15.10 0.OO0E-01 0.OOOE O 0.OOOE O 1238.11 O. O. 5.94 0.OOOE-01 O.000E O 0.OOGE O 1764.49 121. 23. 15.80 1.878E-01 3.337E -6 4.241E -7 2204.22 Oa O. 4.98 0.000E-01 0.000E O O.000E O

i NUC L T IE IDENTIFICAT10N SYSTEM (RE C12/84)

'NUCLIDE LINE ACTIVITY REPORT PAGE 2

'ELAP5ED LIVE TIME: 7199. (PILE-UP CORRECTED)

-NATURAL FRODUCT 1 SIGMA NUCLIDE SBHP ENERGY AREA BLGND %ABN %EFF UCI / UNIT ERROP '

TH-232 NP 238.63 0. O. 44.60 0.000E-01 0.000E O 0.000E O 338,3'2 0. O. 11.40 0.000E-01 0.000E O 0.OOOE O 727.17 0. G. 11.80 0.000E-01 0.OOOE O 0.000E O 583.14 0. O. 30.25 O.000E-01 0.000E O O.000E O 911.07 0. O. 27.70 0.000E-01 0.000E -0 0.000E O 969.11 0. O. 16.60- 0.000E-01 0.000E O 0.000E O 2614.66 36. 7. 35.86* 1.000E 02 8.233E-10 2.035E-10 l

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NUCLIDE IdENTIFICAT!ON SYSTEM (REV 12/84) -

-uni'NOWN LINE FEPORT PAGE 3

' ELAPSED LIVE TIME. 7199. (PILE-UP CORRECTED)

LINES NOT LISTED IN LIBRARY q PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR */.E F F i

1 1 30.59 539. 2263. 2.16 65.6e 60 12 7.49E-02 18.4 0.00E-O! l 2 1 34.94 307. 1225, 1.72 75.12 72 9 4.26E-02 22.O O.00E-01 1 11 1 1377.85 80. 22. 3.63 2994.83 2987 15 1.11E-02 20.4 2.29E-01 17 2 2612.36 21. 12. 1.68 5679.36 5672 24 2'.95E-03 37.8 0.OOE-01 LINES NOT MEETING

SUMMARY

CRITERIA i PK NUCLIDE ENERGY HALFLIFE DECAY UCI / UNIT ABNDIFF FAILED i 3 BA-133 81.00 1.050E 01Y 1.OO1E O 4.323E -5 29.78% ABN 6 F-18 511.00 1.097E O2M 3.574E 27 4.869E 21 100.00% DCY 8 RU-105 724.50 4.440E GOH 2.252E 11 1.432E 5 51.63% DCY.ABN 16 RA-226 1764.49 1.600E 03Y 1.OOOE O 3.337E -6 10.17% ABN 18 TH-232 2614. 6/c 1.000E 10Y 1.OOOE O 8.233E-10 20.121. ABN l

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NUC LIbE ' IDENTIFICATION SYSTEM (REV 12/84) -

SUMr$RY OF NUCLIDE ACT1VITY PAGE 4 TOTAL LINES IN SPECTPUM 18 LINES NOT LISTED IN LIBRARY 4 .,

IDENTIFIED IN

SUMMARY

PEPORT 11 61.11%

FI$$ ION GAS 1-SIGMA NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR */.E R R YE-133 FG 1.259E O2H 2.515 9.762E -5 8.957E -7 0.92 ACTIVATION PRODUCT 1-SIGMA NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR %ERP CR-51 AP 2.770E 01D 1.191 3.528E -6 4.779E -7 13.55 CO-58 AF 7.080E 01D 1.0~1 1.775E -6 9.555E --8 4.84 l CO-60 AP 1.925E 03D 1.003 1.166E -6 9.560E -8 8.20 era Ar ? m 2E 11 ' : 02.243 -, . : e t -5 9.FOCE 2 21. ~C -- a n c eu,4ca..id i

FISSION PRODUCT I 1-SIGMA NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR ~4 ERR i ZR-95 FP 6.402E 01D 1.078 1.075E -6 1.253E -7 11.66 l NS-95 FP 3.506E 01D 1.148 8.717E -7 8.672E -8 9.95 RU-103 FP 3.935E OID 1.131 7. 7 -" 1 E -7 8. 035E --8 10.34 i

l NATURAL PRODUCT i i

1-SIGMA !

NUCLIDE SBHP HALFLIFE DECAY UCI / UNIT ERROR % ERR I K-40 NP 1.277E 09Y 1.000 5. 541 E --6 6.402E -7 11.55

4 g m_____ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - . -

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,.: POINT BEACH' DEMINERALIZED FLUSH'LINE SAMPLE POU. RED INTO:R,3 GEO

' SAMPLE;DATE: 22 .JUN-87 't3:00:00 /

SAMPLE' IDENTIFICATION: 87-255 ,,-' , W. # " ! , ,.

' TYPE OF SAMPLE: LIQUID

' SAMPLE QUANTITY: '458.6000 UNITS: ML j., ,.m "

r LSAMRLE GEOMETRY: L1500 EFFICIENCY FILE NAME: VANEFF.LIS00..

- 44S****************************4.**************:t@*:+4*:t.**4****

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l-l 'ACOUIRE'DATE: 29 ,3UN-87 )3t49:38 *=FWHM(1332)- 2.299 PRESET TIME (LIVE): 4 200. SEC

SENSITIVITY: 5.000

' ELAPSED REAL' TIME: 7226. 'SEC

SHAPE PARAMETER : 10. O ".

ELAPSED LIVE TIME: 7 20'~ . SEC

NBR ITERATIONS: 10.

- - +:*yt**********+***********************************.+:***4.****

.4 DETECTOR: NRC GE 80 4 LIBRARY:NUCL. MASTER s CALIB DATE: 26 .JUN-87 10:30:59 e ENERGY TOLERANCE: O.900KV'

> KEV /CHNL: O.4599891 4 HALF LIFE RA~I0: 8.00 ' 1 OFFSET: 0.3867306 KEV

ABUNDANCE LIMIT: 80.00*4 l O.-COEFF. : -1.467E-08 REV/C+42

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PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 1, 1 19.66 426. 8685. 1.41 41.89 39 8 5.92E-02 38.1 6.97E-01

'2 1 30.90 656. 6174. 1.10 '66.34 64 7 9.12E-02 20.4 1.13E 00 3 1 35.52 1320. '7290. 2.65 76.37 71 10 1.83E-01 12.4 1.33E 00 4 1 81.28 38128. 15109. 1.47 175.86 167 16 5. 30E 00 O.9 2.57E 01 5 1 123.41 1157. 5978. 3.60 267.46 262 10 1.61E-01 12.7 6.89E 00 6 1 133.91 4142. 5898. 1.45 290.28 285 10 5.75E-01 3.8 2.20E 00 7 1 145.G5 5391. o687. 1.53 316.24 310 13 7.49E-01 3.5 2.22E 00 8 1 159.45 1880. 5413. 1.5/ o45.80 341 11 2.61E-01 8.0 2.11E 00 9 1 320.54 3069. 4182. 1.53 696.01 690 12 5.51E-01 3.6 6.53E-01 10 1 392.15 912. 3128. 1.67 851.71 845 12 1.27E-01 12.8 1.59E 00 l 11 1 428.33 256. 2071. 1.35 930.36 926 8 3.97E-02 28.8 1.75E 00 J 12 1 497.Sa .;875. 3361. 1.65 1080.84 1074 13 3.99E-01 4. 6 1.03E 00 13 1 511.57 12673. 5935, 2.84 1111.33 1101 25 1.76E 00 1.9 3.35E 00 14 1 603.11 633. 2959. 1.60 1310.35 1305 11 8.79E-02 17.1 4.77E-01 15 1 622.39 436. 1770. 1.52 1352.27 1348 9 6.06E-02 17.9 1.04E 00 16 2 658.30 923. 1783. 1.85 1430.34 1422 23 1.28E-01 9.6 3.08E-01 j 17 2 662,19 370. 1598. 1.70 1438.80 1422 23 5.14E-02 21.6 i' 18 1 724.60 3078. 1801. 1.83 1574.49 1567 15 4.27E-01 3. 5 1.41E 00 19 1 757.17 3624. 1720. 1.88 1646.31 1637 16 5.03E-01 3.I 1.84E 00 20 1 766.16 5743. 2167. 1.87 1664.92 1657 19 7.98E-01 2.4 1.65E 00 21 1 811.16 27524. 2138. 1.88 1762.69 1752 19 3.82E 00 O.7 4.76E 00 1 22 1 835.10 849. 1327. 1.87 1814.74 1809 14 1.18E-01 9.'8 1.07E 00 I 23 1 885.07 785, 1454. '2.52 1923.40 1917 15 1.09E-01 11.3 1.33E 00 l 24 1 937.71 385. 1601. 2.23 2037.85 2031 14 5. 35E-02 22. 7 9. 37E-01 25 1 1173.41 15836. 848. 2.12 2550.33 2538 22 2.20E 00 0.9 3.'93E 00 J 26 1 1291.63 125. 248. 2.39 2807.38 2798 21 1.74E-02 34.O 1.27E 00 27 1 1332.61 14091. 273. 2. ~21 2896.47 28G4 24 1.96E 00 0.9 5.29E 00 28 1 1384.48 186. 103. 2.49 3009.26 3002 17 2.58E-02 16.1 1.54E 00 29 1 1460.95 133. 105. 2.70 3175.53 3163 21 1.85E-02 23.O 1.06E 00 30 1 1504.84 91. 88. 2.20 3270.97 3265 13 1.26E-02 24.6 9.49E-01 31 1 1674.79 114. .o / . 3.10 3640.52 3633 15 1.55E-02 16.O 8.80E-01 32 1 1691.03 192. 34. 2.92 3675.84 3669 17 2-.66E-02 11.3 8.88E-01 33 1 17e4.08 104, 52. 2.83 3834.65 3825 23 1.45E-02 2*. 7 5.84E-01 34 1 2504,65 121. 16. 2.98 5445.12 5436 20 1.68E-02 11.O 7.39E-01 35 1 2613.73 87 O. 3.37 5682.34 5668 23 1.21E-02 12.2 1.90E 00 <

PEAK SEARCH COMPLETED (REV 15.1) 4 1

1 l

l l PULSE-PILE-UP CORRECTED DATA. CORRECTION = 1.001 '

i UNCORR. LIVE TIME: 72OO.EORRECTED LIVE TIME: 7189.

1 l

l Ph IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /5EC % ERR l 1 1 19.66 426. 8685. 1.41 41.89 39 8 5.93E-02 38.1 l 2 1 30.90 656. 6174. 1.10 66.34 64 7 9.13E-02 20.4 l 3 ,1 35.52 1320. 7290. 2.65 76.37 71 10 1.84E-01 12.4 l 4 1 81.28 38128, 15109. 1.47 175.86 167 16 5.30E 00 O.9 J 5 1 123,41 1157. 5978. 3.60 267.46 262 10 1.61E-01 12.7 133.91 290.28 ]

6 1 4142, 5898, 1.45 285 10 5.76E-01 3.8 ;

7 1 '45.85 1 5391. 6687. 1.53 316.24 310 13 7.50E-01 3.5 !

8 1 159.45 1880. 5413. 1.57 345.80 341 .11 2.61E-01 8.0 1 9 1 320.54 3969. 4182. 1.53 696.01 690 12 5.52E-01 3.6 1 10 1 392.15 912. 3128. 1.67 G51.71 845 12 1.27E-01 12.8 :

11 1 428.33 286. 2071. 1.35 930.36 926 8 3.98E-02 28.8 !

12 1 497.54 2875. 3361. 1.65 1080.84 1074 13 4.OOE-01 4.6 l 13 1 511.57, 12673. 5935. 2.84 1111.33 1101 25 1.76E 00 1.9 ,

14 1 oO3.11 633, 2959. 1.60 131O.35 1305 11 8.80E-02 17.1 _ l 15 1 622.39 436. 1770. 1.52 1352.27 1348 9 6.07E-02 17.9 l 16 2 658.30 ' 923. 1783. 1.85 1430.34 1422 23~1.28E-01 9.6 I 17 2 662.19 370. 1598. 1.70 1438.80 1422 23 5.15E-02 21.6 18 1 724760 r 3J78. 1801. 1 ~. 83 1574.49 1567 15 4.28E-01 3.5 l I

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19 i 757.17 5525. [E55. 1.55 -i545.'31 5557 55 5.b4E-bi 5~i 20 1, 766.19 5743. 2167 1.87 1664.92 1657 19 7.99E-01 2.4

'21 1 811.16 27524. 2138. 1.88 1762.69 1752 19 3.83E 00 0.7 2'2 1' 835.10 849. 1327. 1.87 1814.74 180'? 14 1.18E-01 9. 8 23 1 885.07 785. 1454 2.52 1923.40 1917 15 1.09E-01 11.3 24 1 937.71 385. 1601. 2.23 2037.85 2031 14 5.36E'-02 22.7 15 1 1173.41 15836. 848.. 2.12 2550.33 2538 22 2.20E 00 0.9 26 1 1291.63 125. 248. 2.39 2807.38 2798 2

'1 1.74E-02 34.0 27 1 1332.61 14091. 273. 2.21 2896.47 2884 24 1.96E 00 0.9 28 1 1384.48 186. 103. 2.49 3009.26 3002 l'7 2.58E-02 16.1 29 1 1460.95 133. 105. 2.70 3175.53 3163 21 1.85E-02 23.O 30 1 1504.84 91. 88. 2.20 3270.97-3265 13 1.26E-02 24.6 31 1 1674.79 114. oe. 3.10 3640.52 3633 15 1.58E-02 16.0 32 1 1691.03 192. 34. 2.92 3675.84 3669 17 2.67E-02 11.3 33 1 1764.08 104. 52. 2.83- 3834.68 3825 23 1.45E-02 21.7 34 1 2504.65 121, 16. 2.98 5445.12 5436 20 1.68E-02 11.0 35 1 2613.73 87. O. 3.37 5682.34 5668 23 1.21E-02 2 1'.2 PILE-UP CORRECTION COMPLETED (REV 2)

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i NUCLIDE IDENTIFf CATION SYSTEM (REV 12/84)

I

-NUCLIDE' LINE ' ACTIVITY REPORT' PAGE 1 ELAPiED LIVE TIME: 7189. 4 PILE-UP CORRECTED) ,

I l

FISSION C-AS 1 SIGMA NUCLIDE SSHR ENERGY AREA BUGND %ABN */.EFF UCI / UNIT ERROA KR-88 FG 196.32 0. 0. 26.00+ 0.OOOE-01 O.OOOE O O.OOOE O j 834,83 849. 1327. 13.00 3.484E-01 1.526E 13 1.488E 12 j 1529.77 0. O. 10.90 0.OOOE-01 O.OOOE O O.OOGE O 2195.84 0. O. 13.20 0.OOOE-01 O.OO0E O O.OOGE O 2392.11 O. O. 34.60 O.OOOE-01 O.OOOE O- O.OOOE O XE-133 FG 80.99 38128.- 15109. 36.704 1.202E 00 1.805E -4 1.611E -6 l

1 f4CTIVATION PRODUCT !

1 SIGMA ,

NUCLIDE SBHR ENERG'i AREA BKGND %ABN %EFF UCI / UNIT ERROR l F-18 AP 511.00 12673. 5935. 96.73+ 5.343E-O! 1.757E 20 o,c19E 21 CR-51 AP 320.08 3969 4182. 9.83+ 8.074E-01 4.894E -5 1.784E -6 MN-54 AP 834.93 849. 1327. 99.98+ 3.484E-01 2.028E -6 1.979E -7 FE-59 AP 192.34 0. O. 3.11 0.OOOE-01 O.OOOE O O.OOOE O 1099.22 O. O. 56.50+ 0.OOOE-01 O.OOOE O O.OOOE O ;

1291.56 125. 248. 43.20 2.417E-01 1.097E -6 3.728E -7 !

CO-58 AP 81O.76 27524. 2138. 99.4O* 3.572E-01 6.810E -5 4.955E -7 CO-60 AP 1173.22 15836. 848. 100,00 2.617E-01 4.973E -5 4.660E -7 1332.49 14091. 273. 100.00* 2.356E-01 4.915E -5 4.474E -7 AG-110M AP 657.75 9'2 3. 1783. 94.404 4.281E-01 1.909E -6 1.840E -7 677.61 0. O. 1O.68 O.OOOE-01 0.OOOE O O.OOOE O 1 686.99 O. ,0. 6.47 O.OOOE-01 0.GOOE O O.OOOE O 706.67 O. O. 16.68 O.OOGE-01 O.OOOE O O.OOOE O 763.90 v. v. 22.28 0.OOOE-01 O.GOOE O O.GOOE 0 818.02 O. O. 7.30 C.OOOE-01 0.OOOE O O.COOE O 884.67 785. 1454. 72.60 3.316E-01 2.726E -6 3.073E -7 937.48 385. 1601. 34.20 3.157E-01 2.983E -6 6.757E -7 1384.27 186. 103. 24.26 2.284E-01 2.799E ~6 4.504E -7 1505.00 91. 88. 13.06 2.134E-01 2.728E -6 6.709E -7 HALOGEN FISSION PRODUCT 1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR I-134 HFP 595.36 0. O. 11.40 O.OOOE-01 O.OOOE O O.OOOE O 621.79 436. 1770. 10.60 4.495E-01 1.403E 53 2.514E 52 ;

847.03 0. O. 95.41* O.OOGE-01 O.OOGE O O.OOOE O 884.09 O. O. 65.30 O.OO0E-01 O.OOOE O O.OOOE O ,

1072.55 O. O. 15.30 0.OOOE-O1 0.OOOE O O.OOOE O )

FISSION PRODUCT 1 SIGMA NUCLIDE 5BHR ENERGi AREA BKGND %ABN %EFF UCI / UNIT ERROR RB-89 FP 657.71 923. 1783. 1O.00 4. 281 E-0.t 3.OOOE193 2.892E192 947.69 O. O. 9.20 0.OOGE-01 O.OOOE O O.OOOE O 1031.88 0. O. 58.00* O.OOOE-01 O.OOOE O O.OOOE O 1248.10 O. O. 4'2.00 O.OOOE-01 0.OOGE O O.GOOE O 2196.00 O. O. 13.30 0.OOOE-01 O.OOOE O O.OOOE O 2570.14 0. O. 9.90 0.OOOE-01 O.OOOE O O.OOOE O l

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NUC L X DE 2 IDENTIFICATION SYSTEM (REV 12/84)

NUCLIDE. LINE ~ ACTIVITY REPORT PAGE 2 ELAP9ED LIVE TIME: 7189. (P1LE-UP CORRECTED)

FI~iiIOri PRODUCT 1 SIGMA NU:LIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR SR !2 / FP 241.52 0. O. 3.00 O.000E-01 0.OOOE O O.OOOE O 430.56 A. O. 3.30 O.OOOE-01 0.OOGE 0 0.GOOE O 953,39 6 O. 3.60 O.OOOE-01 0.OO0E O O.OOOE O 1142.30 O. 6 2.90. O.OOOE-01 O.OOOE O 0.OOOE O 1383.94 186. 103. 90.00* 2.284E-01 5.363E 12 8.629E 11 ZF 55 FP 724.18 3078. 1801. 43.70 3.937E-01 1.583E -5 5.596E -7 756.72 '624. 1720. 55.30* 3.791E-01 1.530E -5 4.742E -7 NE-95 FP 765.79 5743. 2167. 99.81* 3.752E-01 1.446E -5 3.41SE -7 NB-97D FP 657.90 923. 1783. 98.09* 4.281E-01 1.908E -3 1.839E -4 1024.50 O. .O. 1.08 0.OOOE-01 0.OOOE O O.OOOE O

/. RU-103 FP 497.08 2875. 3361. 89.00* 5.476E-01 5.478E -6 2.503E -7 !

610.33 0. G. 5.60 O.OOOE-01 O.OOGE 0 0.OOOE O RU-165 FP 316.50 0. O. 11.70 0.OOOE O.OOOE O O.OOOE O 469.40 O. O. 17.50 C.OOOE-01 O.OOGE O O.OOOE O 676.40 O. O. 16.70 O.OOOE-01 O.OOOE O O.OOOE O 724.50 3078. 1801. 49.00* 3.937E-01 4.258E o 1.505E 5 RU-106 FP 621.84 436. 1770. 9.80* 4.495E-01 8.225E -6 1.474E -6 f 1050.47 0. O. 1.73 O.OOOE-01 O.OOOE O O.OOOE O

-/ SN-113 FP 255.12 O. O. 1.93 0.OOOE-01 0.OOOE O O.OOOE O 391.69 912. 0128. 64.90+ 6.763E-01 1.777E -6 2. 283E --7 S5-124 FP 602,71 oo _m . 4"959. 97.87* 4.621E-01 1.245E -6 2.126E -7 645.85 O. O. 7.26 G.OOOE-01 0.OOOE O O.OOOE O 722.78 O. ,O. 11.10 0.OOOE-01 O.OOOE O O.OOGE O 1691.02 192. e4. 49.00 1.943E-01 1.791E -6 2.019E -7 SB-125 FP 176.33 O. O. 6.89 O.000E-01 0.OOOE O O.OOOE O 427.89 286. 2071. 29.33* 6. 254E- 01 1.283E -6 3.691E -7 463.38 O. O. 10.? i O.OOOE-01 O.OOOE O O.COOE O 600.56 0. O. 17.80 0.OOOE-01 O.OOOE O O.OOOE O 635.90 0. O. 11.32 O.OOOE-01 O.OOOE O O.OOGE O

/ Cs-137 FP 661.65 370. 1598. 85. l'2 + 4.259E-01 8.378E -7 1. 812E -7 BA-133 FP 81.00 39128. 15109. 33.00 1.202E 00 7.888E -5 7.042E -7 302.84 O. O. 17.80 0.OOOE-01 0.OOGE O O.OOOE O 356.00 O. O. 60.00* O.OOOE-01 0.OOOE O O.OOOE O V CE-141 FP 145.44 5391. 6687. 48.40* 1.416E 00 7.497E -6 2.592E -7

/ CE-144 FP 80.11 O. O. 1.60 0.OOOE-01 0.OOOE O O.OOOE O 133.54 4142. 5898. 10.80* 1.456E 00 2.196E -5 8.362E -7 i

NATURAL PRODUCT i i SIGMA l

, NUCLIDE SBHR ENERGY AREA BKGND %ABN %EFF UCI / UNIT ERROR K-40 NP 1460.81 133. 105. 1O.67* 2.186E-01 4.671E -6 1.075E -6 FA-226 NP 186.21 0. O. 3.28 O.OOOE-01 O.OOOE 'O O.OOOE O 241.98 0. O. 7.49 O.OOOE-01 0.OOOE O O.OOOE O 295.21 O. O. 19.20 O.OOOE-01 0.OOOE O O.OOGE O 351.92 0. O. 37.20 0.OOOE-01 O.OOOE O O.OOOE O 609.31 O. O. 46.30* O.OOOE-01 O.GOOE O O.OOOE O 1120.29 O. O. 15.10 O.OOOE-01 O.OOOE O O.OOOE O 1238.11 O. O. 5.94 O.OOOE-01 0.OOOE O O.OOOE O 1764.49 104. 52. 15.80 1.878E-01 2.886E -6 6.268E -7 2204.22 O. O. 4.98 O.OOOE-01 O.OOOE O O.GOOE O l

I NUCLIDE IDENTIFICATION SYSTEM (REV 12/84) l UNKNOWN.LINE REPORT PAGE 3 EL'AP5ED LIVE TIME 7189. (PILE-UP CORRECTED) ,

~

l LINES NOT LISTED IN LIBRARY l PV IT ENERGY AREA BFGND FWHM CHANNEL LEFT PW CTG /SEC % ERR %EFF 1 1 19.66 426. 8685. 1.41 41.89 39 8 5.93E-02 38.1 O. ODE-01 1 2 1 30.90 656. 6174 1.t0 66.34 64 7 9.13E-02 20.4 0.OOE-01 !

3 1 35.52 1320, 7290. 2.e5 76.37 71 10 1.84E-01 12. 4 O. OOE-01 I 5 1 2 l'3.41 1157. 5978. 3.60 267.46 262 10 1.61E-01 12.7 1.48E 00 E 1 159.45 1880. 5413. 1.57 345.80 341 .11 2.61E-01 8.O 1.36E 00 31 1 1674.79 114 3/. 3.10 3640.52 3633 15 1.58E-02 16.0 1.46E-01 34 1 2504.65 121. 16. 2.98 5445.12 5436 20 1.68E-02 11.0 1.43E-01 l 35 1 2613.73 87. O. 3.37 5682.34 5668 23 1.21E-02 12.2 0.COE-O! l LINES NOT MEETING

SUMMARY

CRITERIA Pi NUCLIDE ENERGY HALFLIFE DECAY UCI / UNIT ABNDIFF FAILED 4 BA-133 81.00 1.OSCE 01Y 1.001E O 7.888E -5 29.78*e. ABN 11 SB-125 427.So

770E OOY 1.OOSE O 1.283E -6 38.75% ABN 13 F-18 511.00 1.097E O2M 8.741E 27 1.757E 23 100.00% DCY l 15 I-134 621.79 5.260E 01M 1.870E 58 1.403E 53 5.35% DCY,ABN l 1 <- RB-89 657.71 1.544E 01M 1.698E198 3.OOOE19e /.02% DCY,ABN l 16 NB-97D 657.90 1.690E 01H 1.059E 3 1.908E -3 98.91% DCY l 16 AG-110M 657.75 2.499E O2D 1.020E O 1.909E -6 79.00% ABN l 18 RU-105 724.50 4.440E OOH 3.256E 11 4.258E 6 51.63% DCY,ABN l 22 KR-88 834.83 2.840E OOH ,9.934E 17 1.526E 13 13.31% DCV,ABN i l 23 AG-110M 884.67 2.499E O2D 1.020E O 2.726E -6 79.00% ABN I 24 AG-110M 937.48 2.499E O2D 1.020E O 2.983E -6 79.003. ABN !

26 FE-59 1291.56 4.463E 01D 1.116E O 1.097E -6 42.02% ABN I

2. E 5R-92 1383.94 2.710E OOH 7.249E 18 5.363E 12 87.55% DCY l 22 AG-110M 1384.27 2.495E O2D 1.020E O 2.799E -6 79.00% ABN 30 AG-11OM 1505.00 2.499E O2D 1.020E O 2.728E -6 79.00% ABN 33 RA-226 5764.49 1.600E 03Y 1.OOOE O 2.886E -6 10.17% ABN l 4

l

NUCLfDE IDENTIFICATION SYSTEM (REV 12/84) -

SUMMARY

OF NUCLIDE ACTIVITY- PAGE 4

' TOTAL LINES IN SPECTRUM 35 LINE9 NOT LISTED IN LIFRARY 8 I IDENTIFIED IN

SUMMARY

FEPORT 18 51. 4 3*/.

FI5EION GA9 1-SIGMA NUCLIDE $BHR HALFLIFE DECAY UCI / UNIT ERROR '4 ERR XE-133 FG 1.259E O2H 2.548 1.805E -4 1.611E -6 0.89 ACTIVATION PRODUCT 1-SIGMA NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR % ERR CR-51 AP 2.770E 01D 1.194 4.894E -5 1.784E -6 3.65 MN-54 AP 3.127E O2D 1.016 2.028E -6 1.979E -7 9.76 CO-58 AP 7.080E 01D 1.072 o.810E -5 4.955E -7 0.73 CO-60 AP 1 925E 03D 1.003 4.915E -5 4.474E -7 0.91 FISSION PRODj"T 1-SIGMA NUC .. I DE 5BHR HALFL!~E DECAY UCI / UNIT ERROR %ERP ZR-05 FP 6.402E 01D 1.080 1.530E -5 4.742E -7 3.10 NB-95 FP 3.506E 01D 1.150 1.446E -5 3.418E -7. 2.36 RU-103 FP 3.935E 01D 1.133 5.478E -6 2.503E -7. 4.57 RU-106 FP 3.682E 02D 1.013 8.225E ~6 1.474E -6 _17.92 K-113 FP 1.151E O2D 1.044 1.777E -6 2.283E -7 12.84 SB-124 FP 6.O~10E 01D 1.085 ' 1.245E -6 2.126E -7 17.08 C5-137 FP 3.017E 01Y 1.000 8.378E = 1. 812E -7 21.63 CE-141 FP 3.25GE 01D 1.163 7.497E -6 2.592E -7 3.46 CE-144 FP 2.843E O2D 1.017 2.196E -5 8.362E -7 3.81 ]

l i

NATURAL PRODUCT 1-SIGMA l NUCLIDE SBHR HALFLIFE DECAY UCI / UNIT ERROR- % ERR I K-40 NP 1.277E 09Y 1.000 4.671E -6 1.075E -6 23.01

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+9.10E-04 NORMAL 03:25 NORMAL f 09: 35 +9.10E-04 ;

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+9.13E-04 NORMAL 10:25 NORMAL l 10 47 +9.09E-04 UNIT 007-05 9 LIQ in uCi/cc l TEN-MINUTE DETAIL HISTORY 10:47 19 JUN 87 <

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I l . i v. i.r e.1 i mi n or v not i f i r ni i ten i onut i t utes f.ifmLY not i r.e of events al Pi tMi l Fill

.ife1 en roiblit intesest si oni f i c anrn. 'l l m i ni'or ma ti on i s as initiali.

ir < . 6 , r ri s.si t liou l- veri f i cati on or ov a l n a t. .i on , and 2m b at,i c a l 1 y a:t I that i *:

I s e . o .n be i he im01 nn fij sl:a f f an thin date.

l .: i i i I. . t 111 c.r onni n F i er i r i c Prwrr Co. Li cencee Lmorgmocy C1 assi i I cal i t u n e Pr > i n t Elearch Ur ri t e. 1 & .' ... X _ _No l t i i c a l. i oi n of an Unusus) E criit Dot.l. eln :%6 0 '.111 . . A l t'r L Sitr Ar em Fmeronney

, _ FPner al IUr,er g en c.y

, Not A lip l i r.abl e l.iio I. i llnb',/f:H i1 N 1 1. 1 0t11 D l<r.l t A D E .I NTO I Al'.1: t t i t .l i j bhl i f u I a ir -e 'r i ' h /f i i a . m . ,u t el H : ', i2 n . in . t u 'i .h ine 19 .f 9R 7, afL.et completing a pt or r flio i .

'!,. rt i "r t,co qn ihr "H" &snel.P hul rj up tank to Iale Michioan through upecini i roi r li c.oi mi pruvided by th en, Nt o.. ] mar , tien l i c enum at tr.imptecl to f l ush oui i tic

.1 i . . . h ;. eps pMh inth r1t an r enr Lur as.d . e u p watnt. The pr aceduro c al ) red I r .r 1 i n e l i s i .. , t l r- line uninu tire Unje 1 h i n n at e r . When the opor ator star to(i the

i. uieo m.=l r t ip ici t e:>r p u m p ., valve i100, opened att t oma t i c a ) 1 y . This vn)vo

> 1.r o i n . il i t .i ec # 1 J e+. dote , ova t.or in hn mi n et.f wi t h the r mari nr make up wa t el I ( 'i i hd - Il'mh Appr rni mal +1 y ? ?. "., gal t erm of t in i t; I r cactor- coolant w a 's I p l rmr'd te. t -d o iti c h i o nr. , ~1 h n r e t r n c,e w et s nroni i nrod by 2RE229 thrit ? o nr"..i c e i m ir,r e,

ra;I r. .> r il n,nn i i nr .

ne l e i o ci / n.1 Thr highest 10 mi nuto aver age 4,gr the rel ease was '. 8 5 tra the al ar m ont poi nt i r, 7.43 ' 10 mi cr o ri /ml baned nn L. h e le ..Ii<.)<..,i s., I I; I i i unrg ' lor.hntcn1 Sper. i f J t a t 1 on for 11a::1 stium Per mi snt bl e il' " reit e ni i tin inf Co .a t t h e U ni t'ano p oisit . ~l he l i censen decl ared .nrirl nec ur ral I i e .n. ,n u n n ea i n i rw e'n L at t t "? : ' ? a , m . nnd matic tlie necessary not i f i t. at i t .n'. . Ilin lie i i r .no ja t id l e ece ornb r.nmp i cua a t. l'lin Lii sc har ge, p oi n t. os a backup.

l ( H l t /'.( ' I

I/ . n6 f H j P49 i r, R.I. }lngue

'. I . ' I hi I's # h I ( /) l li ) '/ "J}- 7. '.U')

h l ' , I I . l 141.1 i l i st i:

'I. 1t. I Dil NHR f/W Wiliste flai l s (iiiH : l' l it e tinn ii mnn inch PA 10 N1155 dol'r 1 r m i oan!

i t urati, linhnr i r. E l.. D ' 010 RFS i i .uim . th e r 1 *. t. i n u MllD NRC Ups Utr , _ . ,

t ^. o.aa . Inrnthat I . < ui.in . Ci.o r GP _ . _ ,

Hegional Officen .

of le . I i

' .I t i IN11) , NSAU ,_,

j i# RIJl Recident fif f i ro i l 'lif e iicromrc: , ,

(Corp. O f -f i e t* - Reactor L. i t . Unj j req 2on 11I Rev. November J c?Hb Fon - tM17 4/3

~

PRELIMINARYNOTIFICATIONOFEVENTORUNUSUALOCCURRENCE--PNO-III-8I-84DateJune 19, 1937 4 l

' This preliminary notification constitutes EARLY notice of events of POSSIBLE safety

)

or public interest significance. The information is as initially received without fSA verification or evaluation, and is basically all that is known by the Region III staff on this date. ,

l l

Facility: Wisconsin Electric Power Licensee Emergency Classification:

Company X Notification of an Unusual Event i Point Beach Units 1 & 2 Alert Two Rivers, WI 54241 Site Area Enargency {

General Emergency l Docket Nos. 50-266; 50-301 Not Applicable !

1

Subject:

RELEASE OF PRIMARY COOLING WATER INTO LAKE MICHIGAN l l

Between 8:40 and 8:52 a.m. on June 19, 1987, approximately 235 gallons of Unit I reactor cooling water was discharged into Lake Michigan through the Unit 2 service water distharge.

The release exceeded the Technical Specification discharge limit (averaged over 10 mirutes),

but the primary water was diluted with additional service water flow and approximately 360,000 gallons per minute discharge from the condenser cooling water discharge. The total release was about 0.3 curies (beta-gamma). The release did not result in a significant safety or environmental hazard.

Both units were operating at 100 percent power at the time of the incident.

The release occurred when the licensee attempted to flush a line which had been used for the planned discharge of a waste holdup tank. The procedure called for using clean demineralized reactor makeup water for the flushing. When the makeup pump was started, however, a valve in the letdown system opened automatically and al? owed approximately 235 gallons of Unit I reactor cooling water to mix with the makeup water. This discharge was monitored by the Unit 2 service water discharge monitor. The release was about 58 percent over the 10 minute average discharge limit for radioactive liquids. The licensee terminated the release when an alarm was received on the Unit 2 service water discharge monitor. i i

The resident inspector is reviewing the circumstances of the release. The licensee declared an unusual event under its emergency p7an at 9:22 a.m. The classification was termincted at the same time, since the release had been stopped.

The State of Wisconsin will be notified.

Th-are has been local news media interest in this incident.

Region III (Chicago) was notified of this incident at 9:55 a.m. (CDT), June 19, 1987.

This informat ' urrent of 12 noon, June 19, / l CONTACT: e ay 3'8'8-5757) W. ce 88 DISTRIBUTION:

H. St. E00 NRR E/W Willste Mail: ADM:DMB Chairman Zech PA IE NMSS DOT:Trans only Comm. Roberts ELD OIA RES Comm. Asselstine AE00 NRCOpsCtrMD/

Comm. Bernthal Comm. Carr SP 3,W Regional Offices ACRS SECY CA INP0 8[ [$ NSAC 3. M '

RIII Resident Of ficp PDR Licensee: Jgy ,

, (Corp. Office - Reactor Lic. Only) e ne rt i4 Region III I

\ hi ON/ Rev. November 1986

_ _ _ _ _ _ ~

kL-lMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PH0-III-87-84 Date hune 19, 1987 lis preliminary notification constitutes EARLY notice of events of POSSIBLE safety

> public interest significance. The information is as initially received wfthout

rification or evaluation, and is basically all that is known by the Region III aff un this date.

sility: Wisconsin Electric Power Licensee Emergency Classification: {

Company X Notification of an Unusual Event i Pcint Beach Units 1 & 2 Alert Two Rivers, WI 54241 _

Site Area Emergency General Energency Docket Hos. 50 266; 50-301 Not Applicable Gject: RELEASE OF PRIMARY COOLING WATER INTO LAKE MICHIGAN Steen 8:40 and 8:52 a.m. on June 19, 1987, approximately 235 gallons of Unit I reactor {

eling cater was discharged into Lake Michigan through the Unit 2 service water discharge. 1 o release exceeded the Technical Specification disc 1arge limit (averaged over 10 minutes),

{

G the primary water was diluted with additional service water flow and approximately {

@,000 gallons per minute discharge from the condenser cooling water discharge. The tota) l

'leasewasabout0.3 curies (beta-gamma). The release did not result in a significant safety l

> environmental hazard.

Gb units were operating at 100 percent power at the time of the incident. j O ratesse occurred when the licensee attempted to flush a line which had been used for the Gnaed discharge of a waste holdup tank. The procedure called for using clean demineralized Qctor makeup water for the flushing. When the makeup pump was started, however, a valve in e letdown system epened automatically and allowed approximately 235 gallons of Unit I reactor j

@ ling water to mix with the makeup water. This discharge was monitored by the Unit 2 service j ter discharge monitor. The release was about 58 percent over the 10 minute average discharge att fer radioactive liquids, The licensee terminated the release when an alarm was received I the Unit 2 service water discharge monitor, j 1

Q resident inspector is reviewing the circumstances of the release. The licensee declared l unusual event under its emergency plan at 9:22 a.m. The classification was terminated at i o same time, stree the release had been stopped.

9 State of Wisconsin will be notified.

3re has benn local news media interest in this incident.

Bion lif (Chicago) was notified of this incident at 10:55 a.n:. (CST), June 19,1987.

Os information is current an of 12 6oon, June 19, 1987.

MTACT: R. DeFayette (FTS 388-5767) W. Guldemond (FTS 388-5574)

@TRIBUT!0N:

St. EDO NRR E/W Willste Mail: ADM:0MB 91rman Zech PA IE NMSS DOT:Trans only

m. Roberts ELD OlA RES Em. Asselstine AE00 Mic Ops Ctr am. Bernthal

m. Carr SP _ Regional Offices CY INPO NSAC Rl!I Resident Office 2 Licenseu ~ (Corp. Office - Reactor Lic. Only) fol/747-397 ggionIII _

4/f

l yll,,1.MINARY NullflCATION UT TVEN1 OR UNU5UAL Occ0RRENcL--PNO-ll!-87-84A Date: June 24, 1987 lhis preliminary notification constitutes EARL Y notice of events of POS$1BL E safety or publit Interest significance. The information is as initially received without verification or 2 valuation, nnd is basically all that is known by the Region 111 staff on this date.

p

'acility: Wisconsin E16ctric Power Company. Licensee Emergency Classification:

Point Beach Units 1 & 2 Notification of an Unusual Event Two Rivers. WI 54241

' Alert '

Site Area Emergency Docket No. 50-266; 50-301 Gcneral Emergency 1 Not Applicable Bubject:

RELEASEOFPRIMARYCOOLINGWATERINTOLAKEMICHIGAN(UPDATE)

Dn ilune 18,198/, approximately 235 galloniof Unit 2 reactor cooling water was discharged into Lake Michigan through the Unit 2 service water discharge. Preliminary indications were that the release exceedt.d the Technical Specification discharge limit.

l i

liter analy7ing the attual activity of the primary cooling water that w4s discharged during ]

this event, the licensee detent,ined that the cause of the alann on the serylce ster j Discharge m0nitor was due to the presence of entrained nobg gases. The alarm setpoint is i Msed on the maximum pennissible concentration (MPC) of0C0 in the effluent path. The l malysis of the actual water discharged indicates a Co equivalent activity of less than 3; !

sPC.

Thr activity of the noble gases entrained in the discharged water was several tagnitudes higher than the liquid activity. Using the applicable formula for the bobl6 gas ,

'elease it was calculated that en individual in the vicinity of the discharge pier would have '

w eived a whole body er.posure of .06 mrem. This is 3% of the heurly exposure limit for .an unrestricted area, the licens W s calculat ens were verified by the resident inspectors and the licensee's inelysis results will t>e confinned by the use of split samples sent to Region !!! for independeret verification.

The State of Wisconsin will be notified.

'here has been local news medib interest in tMS event.

fhisinformaponiscurr s of 11:00 a. ('T Jun 24, 1987.

n.

0NTACl: R. De ayett R. , Hague 312/790-576 414/755-?309

[

D15TRIBUT10N:

L St. EDO NRR E/W Willste Mail: ADM:DMB

hairman Zech PA IE mly WS5 DOT: Trans

own. Roberts ELD 01A RES

onn. Asseistine Af0D NRC Ops Ctr

om, Bernthal lonn. Carr SP _ . Regionoi Offices 40Y INFO _ NSAC _

a R!ll Resident Office Licensee: , _ , . . . (Corp. Office - Reactor iic. Only) gy,gp g y 7 Region Ill b Rev. November 198f 49% Wxn

~

Dluu I i 1,6 I Illillnir/ NI)f li i t :A i:tIIN f li i vi;H i- t if ,; ill.it M :11A1 lit:rt innt tir;i' f tiu j 1 l . n/ I;IA lh n

> n i ni psvnit iti mi piibonrl i cy intetest ontiiit I1on tr>1w.iiiaut significan , en EAI;LY notitP of evnntn of Pfl% Ilt! l lhe i nf ortantion i n as ini i.i a l l y

+t(

Iriciwie o s v5:d hv the t ii t Region hou t. vnr IIIi stafi f i cates ionthis or rval date, ual i on. and is basica)Iy al1 that in I m i I a i v: Idicrnocin F1ortric Power Co. L.icensee Emergenty C1annifieat)on I oi tit Beach Unitm 1 &

1)nr E n t r. :;%6 .?< 301

,,,__ _ Alert

__ Not i f i c ati co of an tJnucuta l Evcii t ili te orna Emerc.intity

. . . _ Uener al Emer gency Y

,_ JNot 4pp)icablo aih a nt t:

RFl.FAEE Ur FR}t1ARY UOfit I Nfl WA TER INTO LnkE (11CILIGAN (UPDATE) irl I i9 atini v:'i n to thP act mal art ivi ( y of the pr i mary cool .i ng water ihat wan

{ sti

' t ai-imlver

.ui qrd dur i ssa thi s event, t he 1,i r tnece deter mi ned that the cause of the rsili . i e n'rft hontdc <' cer vice water gates. Ih discher oe mnni tor wm, clue to the presem:c, of r i su r r n i i a t i tm i (flPC) of Co"p' al arm cp'not a t i v. bat,,2d on the aan i mu.s prrmi sci bi n ualer eli me. h ar e d i n d I r M a c, a in Un gn nfIluent path. One analysis of t. h e a c t. iia l equ i v m.l en t at t i vi t y of .1oss t.h a n 3% fif 'C.

ller nr l i v i l. V e4 f the noble gasor. entrainud in the discharged water was nseveral mioniiuties i l m- highnr ihan the 1 i qui d attivity. Uniog the Applicab1e Iormula iur inh.le onc rPleann ii I(itt uan cai r.ul ated that an individual in the vicini t y m Il ii s h nr.har or pinr would h.tive r et ni ved a tuhol r body exposure rd ,06 tryam.

i" o f the hour 1 v expor.orr2 1 i mi t for an unrentrictod ar ea.

II.n In:

tniI Ii<rnonrro etnf)rmnd cal cul by tbr e t iu,e onsofwor e po )socii t. rsampiec i ocI and the litonnon's anal ys t re, remuitu r o n t. Lo Region 1II f or e n,Ipl r'r nino i ver.i -f i t a t.1 or e ,

i, l u i l nf l : H. UrW a ynti c

.-l 3) ' ? ' s . n 7 /, .c H.l.. 1laguo c4j4) ; t,r,. 2 3 0 9 o lb il L UI)I f (IN:

11 ;t l ll' EDO NRR E/W Wil ) at e Mai): AllM: D l ~li s i e to.u i 7er le PA IE NMFiS Dill : iran snst t < . , <. m . b'ohr r i n ELD U1A I ' omin . OrnrI9tinP RES i i .viim . Irror : 11 lin i AFDD NRC Ops Ctr , , , . , , _ . , ,

t unne. Carr GP n 1." , _ _ . _ , Recipnal fif f i ctr e

'45 'e I N PO _ , . _ ,, ,

1A l JN A C _ _. _ , _ _,,

l 'lil ' RIII Res i rien t f. l f f i c e L i cen'. ora:

i (Curp. Officre - Reactor Lir. Onls Hegi on IJ1 Rev, Nevember ih Q$- n{ gm -/'.

[03.k

I7' M 7

/4

, _ _ _ _ _ _ _ _ . - _ . _ _ . . _ . . . - - - - - - ~ ~ - ~ - - - - - ' " ' ~ ' '

ML20236J737

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