ML20052E566

Testimony of Jf Schmitt Re Suffolk County Contention 28(a) (III) & Shoreham Opponents Coalition Contention 7A(3) on Iodine monitoring.Post-accident Iodine Monitoring Capability Exists to Measure Iodine Releases from Vent

ML20052E566
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	05/04/1982
From:	Schmitt J LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20052E543	List: ML20052E541 ML20052E551 ML20052E557 ML20052E566 ML20052E573 ML20052E577 ML20052E581 ML20052E587
References
ISSUANCES-OL, NUDOCS 8205110235
Download: ML20052E566 (13)

Text

9 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

)

LONG ISLAND LIGHTING COMPANY ) Docket No. 50-322 (OL)

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(Shoreham Nuclear Power Station, )

Unit 1) )

TESTIMONY OF JOHN F. SCHMITT FOR.THE LONG ISLAND LIGHTING COMPANY ON SUFFOLK COUNTY CONTENTION 28(a)(iii) AND SOC CONTENTION 7A(3) --

IODINE MONITORING PURPOSE This testimony demonstrates that there is a post-accident iodine monitoring capability at Shoreham to measure all iodine l releases from the station vent. LILCO has installed a l

post-accident iodine monitor in the station vent that will be accessible during and after an accident. This iodine monitor 1

is powered from a vital bus.

8205110235 820504

, PDR ADOCK 05000322 T PDR i

l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

)

LONG ISLAND LIGHTING COMPANY ) Docket No. 50-322 (OL)

)

(Shoreham Nuclear Power Station, )

Unit 1) )

TESTIMONY OF JOHN F. SCHMITT FOR THE LONG ISLAND LIGHTING COMPANY ON SUFFOLK COUNTY CONTENTION 28(a)(iii) AND SOC CONTENTION 7A(3) --

IODINE MONITORING

1. Q. Please state your name and business address.

A. My name is John Schmitt. My business address i s Long I land Lighting Company, Shoreham Nuclear Power Station, P. O. Box 628, Wading River, New York.

2. Q. What is your position with LILCO?

A. I am employed by LILCO as the Radiochemistry Engineer for the Shoreham Nuclear Power Station, i

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3. Q. Please state your professional qualifications.

A. My resume, which appears on pages 12-13, describes my professional qualifications. My familiarity with the issues raised in SC Contention 28(a)(iii) and SOC Contention 7A(3) stems from my present position. As Radiochemistry Engineer, I am responsible for assess-ing radioactive releases, including iodine, from the plant during normal and accident conditions. This function requires thorough familiarity with the sys-tems used to monitor releases.

4. Q. Mr. Schmitt, please explain briefly what SC Contention 28(a)(iii) and SOC Contention 7A(3) involve.

A. First, let me state that these two contentions, SC 28(a)(iii) and SOC 7A(3), are identical. My remarks throughout this testimony are equally applicable to both.

These contentions allege that LILCO does not satisfy all of the requirements of NUREG-0737, Item II.F.1 with regard to assessing radioactive iodine released from the station vent. As a result, it is claimed that Shoreham does not meet 10 CFR Part 50, Appendix A, GDC 13 a.id 64. In particular, the contention states that (1) LILCO's monitoring capability will Lat

Ebe available during and following un accident and (2) the sampling instruments LILCO intends to use are not powered by a " vital bus."

5. Q. What is required by NUREG-0737, Item II.F.1.?

A. Among other things, NUREG-0737, Item II.F.1 requires

" capability to collect and analyze representative sam-pies of radioactive iodines in plant gaseous effluents during and following an accident." As noted in NUREG-0737, on-line monitors for radioactive iodines are not considered to be practical. Item II.F.1. allows the use of continuous iodine samples with on-site analysis to meet its requirements as long as the equipment can accomodate a thirty minute sampling time.

6. Q. Please explain, in general, how radioactive iodine in Shoreham's effluent will be monitored.

A. Shoreham's design includes radiation monitors in the gaseous effluent streams cf the plant. These work by continuously withdrawing a sample of the release stream via a special sampling probe and passing it through a monitor. This sample stream is also contin-uously passed through a charcoal filter which traps almost all of the iodine in the stream. The amount of iodine emitted via that effluent stream can then be 1

determined by removing the charcoal filter and analzying it in the on-site laboratory facilities.

The two potential release paths to the atmosphere are the Station Vent Exhaust and the Reactor Building Standby Ventilation System (RBSVS) release point. On page 11 of this testimony is a diagram (FSAR Figure II.F.1-1) of the Shoreham gaseous release system show-ing the location of various monitors on both potential release paths.'

7. Q. Mr. Schmitt, let's go through the arrangements for monitoring iodine released from the station vent in detail.

A. We will use the charcoal filter associated with RE-042,l/ a low range monitor, to collect iodine sam-ples from the station vent during normal operation.

This filter is located on elevation 175 of the Reactor Building.

1/ Charcoal filters actually carry the designation PNL- .

They are associated with other radiation monitoring equipment carrying a corresponding RE- designation. For ease of reference to Figure II. F.1-1, I will use the RE- nomen-clature. It should be noted that there is one exception to this general rule. The low range station vent monitor is PNL-041, but it corresponds to the monitor marked RE-042. I will refer to it as RE-042 for ease of reference.

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Initially, LILCO planned to monitor radioactive iodine effluent under accident conditions by using RE-042 and, if it were inaccessible, by using the combined measurements of iodine discharged from the Turbine Building and the Radwaste Building to the Station Vent. Each of these streams has its own charcoal sample filter. In an accident situation, the Reactor Building Normal Ventilation System (RBNVS) would be secured and the Reactor Building Standby Ventilation System (RBSVS), with its own monitors, would be in operation. Thus, the Turbine Building and Radwaste Building streams would be the only input to the sta-tion vent.

i These contentions seem to allege that the plan just outlined is unacceptable because there might be ways l

for radioactive iodine to escape from the isolated Reactor Building into the station vent. Since RE-042 might not be accessible, this hypothetical leakage might not be monitored. The contentions further claim that the two instruments to be relied upon are not l

powered from a vital bus as allegedly required.

8. Q. Is there any basis for the complaint about the ability to monitor iodine in the station vent exhaust follow-ing an accident?

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7 A. No. LILCO has upgraded its design and no longer in-tends to rely on the monitors described above in the event of an accident. Assessment of iodine released under accident conditions will be performed using the charcoal filter associated with a new high range moni-tor, RE-126. This monitor is located on elevation 63 of the Turbine Building, which will be accessible during and following an accident. It monitors all flow through the station vent. Consequently, it would sample any iodine inadvertently released from the RBNVS.

9. Q. What about the other release path you mentioned, the RBSVS, how will that be monitored?

A. Assessment of radioactive iodine exiting the RBSVS release point is done by both low range and high range monitors. RE-21 and RE-22 are low range monitors which automatically begin operation when the RBSVS begins operation. They use charcoal filters located on elevation 113 of the Turbine Building and are accessible under accident conditions. A charcoal fil-ter is also associated with the high range monitor, RE-134, which monitors the RBSVS discharge. This mon-itor 3s also located on elevation 113 of the Turbine Building.

10. Q. Mr. Schmitt, let's turn to the question of power supplies. What requirements govern the power sources for these iodine monitors?

A. Appendix B to NUREG-0737, entitled " Design and Qualification Criteria for Accident Monitoring Instrumentation" requires, among other things, that such instrumentation be energized from station Class IE power sources.

Whatever the effect of Appendix B when issued, it is no longer clear that it applies to the equipment covered in these contentions. NUREG-0737 (on page vii) states that further criteria on various subjects, including instrumentation, would be issued.

Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident" was subsequently issued in December, 1980.

It describes "a method acceptable to NRC staff for complying with the Commission's regulations to provide instrumentation to monitor plant variables and systems during and following an accident "

. . . . Thus, it appears that Regulatory Guide 1.97 is the NRC's cur-rent guidance for this instrumentation.

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11. Q. What power source does Regulatory Guide 1.97 recommend for the radioactive iodine monitors?

A. Airborne radioactive halogens (of which iodine is one) released from the plant are defined in Table 1 of Regulatory Guide 1.97 to be a Type E variable.

Instrumentation for assessing such releases is re-quired by that table to meet Design and Qualification Criteria Category 3. The regulatory guide does not specify a power source for Category 3 instruments. By contrast, Category 1 instruments must be energized from a station standby power source (i.e., a vital bus) and Category 2 instrvments from a high-reliability power source. Consequently, it appears that the post-accident iodine monitors need not be powered from a vital bus.

12. Q. What power source is used for the post-accident iodine monitor in the station vent at Shoreham?

A. Although LILCO does not believe it is mandated, RE-126

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is powered from an emergency (or vital) bus. All mon-itors in the RBSVS exhaust are also powered from a vital bus.

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13. Q. Mr. Schmitt, would you summarize your conclusions re-garding this contention?

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A. Yes. Contrary to what has been alleged, LILCO has the capability necessary to measure the iodine released from the station vent during and following an acci-i dent. This station vent post-accident monitor will be

powered from a vital bus. Therefore, in this regard, Shoreham meets the requirements of NUREG-0737, Item II.F.1.

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{

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- :.c .e ATMOSPHERE ~

RBSVS RELEASE POINT RE-069 34 ll RE-022 RE-021 FILTER S RB SVS/A A ll lg AM CHARCOAL RE-042 E- 3( -RM R

RE- 26 FILTER E EXHAUST PAM CHARCOAL RBSVS/8 2222203

-RM R E-057 - STATION VENT EXH AUST FANS TURBINE ", l PAM l OUTSIDE DILUTION AIR BUIL DING d I (NORMALLY CLOSED) Y R E-055 R E- 029 RM RE-066 RE-068 RM RADWASTE

lPAM l l PAM l ll REACTOR U U BEDWG BUILDING (RBNVS)

RMs R ADI ATION MONITOR. THESE MONITORS DETECT NOBLE G ASES, AND CONTINUOUSLY COLLECT SAMPLES FOR RADIOIODINE AND PARTICUL ATE RELEASE AN ALYSIS.

PAM POST ACCIDENT MONITOR. THESE ARE HIGH RANGE IN-LINE R ADIATION MONITORS.

PAM-RMs POST ACCIDENT HIGH RANGE EFFLUENT MONITOR. plg,II,p,l-l THESE MONITORS DETECT HIGH RANGE NOBLE GASES AND CONTINUOUSLY COLLECT SAMPLES FOR RADIO!ODINE AND GASEOUS EFFLUENT RADIATION MONITORS PARTICUL ATE RELEASE ANALYSIS. SHOREHAM NUCLEAR POWER STATION-UNIT 1 THERE ARE ADDITIONAL GASEOUS STREAM RADI ATION MONITORS FINAL SAFETY ANALYSIS REPORT IN THE SHOREH AM PL ANT. THIS SIMPLIFIED DIAGRAM SHOWS *

• ONLY THOSE DISCUSSED IN TEXT.

REVISION 22-JULY 1981

JOHN F. SCHMITT Radiochemistry Engineer Long Island Lighting Company My name is John F. Schmitt. I am the Radiochemistry Engineer of the Shoreham Nuclear Power Station, a position I have held since January 1975. As such, I am responsible for developing and implementing the chemistry, radiochemistry and effluent monitoring program for Shoreham. This includes, among other things, directing all work related to conducting the chemical and radiochemical analyses and treatments of plant process systems; detecting and controlling environmental re-leases; implementing the ALARA policy for these releases; and preparing records and reports of chemical surveys.

I graduated from Manhattan College in 1966 with a Bachelor of Science degree in chemistry and received a Master of Science degree in Environmental Health Science, specializing in Radiological Health (Health Physics), from the University of Michigan in 1974. I completed the General Electric Boiling Water Reactor Chemistry Course in November 1975. I have also completed many industry seminars and training programs, includ-ing:

a) Radiation Protection - LILCO Evening Institute b) Radiation Protection Workshops - General Electric Company c) BWR Chemistry Training - General Electric Company d) Health Physics Review - Rockwell International

e) Accelerated Health Physics Instruction - NUS f) Accelerated Nuclear Plant' Chemistry Instruction -

NUS g) Health Physics Review - Brookhaven National Labs h) Environmental Radiation Surveillance - Harvard School of Public Health i) Radioactive Waste Management for Nuclear Power Reactors - ASME/ University of Virginia j)

Post Accident Sampling Workshops - Sentry Equipment, EPRI k) Control of Plant Radiation Fields - EPRI, General '

Electric Company

1) Atomic Absorption ' Atomic Emission Spectrometry -

Instrumentation Labs m) Gamma Spectrometer Operation - Canberra Industries I started work for the Long Island Lighting Company in 1966 as an Assistant Engineer at the Far Rockaway Power Station. I took a military leave of absence from 1967-1972 to serve as an officer in the U.S. Air Force. Returning to LILCO in 1972, I was an Associate Engineer at the Glenwood Power Station. From 1973 until assuming my present position in 1975, I was assigned to the staff of the Shoreham Nuclear Power Station as an Associate Engineer and Plant Engineer. During this time, I studied health physics at the University of Michigan and received training at the AEC's Savannah River Plant and Commonwealth Edison's Dresden Nuclear Power Station.

I am a member of the New York Chapter of the Health Physics Society, Power Reactor Health Physicists, and the Long Island Chapter of the American Nuclear Society.

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