ML20009F191
| ML20009F191 | |
| Person / Time | |
|---|---|
| Site: | Allens Creek File:Houston Lighting and Power Company icon.png |
| Issue date: | 07/27/1981 |
| From: | Mccracken C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20009F186 | List: |
| References | |
| NUDOCS 8107300106 | |
| Download: ML20009F191 (4) | |
Text
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07/27/81 UNITED STATES OF AMERICA
(
NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
HOUSTON LIGHTING AND POWER COMPANY
)
Docket No. 50-466
( Allens Creek Nuclear Generating Station, Unit 1)
)
NRC STAFF TESTIMONY OF CONRAD E. McCRACKEN ON TEXPRIG CONTENTION AC 52 Q.
Please state your name and position with the NRC.
A.
My name is Conrad E. McCracken.
I am a Senior Chemical Engineer in the Chemical Engineering Branch of the Division of Engineering.
A statement of my Professional Qualifications is attached.
Q.
What is the purpose of your testimony't A.
The purpose of my testimony is to respond to TexPrig contention AC 52 which maintains that:
Applicant should commit to a sy3 tem that permits taking of a primary coolant sample when the containment building is dangerously radioactive, such that no workers can enter.
This,was one of the information problems at Three Mile Island, where during emergency conditions caused by an ECCS the utility operating the plant was unable to assess how much fuel damage had occurred.
Intervenor contends lack of this knowledge made some options appear possible when they might have been hazardous or even had severe consequences if attempted.
Such a system would remove some of the uncertainty likely to occur in the event of an ECCS.
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8107300106 810727 PDR ADOCK 95000466 PDR T
- Q.
Since the accident at Three Mile Island Unit Nc 2, has the Commis-sion's Staff adopted new criteria for constructt an permit applicants in the area of reactor coolant system sampling a 'ter an accident in which there has been core degradation?
A.
Yes.
In Nrch,1981, the NRC Staff published NUREG-0718. " Licensing Requirements For Pending Applicants For Construction Pennits And Manufacturing License."
Included in this NUREG in Section II.B.3 1s criteria that all construction permit applicants should review their sampling system design and commit to the necessary modifica-tions for installation of a post-accident sampling system. Accord-ing to NUREG-0718 such a system should provide the capability to promptly obtain inside reactor coolant samples and perform chemical and radionuclide analysis within three hours of making a decision to sample.
Sufficient shielding must be installed to ensure that no person involved in sample taking or analysis will receive a radia-tion exposure in excess of General Design Criterion 19 (5 REM to the whole body or 75 REM to extremities). Additionally, NUPEG-0718 refers the applicant to detailed requirements of NUREG-0737 (Clari-fication Of TMI Action Plan Requirements), which specifies that procedures be prepared which can relate the radionuclide analysis to the severity of core damage.
Q.
Will the Allens Creek applicant be required to meet the post-accident sampling criteria of NUREGS-0718 and 0737?
A.
Yes.
In Amendment 59 to the Allens Creek PSAR the applicant has committed to install a post-accident sanpling system and to develop
t
! an analysis capability which will meet the criteria of NilREG-0718.
Additionally, it has committed to meet the post-accident sampling criteria of NUREG-0737 by the operating license review stage.
Q.
What do you conclude regarding this contention?
A.
The applicant has performed a review of his sampling system in accordance with the criteria of NUREG-0718 and has committed to implement the necessary modifications to ensure that samples can be obtained and analyzed subsequent to an accident in which there is core degradation.
Further, it has conmitted to prepare procedures by the operating license stage for relating radionuclide analysis to core damage in accordance with the criteria of NUREG-0737.
With these cannibnents the applicant has provided reasonable assur-ance that a capability will exist for sampling the reactor coolant system at Allens Creek, following an act! dent in which there is coolant degradation, and having the ability to relate this analysis to core damage.
1
s CONRAD McCRACKEN PROFESSIONAL QUALIFICATIONS.
I am a Senior Chemical Engineer in the Chemical Engineering Braich of the hy Division of Engineering, Office of Nuclear Reactor Regulation.
responsibilities in this position include evaluation of all construction permit applications for compliance with the post-accident sampling requir ments of the Commission.
of operating reactors with the post-accident sampling requirements of the I have served in this capacity since February 1981.
Commission.
Form 1966 to 1981 I was employed by Combustion Engineering Corporation in a variety of management and engineering positions, the last of which was Manager of Chemistry Development from 1977 to 19F1.
During this 15-year period my prime technical responsiLility was support to operating nuclear sampling, analysis, data interpretation establishing chemistry specifications and conducting laboratory experiments to verify or support nuclear p where I physically conducted sample and analysis programs or audited the requirements.
utilities capabilities ir the chemistry and radiochemistry area.
From 1958 to 1966 I served in the United States Navy where I was Qualified in For three years of this period I was submarines for all nuclear duties.
an instructor, responsible for teaching office and enlisted personnel in the area of chemistry, corrosion and mechanical systems operation and control.
My final duty station in the Navy was on the USS Nautilus where I was respons-ible for all chemistry and corrosion control and personnel radiation exposure.
Education I attended the University of Hartford School of Engineering and completed I am a Registered Professional Corrosion Engineer in cource work in 1970.
the State of California.
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