ML20070V815
| ML20070V815 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/11/1983 |
| From: | Dignan T, Gad R POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK, ROPES & GRAY |
| To: | Atomic Safety and Licensing Board Panel |
| Shared Package | |
| ML20070V817 | List: |
| References | |
| ISSUANCES-OL, NUDOCS 8302180136 | |
| Download: ML20070V815 (4) | |
Text
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ntu a ten cora m ?rc Nr r.v c-r Filed: February 11, 1983 Y
{fD 33 FEB 17 N0:51 UNITED STATES OF AMERICA
.;f-NUCLEAR REGULATORY COMMISSION before the ATOMIC SAFETY AND LICENSING BOARD
)
In the Matter of
)
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PUBLIC SERVICE COMPANY OF NEW
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Docket Nos. 50-443 OL HAMPSHIRE, et al.
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50-444 OL
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(Seabrook Station, Units 1 & 2)
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APPLICANTS' FIFTH MOTION FOR
SUMMARY
DISPOSITION (CONTENTIONS NH-9 AND CCCNH-7)
Pursuant to 10 CFR S 2.749, the Applicants hereby move for summary disposition of contentions NH-9 and CCCNH-7.
This motion is made upon the affidavit of James A.
MacDonald, attached hereto.
As is set forth therein, the Applicants' system and programs for radioactivity monitoring meet the requirements of GDC 63 and 64, s
8302180136 830211 PDR ADOCK 05000443 0
t which for the basis for this contention.
On the basis of the matters contained in that affidavit, these contentions should be dismissed.
Respectf Qubmitted,
'f l
Fr&Jw Thomas G. Dignan, Jr.
R. K. Gad III Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 Telephone:
423-6100 Dated:
February 11, 1983 9
STATMENT OF MATERIAL FACTS AS TO WHICH THERE IS NO DISPUTE 1.
GDC 63 refers to radioactivity monitoring in the spent fuel storage areas.
2.
The Seabrook spent fuel storage area is provided to two area monitors.
The normal monitor has a range of 10-1 to 10* mr/hr.; the accident monitor has a range of 10-2 to 10* R/hr.
3.
The Fuel Storage Building exhaust monitor is located in the Fuel Storage Building ventilation exhaust duct downstream of the fans.
This detector measures the gross activity vented from the Fuel Storage Building to the plant vent.
Indication and alarm is available locally and in the Main Control Room.
The effluent is monitored again at the plant vent.
4.
GDC 64 refers to monitoring of the reactor containment atmosphere, spaces containing components for recirculation of loss-of-coolant accident fluids, effluent discharge paths and the plant environs for radioactivity.
5.
Monitoring of process and effluent streams is discussed extensively in Section 11.5 of the FSAR.
Section 12.3 of the FSAR presents a detailed description of the airborne radioactivity monitors l
including the containment atmosphere monitors as well as the plant vent.
6.
The Applicants have committed to the requirements of NUREG-0737.
The plant vent monitors have provisions for monitoring up to 105 uCi/cm,
a There are also provisions for taking samples of particulates and iodines from the vent.
The steam lines are monitored for releases of noble gas through the safety valves in the event of a tube-rupture accident.
7.
The RHR vault area and other selected PAB areas are monitored by detectors with an upper range of -
b 104 R/hr.
These detectors insure adequate monitoring of spaces containing recirculated loss-of-coolant accident fluids.
8.
Sections 6.1.5 and 6.2.1 of the ER-OL present details of the environmental radiological monitoring program.
Section 6.2 of the Emergency Plan describes assessment capabilities including provisions for off-site monitoring in the event of an accident.
9.
The design of the process and effluent Radiological Monito-ing Instrumentation and Sampling Systems meets the requirements of NUREG-0800.
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