ML20125B184
| ML20125B184 | |
| Person / Time | |
|---|---|
| Site: | Cooper |
| Issue date: | 12/01/1992 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | Horn G NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| TAC-M83768, NUDOCS 9212090245 | |
| Download: ML20125B184 (5) | |
Text
.-
December 1, 1992 h[ Docket No. 50-298 Mr. Guy R. Horn Nuclear Power Group Manager Nebraska Public Power District Pos( Office Box 499 Columbus, Nebraska 68602-0499
Dear Mr. Horn:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO PROPOSED CHANGE NO. 100 TO THE COOPER NVCLEAR STATION TECHNICAL SPECIFICATIONS, ELIMINATION OF MAIN STEAM LINE RADIATION MONITOR SCRAM AND ISOLATION FUNCTIONS (TAC N0./g83768)
By letter dated May 4, 1992, you requested that the NRC staff amend the Technical Specifications (TS) for Cooper Nuclear Station (CNS) to permit removal of the Main Steam Line Radiation Monitor (MSLRM) reactor scram and containment isolation functions.
The NRC staff has examined your request and finds that additional information is needed to complete our review.
The specific additional information is defined in the enclosure.
We request that you cxpedite your response to this request to permit the staff evaluation to be complete in time for you to implement the proposed changes during the next CNS refueling outage.
If you hhve any questions regarding this issue, please contact me.
This requirement affects fewer than ten respondents and therefore is not subject to Office of Management's Budaet review under P.L.96-511.
l Sincerely.
ORIGINAL SIGNED BY:
Harry Rood, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation l
Enclosure:
RAI cc w/ enclosure:
See next page DISTRIBUTION:
Docket dile NRC & Local PDRs PD4-1 Reading M. Virgilio J. Larkins P. Noonan ACRS (10) (P-315)
OGC (15B18)
A. B. Beach, RIV PD4-1 Plant File H. Rood J. Roe OFC LA: PD4-17 N PM:PD4-111bD:PD4 A NAME PNoonknN HRood:pk jib' ins}
~
DATE
// /.)//92 l'A./ / /92
//'/ / /92 (0)'
OFFICIAL RECORD COPY Document Name:
C0083786.RAI 9212090245 921201
~
PDR ADOCK 05000298 p
PDR a
/ pm Rag o,,
UNITED STATES -
["
g NUCLEAR REGULATORY COMMISSION g
t WASHINGTON D. C.20$$$
o,
'%,,,,, #g December 1, 1992 Docket No. 50-298 Mr. Guy R. Horn Nuclear Power Group Manager Nebraska Public Power District Post Office Box 499 Columbus, Nebraska 68602-0499
Dear Mr. Horn:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO PROPOSED CHANGE NO.100 TO THE COOPER NUCLEAR STATION TECHNICAL SPECIFICATIONS,-
EllHINATION OF MAIN STEAM LINE RADIATION MONITOR SCRAM AND ISOLATION FUNCTIONS (TAC NO./183768)
By letter dated May 4, 1992, you requested that the NRC staff amend the Technical Specifications (TS) for Cooper Nuclear Station (CNS) to permit removal of the Main Steam Line Radiation Monitor (MSLRM) reactor scram and containment isolation functions. The NRC staff has examined:your request and finds that additional information is needed to complete our review.
The specific additional information is defined in the enclosure.
We request that you expedite your response to this request to permit the staff evaluation.to be complete in time for you to implement the proposed changes during the next CNS refueling outage.
If you have any questions regarding-this issue, please contact me. This requirement.affects fewer than ten--
respondents and therefore is not subject to Office of Management's Budget j
review under P.L.96-511.
Sincerely, A4 Harry Rood, Senior Project Manager i
Project Directorate IV-1 i
Division of Reactor _ Projects - III/IV/V l
Office of Nuclear Reactor Regulation
Enclosure:
RAI cc w/ enclosure:
See next page L
i
~
Mr. Guy R. Horn Nuclear Power Group Manager Cooper Nuclear Station cc:
Mr. G. D. Watson, General Counsel Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68602-0499 Cooper Nuclear Station ATTN: Mr. John M. Meacham Site Manager P. O. Box 98 Brownville, Nebraska 68321 Randolph Wood, Director Nebraska Department of Environmental Control P. O. Box 98922 Lincoln, Nebraska 68509-8922 Mr. Richard Moody, Chairman Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, Nebraska 68305 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 218 Brownville, Nebraska 68321 Regional Administrator, Region IV li.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Harold Borchert, Director Division of Radiological Health Nebraska Department of Health 301 Centennial Mall, South P. O. Box 95007 Lincoln, Nebraska 68509-5007
l ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION 1
EllMINATION OF MAIN STEAM LINE RADIATION MONITOR SCRAM / ISOLATION FUNCTIONS COOPER NUCLEAR STATION (CNS)
DOCKET NO. 50-298
)
I l
Your request (Proposed Change No. 100) for Technical Specification (TS) changes relies on the NRC Staff's Safety Evaluation (SE) of the General l
Electric Topical Report, NE00-31400,- The SE approved removal of the Main j
Steam Line Radiation Monitor (MSLRM) reactor scram and containment isolation functions, subject to three conditions being met by each licensee desiring to make the change.
Additional information is needed by the staff to make the i
determination that the three conditions have been or will be met at CNS.
1.
The staff SE requires that "The applicant demonstrates that the assumptions with regard to input values (including power per assembly, Chi /Q, and decay times) that are made in the generic analysis bound those 4
I for the-plant."
Your response to this is the statement that "The i
District has also evaluated the CRDA (Control Rod Drop Accident) analysis j
for CNS and concludes that the assumptions used in NE00-31400 bound those i
used in the CNS CRDA accident analysis."
This statement asserts, but does not demonstrate, that the CNS assumptions are bounded by the generic analysis.
To permit-the staff to evaluate your compliance with this requirement, we request that you i
demonstrate that the CNS input values are bounded by the NE00-31400 values by providing a list of the input values used in the analysis of CNS and tnose used in the NED0-31400 analysis, and a discussion of any values for which the CNS value is not bounded by the NED0-31400 analysis.
l 2.
The staff SE requires that "The applicant includes sufficient evidence (implemented or proposed operating procedures, or equivalent commitments) to provide reasonable assurance that increased significant levels of radioactivity in the main steam lines will be controlled expeditiously to limit both occupational doses and environmental releases." Your response is the statement that "The District commits to revise its procedures as necessary to ensure that adequate controls exist to provide prompt control of significant increases in Main Steam Line activity..."
In order to determine whether or not this requirement will be met at CNS,
~
we request that you provide a discussion of any procedure changes-that-you plan to make in response to this requirement, and how the revised (or existing, if no changes-are planned) procedures ensure that significant increases in Main Steam Line activity will be promptly controlled in the absence _ of automatic containment isolation on high MSLRM signal. Also, we request that you provide an evaluation of the time that it takes to -
isolate and the occupational doses and environmental releases with and without automatic isolation on a MSLRM signal so that we may review this aspect of the proposed change.
4 i
f
2 j :
l 3.
The staff SE requires that the HSLRM and the offgas radiation monitor alarm setpoint-be-standardized at 1.5 times the nominal full-power nitregen-16 background dose rate at the monitor locations, and that the I
applicant commits to promptly sample the reactor coolant to determine possible contamination levels in the slant reactor coolant if the MSLRM or offgas radiation monitors exceed t1eir alarm setpoints. Your response to this requirement states that the MSi.RM alarm setpoint will be retained at 1.5 times the nominal background, and commits to promptly sample the reactor coolant if this setpoint is exceeded. However, you make no mention of the offgas radiation monitor. We request that you explain how a
l this aspect of requirement 3 is met at CNS.
I t
a 4
}
i 4
i l
l e
i 4
4 4
4 4
1
.. -