ML20209J082
| ML20209J082 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/05/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | Lee O PUBLIC SERVICE CO. OF COLORADO |
| References | |
| TAC-59787, NUDOCS 8511110346 | |
| Download: ML20209J082 (5) | |
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November 5 1985 0
s l
I Distribution:g" Branch Files j
Docket File.
Docket No. 50-267 NRC & LPDRs l
PKreutzer KHeitner
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HBerkow ACRS 10 Mr. O. R. Lee, Vice President 0 ELD BGrimes Electric Production Edordan Public Service Company of Colorado P. O. Box 840 l
Denver, Colorado 80201 1
SUBJECT:
FORT ST. VRAIN EQUIPMENT QUALIFICATION
Dear Mr. Lee:
On October 29, 1985, the NRC staff met with you to discuss the Fort St. Vrain Equipment Qualification Program and your request for an extension of the deadline for compliance with the equipment qualification rule.
At the conclusion of that meeting, I stated that we still had many unanswered questions about both your extension request and overall program, and agreed to provide as soon as possible a list of the additional information we required to resolve these questions. The required information is listed in the l
enclosures. These questions, and any others that arise during the course of our review, must be resolved before we can conclude that FSV is in compliance with the equipment qualification rule. Draft copies of the enclosures were provided by telecopy to Mr. Holmes of PSC on November 1, 1985.
During the meeting we also comitted to provide an NRC staff position on the question of whether the rapid depressurization of the PCRV (DBA #2) must be considered in establishing environmental requirements for the equipment qualification program. Although we are still considering this issue, our preliminary conclusion is that this event must be considered. We will provide our final conclusion on this question as soon as our review is complete.
The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Edward J. Butcher, Acting Chief Operating Reactors Branch No. 3 Division of Licensing
Enclosures:
As stated cc w/ enclosures:
See next page NW ORBf p/
PKr tzer KHeitnertef ebb 1er Y85 11 /5~/85 u/ /85 8511110346 851105 PDR ADOCK 05000267 P
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s Mr. O. R. Lee Public Service Company of Colorado Fort St. Vrain cc:
C. K. Millen Albert J. Hazle, Director Senior Vice President Radiation Control Division Public Service Company 4210 East lith Avenue of Colorado Denver, Colorado 80220 P. O. Box 840 Denver, Colorado 80201 J. W. Gahm Nuclear Production Manager Mr. David Alberstein, 14/159A Public Service Company of Colorado GA Technologies, Inc.
P. O. Box 368 P. O. Box 840 Platteville, Colorado 80651 Denver, Colorado 80201 J. K. Fuller, Vice President Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Senior Resident Inspector U.S. Nuclear Regulatory Comission P. 0. Box 640 Platteville, Colorado 80651 Kelley, Stansfield & 0'Donnell Public Service Company Building Room 900 550 15th Street Denver, Colorado 80202 Regional Administrator, Region IV U.S. Nuclear Regulatory Comission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1800 Lincoln Street Denver, Colorado 80651 i
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i FORT ST. VRAIN REQUEST FOR ADDITIONAL INFORMATION EQUIPMENT QUALIFICATION PROGRAM EQUIPMENT QUALIFICATION BRANCH i
1.
Provide a description of the aging studies being performed and any interaction between equipment degradation and harsh environment accident conditions.
(i.e., clarify the following statements: "The accelerated aging that occurs during the 4 minute isolation is very much different from that which occurs during a faster isolation time." "These lower temperature profiles will have a favorable impact in the areas of aging.")
2.
Provide a description of the operability studies being performed, specifically how operability is being demonstrated when test duration is less than required equipment post-accident operating time.
3.
Provide sample files (at least 3) which demonstrate how the above are being factored into the FSV EQ program.
4.
Provide assurance that the equipment within the scope of 10 CFR 50.49 is being qualified to the most limiting environment resulting from a spectrum of break sizes.
5.
Provide assurance that equipment accessibility is possible within the required time frame in the most limiting environment resulting from a spectrum of break sizes.
6.
Provide assurance that all design basis events, as defined in 10 CFR 50.49, have been considered in the detemination of harsh environments.
I b
FORT ST. VRAIN REQUEST FOR ADDITIONAL INFORMATION EQUIPMENT QUALIFICATION PROGRAM AUXILIARY SYSTEMS BRANCH 1.
Provide a detailed description of the steam line rupture detection and isolation system (SLRDIS). This discussion should include the systems design basis including its capability to assure environments within acceptable limits following steam line breaks concurrent with a single failure.
2.
Confirm that previous pipe break analyses have addressed equipment r, ali-fication concerns for failures in systems other than the steam lines, e.g., main feedwater. Verify that these analyses have addressed protec-tion from flooding.
3.
Provide the results of an analysis of a spectrum of postulated breaks in the main steam, and hot and cold reheat lines in the turbine and reactor buildings.
Include the resulting temperature profiles. Confirm that small breaks, i.e., those less than a full double ended break can be detected and isolated by the SLRDIS prior to exceeding the equipment, qualification envelop or unacceptably preventing access for required manual actions to achieve shutdown.
s In addition, provide response to the attached information request sheet in order to permit us to perform an independent c,alculation to verify your' temperature profiles.
4.
Provide information on the capability of the SLRDIS temperature sensors (thermistor cabling) t.o adequately detect elevated temperatures in the areas of concern. Verify that the sensitivity of these sensors is sufficient to provide proper indication / actuation in the event of localized temperature effects following steam line breaks.
Include any available roanufacturers test data and/or performance information on similar detectors in comparable applications, t
.z PRESSURE AND' TEMPERATURE PROFILES FOR PIPE BREAKS OUTSIDE CONTAINMENT
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The follow $ng information is required for each pipe break analysis performed by the applicants, l.
With respect to the pipe to be broken, we need to know the:
a.
Type of fluid (water or steam);
b.
Temperature; c.
Pressure; d.
Source of the fluid; e.
Flow rate (or assumed flow rate) versus time; and f.
Enthalpy versus time 2.
With respect to the compartments being analyzed:
a.
Number of compartment analyzed; b.
For each compartment:
1.
initial temperature 11.
initial pressure iii.
initial humidity iv. floor area including floor space taken by equipment (squa'.te feet) v.
number of verits and vent areas (square feet) for each vent; and vi. compartment wall height (feet) and c.
Simple compartment and interconnection diagram. ' '
3.
All assumptions used, including but not limited to the:
a.
Orifice coefficient; b.
Fluid expansion factor; and c.
Heat transfer coefficient for heat through the walls 4.
Utilities analysis results:
a.
Temperature versus time curve (peak temperature specified);
b.
Pressureversustimecurve(peakpressurespecified);and c.
Humidity versus time curve (peak humidity specified)
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