ML18093A341
| ML18093A341 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/02/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18093A342 | List: |
| References | |
| NLR-N87156, NUDOCS 8709090212 | |
| Download: ML18093A341 (8) | |
Text
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',t Public Service Electric and Gas Company Corbin A. McNeil!, Jr.
Senior Vice President -
Nuclear Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 September 2, 1987 NLR-N87156 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REVISION TO REQUEST FOR AMENDMENT SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272/50-311 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of Revision 1 of our request for amendment of Facility Operating License Nos.
DPR-70 and DPR-75 for Salem Generating Station Unit Nos. 1 and 2.
The proposed amendment requests modification of Reactor Trip System and Emergency Safety Features response times to accommodate the removal of RTD bypass piping.
This revision incorporates changes to the initial request which became necessary as a result of the NRC staff's review.
The primary change is the incorporation of changes to the footnotes on Technical Specification Table 2.2-1.
The attached Technical Specification page changes should be included with those of the initial submittal dated May 5, 1987.
Additional changes include the results of calculations performed to resolve staff reviewers questions.
These calculations are being provided under separate cover due to their proprietary nature.
Also attached to this letter are revised pages to Licensing Report S-87-05, a Combustion Engineering proprietary document which was an attachment to the initial request for amendment.
These pages should. be inserted into Licensing Report S-87-05 as indicated.
These pages which are to be inserted do not contain proprietary information.
Pursuant to the requirements of 10CFR50.91, a copy of this request for amendment has been sent to the State of.New Jersey as i.ndicated below.
This revision to a request for amendment pro-vides clarifying information in response to NRC staff questions regarding the initial submittal and represents changes which are conservative with respect to those provided in the initial submittal.
As such, we feel that the noticing of this revision for public comment pursuant to 10CFR50.9l(a) is not necessary.
\\...
Document Control Desk 2
9-2-87 This submittal includes one (1) signed original and thirty-seven (37) copies.
Should there be any questions regarding this matter, please feel free to contact us.
Attachment C
Mr. D. C. Fischer Licensing Project Manager Mr. T. J. Kenny Senior Resident Inspector Sincerely, Mr. W. T. Russell, Administrator Region I Director, Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628
Ref:
LCR 87-05 STATE OF NEW JERSEY SS.
COUNTY OF SALEM Corbin A. McNeill, Jr., being duly sworn according to law deposes and says:
I am Senior Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated September 2, 1987, concerning Docket Nos. 50-272 and 50-311 for Salem Generating Station, is true to the best of my knowledge, information and belief.
My Commission expires on me 1987 LARAINE Y. BEARD Notary Public of New Jersey My Commission Expires May 1, 1991
LICENSE AMENDMENT REQUEST 87-05 RTD BYPASS ELIMINATION, REVISION 1 SALEM GENERATING STATION UNIT NOS. 1 AND 2 REVISED PAGES INSTRUCTIONS Section Remove Insert Description of Amendment Request All 3 pages, Revision 1 Technical Specification Pages Licensing Report S-87-05 N/A N/A Pg Pg Pg Pg Pg N/A Pg Pg Pg Pgs Pgs 3
Pg 7
Pg 8
Pg 9
Pg 17 Pg
- Pg 27 Pg 28 Pg 29 Pg 2-5 and 2-9, Unit 2-5 and 2-9, Unit 3, Revision 1 7, Revision 1 8, Revision 1 9, Revision 1 17, Revision 1 22b 27, Revision 1 28, Revision 1 29, Revision 1 1
2
REVISED PAGES DESCRIPTION OF AMENDMENT REQUEST
DESCRIPTION OF AMENDMENT REQUEST The proposed amendment would modify Technical Specifications 2.2.1, "Reactor Trip System Instrumentation Setpoints", 3.3.1, "Reactor Trip System Instrumentation",
and 3.3.2, "Engineered Safety Features (ESF)
Instrumentation."
The proposed request for amendment is made to support the removal and replacement of the existing Reactor Coolant System narrow range Resistance Temperature Detectors (RTDs).
The existing technical specifications pages for Units 1 and 2 are provided in Attachments A and B, respectively.
Table 3. 3. 2, "Reactor Trip System Response Times" would be modified to increase the measured response time for the Overtemperature Delta-T (OTAT) trip from 4.0 seconds to 5.75 seconds. Table 3.3.5, "Engineered Safety Features Response Times", will be modified.
All of the response times listed under Initiating Signal Number (5), "Steam Flow in Two Steam Lines -
High Coincident with Tavg-Low-Low" will be increased 1.75 seconds.
The allowable values for OT~T and OPAT, Table 2.2-1, are being reduced from the existing 4.0% value.
The new allowable for OTAT is 3.1% and for OPbT it is 3.0%.
The proposed Technical Specification sections 2.2.1, 3.3.1 and 3.3.2 for Units 1 and 2 are provided at Attachments C and D, respectively.
As described in the Updated Final Safety Analysis Report (UFSAR) Section 5.6.1, Reactor Coolant System (RCS) hot and cold leg temperatures are measured by narrow range direct immersion RTDs located in bypass manifolds.
Through the use of a bypass manifold around each steam generator, hot leg temperatures are obtained by mixing the flow from three scoop connections which extend into the flow stream at locations 120° apart circumferentially.
Flow for the cold leg manifold is obtained downstream of the pump.
Both hot leg and cold leg bypass flows enter a common return line to the cross over leg.
Figure 5.l-6A and B of the UFSAR illustrates the existing configuration.
As discussed in UFSAR Section 7.2.3.2, the existing RTD temperature outputs are used for a number of purposes.
They are used by the Reactor Protective System for the Overtemperature Delta-T (OT~T) and overpower Delta-T (OPAT) trip functions.
Reactor control is based upon Tavg signals derived from protective system channels.
An engineered safety feature (ESF) actuation and steam line isolation is actuated on steam flow in two steam lines -
high coincident with Tavg-low-low.
The output from the narrow range RTDs are used to calculate the Tayg input to this ESF actuation.
The Tavg signals are provided to the Rev. 1
pressurizer level control system, the steam dump control system, the reactivity computer, and certain interlocks.
The functions that utilize temperature input from the existing narrow range RTDs will not be affected by their proposed removal and replacement because the signals derived from the proposed replacements will be equivalent to those provided by the existing RTDs.
Only one of the functions which use signals from the existing RTDs, the OT~T, is a primary trip in the accident analysis (UFSAR Chapter 15).
The steam flow in two steam lines -
high coincident with Tavg-low-low ESF activation provides backup protection for the steam line break accident.
The revised OT~T and OPAT allowables are more conservative than the existing 4.0% value.
The lower value is primarily a result of an overall revision to the previous setpoint analyses to incorporate errors previously not considered.
The proposed new allowable values do not require changes to either the trip setpoints nor to the safety analyses values.
Setpoint analyses, submitted separately, demonstrate that the proposed modification results in a slight improvement in the overall accuracy of the temperature related channels.
The total response times of the OTAT trip and steam flow in two steam lines -
high coincident with Tavg-low-low ESF actuation consist of components that are measured at the frequency specified in the Surveillance Requirements (i.e., RTD response, electronics, and actuated components delay times) and times determined analytically (fluid transport time in the bypass line and bypass line heat capacitance lag).
Thus the technical specification limiting condition for operation (LCO) lists the measured response times.
These do not account for the time required for fluid transport from the entrances of the bypass lines to the RTD and for the heat capacitance of the bypass lines.
For the accident analyses, an additional 2 seconds is added to the response times given in the technical specifications to account for analytically determined components.
Following the proposed modification there will be no need to account for bypass line fluid transport time and heat capacitance.
The fluid transport time in and heat capacitance of the hot leg scoops, however, will still need to be accounted for.
This time will be no more than 0.25 seconds.
The OT~T and steam flow in two steam lines -
high coincident with Tavg-low-low EFS response time listed in Rev. 1
Table 3.3-5 respectively can be increased 1.75 seconds without increasing the overall response times and without invalidating the existing safety analyses.
The proposed change involves removal of the existing bypass lines and replacement of the existing RTDs with thermowell RTDs.
Three dual element RTDs will be used for each hot leg.
These will be located in the existing scoops.
One dual element thermowell RTD will be located in the existing pump cold leg penetration.
The nozzles in the cross over legs for the bypass line return will no longer be used.
A 3 inch schedule 160 buttweld cap will be installed at each nozzle to close it off.
The thermowells are pressure boundary parts which completely enclose the RTD.
They will be shop hydrotested to 1.25 times the RCS design pressure.
The external design pressure and temperature will be the RCS design temperature and pressure.
The RTD is not part of the pressure boundary.
The scoop thermowell, cross over leg nozzle buttweld cap, and thermowell/scoop assembly will be analyzed to the ASME Boiler and Pressure Vessel Code,Section III, Class 1.
Additional changes have been made to achieve consistency between units.
Primarily, a requirement for Auxiliary Feedwater Response Time has been added to Unit 1 to achieve consistency with Unit 2 and the Westinghouse Standard Technical Specifications (WSTS).
Item 14 -
Station Blackout was added to Unit 2 to achieve consistency with Unit 1 and the WSTS.
Other typographical errors were corrected on the Unit 1 Technical Specifications, again to be consistent with Unit 2.
The 10 CFR 50.92 evaluation addressing the basis for no significant hazards determination is attached after this Description of Amendment Request.
Detailed description of the proposed amendment request is contained in Licensing Report S-87-05 dated April 2, 1987, a copy of which is included for information in support of the licensing submittal. Rev. 1