ML20058A283
| ML20058A283 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/22/1978 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7811280279 | |
| Download: ML20058A283 (5) | |
Text
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NSHD NORTHERN STATES POWER COMPANY
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u m s c a r.ou s. m e s s a. ora e s oi 1
i November 22, 1978 S
I Director of Nuclear Reactor Regulation i
U S Nuclear Regulatory Commission I
Washington, DC 20555
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1 PRAIRIE ISLAND UUCLEAR GENERATING PLANT Docket No. 50-282 g License No. DPR-42 50-306 I DPR-60
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License Amendment Request Dated November 22, 1978 f
Secondary Coolant Chemistry Monitoring Requirements
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References:
(a) Letter, A Schwencer (URC) to L 0 Mayer (NSP), dated September 7,19 78 I
(b) letter, L 0 Mayer (NSP) to Director of Nuclear Reactor Regulation (NRC), dated September 18, 19 78 I
Attached are three originals and 37 conformed copies of a request for a 3
change of Technical Specifications, Appendix A, of Operating Licenses l
DPR-42 and 60. Also attached is one copy of the license amendment class determination and a check in the amount of $4400.00 for the i
i amendment fee.
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This submittal proposes secondary coolant chemistry monitoring technical specifications requested in reference (a).
Reference (a) also requested that we propose technical specifications on
'I reactor coolant and secondary coolant activities. In that rega rd, a meeting with the NRC was requested in reference (b).
The meeting was held 3
on October 26, 197S. The NRC staff and NSP agreed to interchange additional information and to pursue in core detail the basis for positions expressed at that meeting.
4 Yours very trul'y, M G.9 w,
L 0 Mayer, PE i
Manager of Nuclear Support Services o
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UNITED STATES NUCLEAR REGUL\\ TORY COM2 FISSION HORTilER!i STATES POWER C0!!PM;Y PRAIRIE ISUd1D NUCLEAR GENERATING PIRIT Docket No. 50-282 50-306 REQUEST IUR XIND:!ENT TO OPERATING LICENSE NO. DPR-42 & DPR-60 (License Amendment Reques t Dated Novecber 22, 19 78)
Northern States Power Company, a !!!nnesota corporation, req ues ts authorization for changes to the Technical Specifications as shown on the attachcents labeled Exh-ibit A, and Exhibit B.
Exhibit A describes the proposed changes along with reasons for the change. Exhibit B is a set of Technical Specification pages incorporating the proposed changes.
This request contains no restricted or other defense information.
NORTHERN STATES POWER COMPM;Y Ey G Y/ho WL J Wachter ~
Vice President, Power Production
& System Operation On this 22nd day of November 1978, before ce a notary public in and f or said County, personally appeared L J Wachter, Vice President, Power Production and Systen Operatien, and being first duly sworn acknowl-edged that he is authorized to execute this document on behalf of Northern States Power Company, tnat he knows the contents thereof and that to the best of his knowledge, information and belief, the statements made in it are true and that it is not interposed for delay.
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EXHIBIT A PRAIR1E ISLAND NUCLEAR GENERATING PLANT License Amendment Request Dated November 22, 1978 PROPOSED CHANCES TO THE TECHNICAL SPECIFICATIONS APPENDIX A 0F OPERATING LICENSE DPR-42 & DPR-60 Pursuant to 10CFR50.59, the holcers of operating Licenses DPR-42 and DPR-60 hereby propose the following changes to Appendix A, T(.hnical Specifications:
1.
Specification 4.1 Operational Saf ety Review, Table TS.4.1-2B PROPOSED CHANGE Change Tab le, TS.4.1-2B to read as shown in Exhibit B, Revised Pages, of this Amendment Req ue s t.
REASON FOR CHANGE By le tter dated September 7,19 78 Mr A Schwence r, Chief, Operating Reactors Branch #1, Division of Operating Reactors, requested that Northern States Power propose a License Amendment to incorporate secondary water chemistry monitoring requirements appropriate for the Prairie Island Plant.
The Technical Specifications proposed herein are identical to those issued to Kewaunee Nuclear Power Plant (a sister plant to the Prairie Island units) on Janua ry 31, 19 78 ( Amendment 18 to DPR-4 3).
SAFETY EVALUATION The steam generator tubing in pressurized water reactors is part of the reactor coolant pressure bounda ry.
Industry operating experience indicates that contamination of the steam generator secondary coolant is a funda= ental cause of tube degradation. Caref ul control of the secondary water chemistry should se rve to inh ibi t potential accumulation of corrosive impurities in the steam generator and limit tube degradation. The recommended sampling program and frequencies will make it pos sib le to detect the presence of a potentially corrosive environment and will provide a basis for taking appropri-ate correct ive act ion.
EXHIBIT B License Amendment Request dared November 22, 1978 Exhibi t B consists of a revised page of Appendix A Technical Specifica-tions as listed below:
PAGE Table TS.4 1-23 r
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Table TS.4.1-23 REV TABLE TS.4 1-2B MINIMUM TREQUENCIES FOR SAMPLING TESTS FS AR Section Test Frequency Peference 1.
Reactor Coolant Samples Radiochemistry (a)
Monthly Gross Beta gamma 5/ week activity (excluding tritium)
Tritium Activity Weekly
- Chemistry (C1, F, S/ week and 0 )
2 2
Reactor Coolant Boron (b)
- Boron concentra-2/ week (c) 9.2 tion 3
Ref ueling Water Storage Boron concentra-Weekly Tank Water Sample tion 4.
Boric Acid Tanks Boron concentra-Twice/ week tion 5.
Chemical Additive Tank NaOH concentration Monthly 6.4 6.
Accumulator Boron concentra-Monthly 6
tion 7.
Spent Fuel Pit Boron concentra-Monchly 9.5.5 tion 8.
Secondary Coolant pH 5/ week (f)
Ammonia 5/ week (f)
Sodium 5/ week (f)
Gross Beta-gamma Weekly ac t ivi ty I-131 concentration Weekly (d) in water and steam (e)
NOTES:
To determine activity of corrosion products having a half-life greater a.
than 30 minutes.
(See Specification 3.1.D.)
b.
See Specification 3.8 for requirements during refueling.
The maximum interval between analyses shall not exceed 5 days.
c.
d.
If activity of the samples is greater than 10% of the limit in Specification 3.4.A.9, the frequency shall be daily.
1-131 analysis in steam is not required if I-131 is undetectable e.
in water.
f.
The maximum intarval between analyses shall not exceed 3 days.
l See Specification 4.1.D.
l l
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