ML20024G798
| ML20024G798 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/20/1974 |
| From: | Wachter L NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20024G796 | List: |
| References | |
| NUDOCS 9104300425 | |
| Download: ML20024G798 (4) | |
Text
{{#Wiki_filter:-_ l i UNITED STATES ATOMIC ENERGY C0tt!ISSION NORTHEPS STATES POWER COMPA!N Honticello Nuc1chr Generating Plc.nt Docket No. 50-263 RIM'EST FOR AMENIR4r.N1 TO OPERATING LICENSE NO. DPR-22 (License Amendment Requcet Dated Augur,t 20, 19??) Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Exhibit B. F.xhibit A describes i the proposed changes along with reasons for the change. Exhibit B is a set of lechnical Specification pages incorporating the proposed changer. This request contains no restricted or other defence information. NORTHEPS STATES POWER COMPANY Ya '} fuf$) Dy ' Leo J Nachter Vice President, Power Production 6 System Operation un this 20th day of Aucust 1974, before me a notary public in and for said County, personally appeared Leo J Wachter, Vice President, Power Production 6 System Operation, and first being duly sworn acknowledged that he is authorized to execute this document in behalf of Northern States Power Company, that he knows the caatents thereof and that to the best of his knowledge, information and belief, the statements made in it are true and thc.t it is not interposed for delay. REGULATORY DOCKET FILE COPY x s s = b [lAk~ ?' / ' . W iD 1 F C':[t r'.,0. Het : An Counh, W ' k y L a. m s'on b r r O G. 1. M '. /N' u i ? 9104300425 740820 PDR ADOCK 05000263 P PDR
i ) e l EXil1 BIT A MONTICELLO NUCLTAR CENERATING PLANT DOCKET No. 50-263 I AMENDMIFT REQUEST DATED AUGUST 20, 1974 PROPOSED CllA).GES TO Tile TECIDi1 CAL SPECIFICATIONS APPENDIX A OF PROVISIONAL OPERATING LICCiSE NO. DPR-22 I Pursuant to 10 CTR 50.59 and 10 CrR 50.46, the holders of the above mentioned license hereby propor.c th. following changes, to Appendix A, Technical Specifi-cations. l l PROPOSED C} LANCES I a.) Pa3e 2, TS 1.0.1 Add a definition of MCPR to the existing definition of MCitTR in the following fomat: 1.0.1 Minirnum Critical Heat Flux and Power Ration
- 1. Minimum Critical Heat T1ux Ratio (MCliFR) -
The lowest in-core ratio of critical heat flux (that heat flux which results in transition boiling) to the actual heat flux.
- 2. Minimum Critical Power Ratio (MCPR) -
The lowest in-core ratio of critical power (that power which causes some point in the assembly to experience the onset of transition boiling) to the bundle power. b.) Pager 108 A, 108 B and 108 C, TS 3.5.J, 4.5.J 3.5K, 4.5K and Figurc 3.5.1 1)elete these four Specifications from this section. Delete Figure 3.5.1, (Page 108C). c.) Page 113, TS Bases 3.51 Kepit.cc the firct paragraph in this section with the following: 1he capacity of the thergency Core Coolant System is based on the potential consequences of a double ended recirculation t line breek. Such a break involves 3.9 sq. f t. When the cross i h yr,_,,4.-,-,,-r--.<- -,--_m,--.--, -,,,,-,.y-e,_ ..~ m, -m.. ,,,,---,.-m.,,e-
? ) 2 tie valves are closed and 5.3 sq. ft when the cross tie valves are open. Specification 3.11. A is based on an ECCS evaluation assuming a break area of 3.9 sq. (L; the limitations of 3.11. A do not apply to the larger break. Therefore, at least one cross tie valve must remain closed with two pump operation to reduce the potential break area, d,) page 113 A and 113 B, TS Bases 3.5.J and 3.5.K Delete these pages. e.) page 114 TS Bases 4.5 Delete the last paragraph on this page,
- f. ) pages 189 B through 189 J, TS 3.11 and 4.11 Porm a new section of Specifications entitled 3.11/4.11, Reactor Tuel Assemblies.
Refer to Exhibit B for the new wording. RFA59:r. T0h C:'ASCES These changes are the result of the evaluations included as Exhibit C entitled "Monticello Nuclear Generating plant Loss of Coolant Accident Analysis Conformance with 10 CTR 50 Appendix K, August 1974 " { Specifications on the average planar and local linear generation rate have been moved from section 3.5/4.5 to a new section, 3.11/4.11. Since the Appendix K evaluation was based on an initial MCpR'of 1.19, a Specification is included to monitor that condition. 1 Item c.) above and Dxhibit C report a DBA break area of 3.9 sq. f t. rather than the 4.2 sq. f t. area used previously. The larger area was based on a generic jet pump orifice size. The nominal Monticello orifice size was used in che new evaluation, resulting in the more representative break sire, i
) l I I i TX111 BIT B f r I Wis exhibit consists of the following pages revised to incorporate the proposed changes l Panes k g 1 108 A
- 108 B I
- 108 C 113
- 113 A
- 113 B 114 169 b l
189 C 189 D 189 E 189 r 189 G 189 11 189 1 189 J t Rese pages were simply deleted and were therefore omitted from this Exhibit, f t l p 1 I l i 9 - -, + - - --,.e ww.,--.3 .,,-.w.9--v--%,n+-,.. y,-,,y..,-% ,e,,,-w,r-,-.-... wmw-ee--w...~,rm.~~~+-.r=--
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