NLS2004043, Supplement to License Amendment Request to Revise Technical Specification 3.4.9 Pressure Temperature (P/T) Curves, Figures 3.4.9-1, 3.4.9-2, & 3.4.9-3
| ML041040760 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/08/2004 |
| From: | Edington R Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NLS2004043 | |
| Download: ML041040760 (8) | |
Text
Nebraska Public Power District Always there when you need us 10 CFR 50.90 NLS2004043 April 8, 2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Supplement to License Amendment Request to Revise Technical Specification 3.4.9 Pressure Temperature (P/T) Cura'es, Figures 3.4.9-1, 3.4.9-2, and 3.4.9-3 Cooper Nuclear Station, Docket 50-298, DPR-46
Reference:
I.
Letter to U. S. Nuclear Regulatory Commission from Randall K. Edington (Nebraska Public Power District) dated January 29, 2004, "License Amendment Request to Revise Technical Specification 3.4.9 Pressure Temperature (P/T) Curves figures 3.4.9-1, 3.4.9-2, and 3.4.9-3" (NLS2004005)
- 2.
Letter to U.S. Nuclear Regulatory Commission from Randall K. Edington (Nebraska Public Power District) dated March 25, 2004, "Confirmation of Commitments" (NLS2004042)
The purpose of this letter is to request interim Nuclear Regulatory Commission (NRC) approval of the 32 Effective Full Power Years (EFPY) Pressure Temperature (P/T) Limits Curares, submitted by Reference I, through the end of Cycle 23. Refueling Outage RE-23 is currently scheduled to start October 7, 2006.
On March 5, 2004, a teleconference was held with the NRC staff to discuss the proposed License Amendment Request. During the teleconference the NRC expressed concerns regarding the neutron fluence calculations utilized as an input to the revised P/T Limit Curves with regard to the validity of the Curves as vessel fluence approached 32 EFPY. It was agreed that the P/T Limit Curves would remain valid for a limited period of time not to exceed one operating cycle to allow resolution of this issue.
The operating portion of Cycle 23 is currently scheduled to end in October of 2006. Attached to this letter are revised P/T Limit Curves (Technical Specification Figures 3.4.9-1, 3.4.9-2 and 3.4.9-3) which identify that the curves are "Valid Through End of Cycle 23." These curves are based on an Adjusted Reference Temperature of Nil-Ductility Temperature that bounds the effect of fluence on the reactor materials for 32 EFPY. This evaluation was performed in the early 1990s using available state of the art methodology. It is estimated that at the end of Cycle 23, COOPER NUCLEAR STATION P.O. Rox 98/ Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fix: (402) 825-5211
_A www.nppd.comr
NLS2004043 Page 2 of 3 the reactor will have experienced 22.8 EFPY. This provides significant margin to assure that the P/T curves based on the current fluence calculations will provide adequate protection against brittle failure of the reactor vessel for Cycle 23.
In Reference 2, Nebraska Public Power District revised the due date of the previous commitment to perform fluence calculations in accordance with Regulatory Guide 1.190 to June 2005. Once the new fluence calculations are available, NPPD will submit information in support of a License Amendment that will remove the one cycle operating restriction currently imposed on the proposed TS Figures.
Similar approval of P/T Limit Curves for one operating cycle has been granted to Dresden Nuclear Power Station, Units I and 2, "Issuance of Amendments - Revised Pressure Temperature Limits (TAC NOS. MA8346 AND MA8347)," dated September 19, 2000 and Vermont Yankee Nuclear Power Station, "Issuance of Amendment RE: P/T Limit Curves (TAC NO. MB0764),"
dated May 4, 2001.
The determination of no significant hazards consideration that accompanied Reference I is bounding for this submittal.
Should you have any questions concerning this matter, please contact Mr. Paul Fleming at (402) 825-2774.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on 044q /i?,x, /
(bate)
Sincerely, Ra all K. Edington Vice President - Nuclear and Chief Nuclear Officer
/rar Attachment
NLS2004043 Page 3 of 3 cc:
Regional Administrator w/ attachment USNRC - Region IV Senior Project Manager w/ attachment USNRC - NRR Project Directorate IV-I Senior Resident Inspector xv/ attachment USNRC Nebraska Health and Human Services w/ attachment Department of Regulation and Licensure NPG Distribution wv/o attachment Records w/ attachment
NLS2004043 Attachment I Page I of 4 ATTACHMENT I PROPOSED TECHNICAL SPECIFICATIONS REVISIONS FINAL TYPED FORMAT COOPER NUCLEAR STATION NRC DOCKET 50-298, LICENSE DPR46 Listing of Revised Pages TS Pages 3.4-23 3.4-24 3.4-25
RCS P/T Limits 3.4.9 Cooper Heatup/Cooldown, Core Not Critical Curve (Curve B), 32 EFPY 1,600 1,500 1,400
_ 1,300
.0CL
) 1,200
,L 1,100 EL0
-i 1,000 w
a) a)w 900 0
t 800 w
z 700 600 w
M 500 a)
U)w 0:
ffi 400D
,z --
-ij
-i--
4-P-
t' 1
I-w
_4.
I
,I_
__-t-D_ ut,,,4'__l_t
-:,T, 7
ri,
=;--,.-.t--
.1-S_---,a-t, e
- =
J
=~~~I
-- !- j_4 S
-=-=__
- -'-t-
-S ~ ~
~
~
~
~
t---.-e-
=-e
=l-
-=-
-Beltline
' [
L
-Bottom Head
-i 1
,_._--Upper Vessel 300 200 100 0
0 50 100 150 200 250 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (°F)
Figure 3.4.9-1 (page 1 of 1)
Pressure/Temperature Limits for Non-Nuclear lecatup or Cooldown Following Nuclear Shutdown Valid Through End of Cycle 23 3.4-23 Amendment No. XXX Cooper
RCS P/T Limits 3.4.9 Cooper Pressure Test Curve (Curve A), 32 EFPY 1.600
- T:
-z-1 ;
1 1,500
_f-1,400 r7 2
=-
4 I-1,300 1,200
- -t T__.
1,100 i
0, 1
__ t1_j-_
0I-1.000 CO 900 800 Safe 70
-t Operating rt 700 i
I-12°,753 psig _ Rio__
ZFT-Region 2
600
_l
~~~~80°F7, 597 psig l-
=
- =
t-=
I-i---_. _
- *---_--_-;-r---
1-'__=-!-4---
600 JPtj
£,F 500 80, 555 psig i---
- o.
400 1
r 4Beltline 300 Bottom Head
- ~-
H-V
-4 l
- Upper Vessel 200
=
I23F
=_
100 l>80°F
+/-
° ----
I Z
0 20 40 60 80 100 120 140 160 180 200 220 240 MINIMUM REACTOR VESSEL METAL TEMPERATURE (F)
Figurc 3.4.9-2 (page I of 1)
Pressure/Temperature Limits for Inservice Hydrostatic and Inservice Leakage Tests Valid Through End of Cycle 23 Cooper 3.4-24 Amendment No. XXX
RCS P/T Limits 3.4.9 Cooper Heatup/Cooldown, Core Critical Curve (Curve C), 32 EFPY 1,600 1,500 1,400 1,300 oS 1,200
-a a<
1,100 rLw a.
0 1,000
-jJ (I,W 900 w
o 800 cc 700 z
9 600 u3 t
500 U,
U, 0:
400 cn
-- A Minimum------
t1--
33--
-. t t.-
Operating.__
Reio
.1 I.
FI-I"77 II F
300 200 100 0
- ...d V._1
).r p
Criticality with 1-----
Normal Water Level
> 80 F
-=-
-~--
I_
I__
0 50 100 150 200 250 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (°F)
Figure 3.4.9-3 (page 1 of 1)
Pressure/Temperature Limits for Criticality Valid Through End of Cycle 23 3.4-25 Cooper Amendment No. XXX
I ATTACHIYIENT 3 LIST OF REGULATORY COMMITMENTSl Correspondence Number: NLS2004043 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the Licensing & Regulatory Affairs Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE COMMITMENT OR OUTAGE None N/A 4-4-
4.
I. 1
1*
4-4.
l PROCEDURE 0.42 l
REVISION 14 l
PAGE 15 OF 17