ML20009G470
| ML20009G470 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/29/1981 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 451, NUDOCS 8108040295 | |
| Download: ML20009G470 (5) | |
Text
.
4[\\,b VinoINIA ELECTRIC AND Powna CoxyAwy 4
nicnxoxo, vimoixa 2020:
July 29, 1981 b
3 Ngy. -31
,,,G 0 N
H.11. LF AMB U NG 5
4 gg, 94
(
Wcm Psammzar Noctmau Ursuanomm
/
g N
01 Mr. Harold R. Denton, Director Serial No. 451 Office of Nuclear Reactor Regulation N0/RMB:ms Attn:
Mr. Robert A. Clark, Chief Docket Nos. 50-338 Opc ating Reactors Branch No. 3 50-339 Di -sion of Licensing License Nos. NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C.
20555 Centlemen:
PIANT UPRATING PROGRAM NORTH ANNA UNIT NOS. 1 AND 2 Vepco, in conjunction with Westinghouse Electric Corporation, is in the process of conducting feasibility studies in an effort to maximize the elec-trical plant power ratings of North Anna Unit Nos. I and 2.
The incentive for conducting the uprating ef fort is that it will provile a cost of fective means of increasing our generating capacity.
The proposed uprating program under evaluation at this time consists of implementation in the near term of a steam pressure increase to maximize electrical output at the currently licensed thermal power level, followed by implementation of a core thermal power uprating upon completion of the engineering evaluation, plant safety analyses and licensing process.
The proposed steam pressure increase is designed to raise the design steam pressure at full load from 850 psia to 900 psia.
Engineering evaluation and results of plant tests indicate that this 50 psi increase in secondary pressure will result in an increase in electrical output of approximately 5 MW,
We are considering implementing this steam pressure increase in two e
phases.
Phase 1 would consist of it,,lementation of a partial steam pressure increase of approximately 20 psi and would be achieved by increasing the reference from 580.3*F to 582.8*F.
T (T^k) sed
=
reactor coolant average tempe rature lic reference value while T^
580.3*F corresponds to the current
=
582.8'F is consistent with the average temperature value assumed in thbAR accident analyses.
Since the accident analyses assumed an average temperature conservative with respect to T
= 582.8*F, no accident reanalysis will be implemen[gthis partial pressure uprating, it will be 3
required.
In order to necessary to make several minor revisions to the Technical Specification, the sh 8108040295 810729 ~
i t
I 4 i
PDR ADOCK 05000338 P
(
VlWO1MIA ELECTHIC AND POWER COMPANY TO Precautions, Limitations, and Setpoint (PLS) document, and the plant operating procedures.
It is anticipated that this partial pressure increase can be implemented in the near term and will result in an increase in electrical plant output of approximately 2 MW.
Phase 2 would consist of implementation of the full 50 psi steam pressure increase and would be achieved by increasing the reference reactor coolant average temperature to 587.8 F.
Since this value of T is higher than that g
assumed in the FSAR, implementation of the full pressure upratin, will require a
reanalysis of the FSAR accident analyses affected by this increase in T as ankGthe A
well as revision of the Technical Specifications, the PLS document, plant operating procedures.
As indicated above, the overall uprating program consists of taking advantage of an increased electrical output available through a steam pressure increase while completing the licensing process necessary to implement a core thermal power uprating.
This licensing process is anticipated to consist of comple-tion of an engineering evaluation to identify the uprated core parameters and plant modifications required, completion of a plant systems review and accident reanalysis, preparation of a licensing document, review and approval of the license application by the NRC, and implementation of the required plant modifications.
Based on initial scoping studies, the engineering evaluation has been initiated to determine the feasibility of uprating the NSSS thermal power from 2785 MW to 2910 MW.
The thermal power rating of 2910 represents the Engineered Safety Fea[ures design rating presented in the FS and was used as the basis for accident analyses where demonstration of the adequacy of the Containment and Engineered Safety Features is concern-ed.
A thermal power uprating to 2910 MW wo result in an increase in electrical plant output of approximately 40 h.uld e
A preliminary schedule for completion of the North Anna Uprating Program is shown in Attachment 1.
The schedule assumes that the NRC staff will be able to myiew the license application for the full pressure uprating without significantly delaying the review of the licensing application for core uprat-ing scheduled for submittal in approximately November, 1982.
In order to determine if additional Vepco resources should be applied to preparation of a licensing package for a full steam pressure uprating as well as preparation of a licensing application for a core uprating, we would like to meet with the appropriate members of the NRC staff to discuss our North Anna uprating program.
The objective of the meeting would be to solicit the NRC's support of our plant uprating program and to assess the availability of the NRC staff's resources to review the necessary licensing applications in accordance with our proposed schedule.
Vinois:A Etzerwic AND IbwER COMPANY TO We would like to arrange this meeting as soon as possible and would appreciate any feedback which would assist in our determination of the feasibility of pursuing the plant uprating in the manner outlined.
We will contact you to make arrangements for our meeting to discuss this matter.
Very truly yours, b
e]/
R. H. Leasburg Vice President Nuclear Operations Attachment cc:
Mr. James P. O'Reilly Office of Inspection and Enforcement Region II
SCHEDULE OVERVIEW
}
NORTH ANNA PLANT UPRATING PROGRAM IMPLEMENT COMPLETE DETAILED 7 y EQUIPMENT AND
-I ' ',
m,
DOCUMENT REVIEW FOR NRC REVIEW PARTIAL PRESSURE I
AND IMPLEMENT PHASE 1)
APPROVALj PHASE 1 a
j(
l ON
'f
. UNIT 2-l SUBMIT T.S.
COMPLETE STEAM g
CHANGE PRESSURE UPRATING REQUEST IMPLEMENT FEASIBTLTTY STimY (Pl!ASE 1)
PHASE 2 ON -
g UNIT 1 PRESSURE UPRATING l
COMPLETE ACCIDENT REANALYSIS, p
->-C PROGRAM I
EQUIP::ENT AND DOCUMENT I
REVIEW FOR FULL PRESSURE NRC REVIEW l_ 4 gITPRATTNG (PTTASF ?)
AND APPROVAL I
y 0
4 1-SUBMIT LICENSING h.
PACKAGE FOR G
IMPLEMENT PHASE 2 ON H
UNIT 2 COMPLETE CORE UPRATING COMPLETE ENGINEERING PREPARE SCOPING STUDY STUDY LICENSING DOCUMENT
. y p._______
>c CORE UPRATING PROGRAM i
'81
' 8,2 i
J F
M A
M J
J A
S O
N D
J F
M A
M J
J A
S 0
N i
SCHEDULE OVERVIEW
~
NORTH ANNA PLANT UPRATING PROGRAM I
t 1
I, INSTALLATION OF PLANT i
MODIFICATIONS AND i
IMPLEMENTATION OF CORE UPRATING ON UNIT NO. 1 COMPLETION OF DETAILED ENGINEERING l
FOR PLANT MODIFICATIONS, PROCUREMENT l MAY,85 0F MATERIALS AND DOCUMF*.'T REVISION INSTALLATION OF PLANT C
MODIFICATIONS'AND
' IMPLEMENTATION OF CORE UPRATING ON UNIT NO. 2 p
l NRC REVIEW NRC PREPARATION NRC QUESTIONS
/
DEC '84 T.1 CENSING OF SAFETY AND RESPONSES j
DOCUMENT EVALUATION REPORT j
CORE UPRATING PROGRAM
'84
'83
(
i a
j i
i 3
J A
S 6
6 j
{
s A
s J VJ s b
J
.f s,
,m,
,