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(q Ob f70 fS7 Duxa Powan CoMISMY Powan Bt 3.ns wo 422 Souta Carmen Srmanr. Caunterra. N. C.nas4a wnum o. e a n..em. | |||
v.ee ene,.ee ne 1:6e.-o=e; A= e. vos s e. | |||
: 6. M. UPRIGHT P. & CHENDEMI N. S. KENNA | e.oouc..o= | ||
Mr. James P. O'Reilly, Director | s u-aos April 21, 1979 i 9. O'RULLY enemasmurt | ||
: 6. M. UPRIGHT P. & CHENDEMI N. S. KENNA Mr. James P. O'Reilly, Director F. 1 tonc Region II | |||
Region II | * Ek L MURPHY L T. amRLAno x | ||
* Ek L MURPHY Office of Inspection and Enforcement | Office of Inspection and Enforcement U. S. Nuclear Regulatory Comuniasion h | ||
U 101 Marietta Street, Northwest gm Atlanta, Georgia 30303 22 c:= | |||
gm | Re: | ||
Oconee Nuclear Station Units 1, 2, and 3 t | |||
Re: | Docket Numbers 50-269, ~270, -287 | ||
~ | |||
IE Bulletin 79-05 | IE Bulletin 79-05 | ||
==Dear Mr. O'Reilly:== | ==Dear Mr. O'Reilly:== | ||
With regard to Oconee Nuclear Station, Duke Power Company received IE Bulletin 79-05B as of 1525 hours April 21, 1979. | |||
With regard to Oconee Nuclear Station, Duke Power Company received IE Bulletin 79-05B as of 1525 hours April 21, 1979. In response to Item 3 of the Bulletin, prior to 1525 hours April 22,1979, the Reactor Protective Systen "High RCS Pressure" setpoint for the Oconee | In response to Item 3 of the Bulletin, prior to 1525 hours April 22,1979, the Reactor Protective Systen "High RCS Pressure" setpoint for the Oconee units has been lowered to not greater than 2300 psig and the pressurieer power operated relief valve setpoint has been raised to nominally 2450 psig. | ||
units has been lowered to not greater than 2300 psig and the pressurieer power operated relief valve setpoint has been raised to nominally 2450 psig. | 1 These changes are considered to reduce the likelihood of automatic actuation of the pressurizer PORV during anticipated transients, without increasing the frequency of pressurizer safety valve operation for such anticipated transients. | ||
Ve | This conclusion is based on a review of Enclosure 1 to IEB 79-05B and our cognizance of infor-mation exchanged on this matter in recent days between the NSSS vendor for Oconec, Babcock and Wilcox, and the NRC Office of Nuclear Reactor Regulation. | ||
Ve truly yours,[ | |||
2230 258 | |||
..-:- 4. | |||
William O. Parker, J DCH vr | William O. Parker, J DCH vr | ||
,# 80ea ces Division of Reactor Operations Inspection 790611 0061 wa.hington, n. c. | |||
.,7 q | |||
,,}} | |||
Latest revision as of 10:23, 2 January 2025
| ML19289F505 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 04/21/1979 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7906110062 | |
| Download: ML19289F505 (1) | |
Text
,
^ -
(q Ob f70 fS7 Duxa Powan CoMISMY Powan Bt 3.ns wo 422 Souta Carmen Srmanr. Caunterra. N. C.nas4a wnum o. e a n..em.
v.ee ene,.ee ne 1:6e.-o=e; A= e. vos s e.
e.oouc..o=
s u-aos April 21, 1979 i 9. O'RULLY enemasmurt
- 6. M. UPRIGHT P. & CHENDEMI N. S. KENNA Mr. James P. O'Reilly, Director F. 1 tonc Region II
- Ek L MURPHY L T. amRLAno x
Office of Inspection and Enforcement U. S. Nuclear Regulatory Comuniasion h
U 101 Marietta Street, Northwest gm Atlanta, Georgia 30303 22 c:=
Re:
Oconee Nuclear Station Units 1, 2, and 3 t
Docket Numbers 50-269, ~270, -287
~
Dear Mr. O'Reilly:
With regard to Oconee Nuclear Station, Duke Power Company received IE Bulletin 79-05B as of 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br /> April 21, 1979.
In response to Item 3 of the Bulletin, prior to 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br /> April 22,1979, the Reactor Protective Systen "High RCS Pressure" setpoint for the Oconee units has been lowered to not greater than 2300 psig and the pressurieer power operated relief valve setpoint has been raised to nominally 2450 psig.
1 These changes are considered to reduce the likelihood of automatic actuation of the pressurizer PORV during anticipated transients, without increasing the frequency of pressurizer safety valve operation for such anticipated transients.
This conclusion is based on a review of Enclosure 1 to IEB 79-05B and our cognizance of infor-mation exchanged on this matter in recent days between the NSSS vendor for Oconec, Babcock and Wilcox, and the NRC Office of Nuclear Reactor Regulation.
Ve truly yours,[
2230 258
..-:- 4.
William O. Parker, J DCH vr
,# 80ea ces Division of Reactor Operations Inspection 790611 0061 wa.hington, n. c.
.,7 q
,,