ML20083R740: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 19: Line 19:
{{#Wiki_filter:~
{{#Wiki_filter:~
e r,
e r,
                                                                                                      /
/
          's   1                                       ,
's 1
[l
[l l
                                                                                                                /[2 , C m     . , . -      1                                                                      #
* 8 [2,
  )=n ?' '' ~ .' r ,g Consolidated Edison Company of New York. Inc.
1 C
J=ubav 6.J u 4 Irving Place. New York, N Y 10003                                     ,
m
y l
/
* 8
)=n ?' '' ~.' r,g Consolidated Edison Company of New York. Inc.
                                                                                                            , ,      74 Q s             ,
7 Q
w             %.-
J=ubav 6.J u 4 Irving Place. New York, N Y 10003 y
                                                                                            '\ 4         4                     l 4y January 28, 1974                 -
4 s
sypy Re:   Indian Point Unit No. 2 AEC Docket No. 50-247 Operating License DPR-26                                     -
w l
A.O.-4-2-5 Mr. James P. O'Reilly, Director Regulatory Operations, Region I                                                   -
'\\ 4 4
U. S. Atomic Energy Co r.ission 631 Park Avenue King of Prussia, Pennsylvania 19406
4y sypy January 28, 1974 Re:
Indian Point Unit No. 2 AEC Docket No. 50-247 Operating License DPR-26 A.O.-4-2-5 Mr. James P. O'Reilly, Director Regulatory Operations, Region I U. S. Atomic Energy Co r.ission 631 Park Avenue King of Prussia, Pennsylvania 19406


==Dear Mr. O'Reilly,==
==Dear Mr. O'Reilly,==
In accordance with the requirements of Section 6.12.2a of the Technical Specifications of Facility Operating License No. DPR-26, the following report is submitted.
On January 23, 1974 at approximately 1538 hours a slight reactor coolant system pressure transient above the Technical Specifica-tions limit was experienced in the course of placing a reactor coolant pump in service.
At the time of the occurrence, the re-actor was shutdown with all full length control rods fully ig-sorted and a reactor coolant system temperature of about 190 F.
0 In order to heat tne reactor coolant 'ystem to 547 F preparatory to returning the plant to service following completion of repairs associated with the November 13, 1973 feedwater line break inci-dent, the first reacter coolant pump was placed in service fol-lowing prescribed procedures.
These procedures entailed-the es-tablishment of a nitrogen blanket in the pressurizer to act as a surge volume for the start of the first pump.
Upon starting the pump, the reactor coolant system pressure increased to 525 psig, and 510 psig. as indicated on two installed drag pressure gages.
The pressure was immediately brought down to the desired 425 psig. by operator action.
Technical Specification 3.1.B.l.a 0
states that for indicated temperatures at or below 220 F the max-imum indicated pressure shall not exceed 500 psig.
There was no damage incurred to any system or component as a re-sult of a pressure transient of this magnitude nor was there any reason to expect any.
The transient experienced was much less 1
h
!N /'
8304040621 740205 C,k
'0 PDR ADOCK 05000247 1J 3-3'y
. /~
t S
PDR r
2 y
gY M 7;;pH g
m


In accordance with the requirements of Section 6.12.2a of the Technical Specifications of Facility Operating License No. DPR-                                                      -
p 3
26, the following report is submitted.
Mr. James P. O'Reilly January 28, 1974 Re:
On January 23, 1974 at approximately 1538 hours a slight reactor coolant system pressure transient above the Technical Specifica-tions limit was experienced in the course of placing a reactor coolant pump in service. At the time of the occurrence, the re-actor was shutdown with all full length control rods fully ig-sorted and a reactor coolant system temperature of about 190 F.
Indian Point Unit No. 2 AEC Docket No. 50-247 Operating License DPR-26 A.O.-4-2-5 than those previously reported and demonstrates the effective-ness of a gas blanket in eliminating or minimizing pressure surges when starting the first pump.
0 In order to heat tne reactor coolant 'ystem to 547 F preparatory to returning the plant to service following completion of repairs associated with the November 13, 1973 feedwater line break inci-dent, the first reacter coolant pump was placed in service fol-lowing prescribed procedures. These procedures entailed-the es-tablishment of a nitrogen blanket in the pressurizer to act as a surge volume for the start of the first pump. Upon starting the pump, the reactor coolant system pressure increased to 525 psig, and 510 psig. as indicated on two installed drag pressure gages.      The pressure was immediately brought down to the desired 425 psig. by operator action. Technical Specification 03.1.B.l.a states that for indicated temperatures at or below 220 F the max-imum indicated pressure shall not exceed 500 psig.                                    .
We believe this particu-lar transient was due to an insufficient volume of nitrogen in the pressurizer and we plan to modify our procedure to insure the proper amount.
There was no damage incurred to any system or component as a re-sult of a pressure transient of this magnitude nor was there any reason to expect any. The transient experienced was much less 1
h      !N /'                                    .
8304040621 740205
                                                                        '0  C ,k                                      ,
1J                                        :
PDR ADOCK 05000247 S                    PDR                      r    .
t    3'y 3-
                                                                                                                . /~
2                                y g
gY M                            7;;pH m
 
p                                 3             .
Mr. James P. O'Reilly                       January 28, 1974 Re:   Indian Point Unit No. 2 AEC Docket No. 50-247 Operating License DPR-26 A.O.-4-2-5 than those previously reported and demonstrates the effective-ness of a gas blanket in eliminating or minimizing pressure surges when starting the first pump. We believe this particu-lar transient was due to an insufficient volume of nitrogen in the pressurizer and we plan to modify our procedure to insure the proper amount.
Mr. Anthony Fasano of your office was informed of this occur-rence by Mr. John Makepeace on January 24, 1974.
Mr. Anthony Fasano of your office was informed of this occur-rence by Mr. John Makepeace on January 24, 1974.
Very truly yours, i   MLt             (Ld d Warren R. Cobean, Jr. * \ Manager Nuclear Power Generation cc:   Mr. John F. O' Leary l
Very truly yours, i
1
MLt (Ld d Warren R. Cobean, Jr. * \\ Manager Nuclear Power Generation cc:
                                                                                    -l f   .-
Mr. John F. O' Leary 1
                                                                            *.        I L-}}
-l f
I L-}}

Latest revision as of 05:06, 14 December 2024

AO 4-2-5:on 740123,while Placing Reactor Coolant Pump in Svc,Coolant Sys Pressure Exceeded Tech Spec Limit.Probably Caused by Insufficient Nitrogen Vol
ML20083R740
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 01/28/1974
From: Cobean W
CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To: James O'Reilly
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20083R732 List:
References
AO-4-2-5, NUDOCS 8304040621
Download: ML20083R740 (2)
v • d • e


Text

~

e r,

/

's 1

[l l

  • 8 [2,

1 C

m

/

)=n ?' ~.' r,g Consolidated Edison Company of New York. Inc.

7 Q

J=ubav 6.J u 4 Irving Place. New York, N Y 10003 y

4 s

w l

'\\ 4 4

4y sypy January 28, 1974 Re:

Indian Point Unit No. 2 AEC Docket No. 50-247 Operating License DPR-26 A.O.-4-2-5 Mr. James P. O'Reilly, Director Regulatory Operations, Region I U. S. Atomic Energy Co r.ission 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. O'Reilly,

In accordance with the requirements of Section 6.12.2a of the Technical Specifications of Facility Operating License No. DPR-26, the following report is submitted.

On January 23, 1974 at approximately 1538 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.85209e-4 months <br /> a slight reactor coolant system pressure transient above the Technical Specifica-tions limit was experienced in the course of placing a reactor coolant pump in service.

At the time of the occurrence, the re-actor was shutdown with all full length control rods fully ig-sorted and a reactor coolant system temperature of about 190 F.

0 In order to heat tne reactor coolant 'ystem to 547 F preparatory to returning the plant to service following completion of repairs associated with the November 13, 1973 feedwater line break inci-dent, the first reacter coolant pump was placed in service fol-lowing prescribed procedures.

These procedures entailed-the es-tablishment of a nitrogen blanket in the pressurizer to act as a surge volume for the start of the first pump.

Upon starting the pump, the reactor coolant system pressure increased to 525 psig, and 510 psig. as indicated on two installed drag pressure gages.

The pressure was immediately brought down to the desired 425 psig. by operator action.

Technical Specification 3.1.B.l.a 0

states that for indicated temperatures at or below 220 F the max-imum indicated pressure shall not exceed 500 psig.

There was no damage incurred to any system or component as a re-sult of a pressure transient of this magnitude nor was there any reason to expect any.

The transient experienced was much less 1

h

!N /'

8304040621 740205 C,k

'0 PDR ADOCK 05000247 1J 3-3'y

. /~

t S

PDR r

2 y

gY M 7;;pH g

m

p 3

Mr. James P. O'Reilly January 28, 1974 Re:

Indian Point Unit No. 2 AEC Docket No. 50-247 Operating License DPR-26 A.O.-4-2-5 than those previously reported and demonstrates the effective-ness of a gas blanket in eliminating or minimizing pressure surges when starting the first pump.

We believe this particu-lar transient was due to an insufficient volume of nitrogen in the pressurizer and we plan to modify our procedure to insure the proper amount.

Mr. Anthony Fasano of your office was informed of this occur-rence by Mr. John Makepeace on January 24, 1974.

Very truly yours, i

MLt (Ld d Warren R. Cobean, Jr. * \\ Manager Nuclear Power Generation cc:

Mr. John F. O' Leary 1

-l f

I L-

Retrieved from "https://kanterella.com/w/index.php?title=ML20083R740&oldid=4362914"