ML19207A149

From kanterella
Jump to navigation Jump to search
Forwards IE Bulletin 79-05B Re Procedures & Training for Establishing & Maintaining Natural Circulation & Reactor Vessels Integrity at B&W Plants.W/O Encl
ML19207A149
Person / Time
Issue date: 04/23/1979
From: Lafleur J
NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP)
To: Abraham P, Cunningham J, Simpkins R
INDIA, STATE, DEPT. OF, UNITED KINGDOM
References
FOIA-79-98 NUDOCS 7905300365
Download: ML19207A149 (1)


Text

TELEGRAPHIC MESSAGE

[

' I I-

' " ' " ~ ' '

~5 ilU'CYTAR REGULATORY C0i'J11SSION PRIORITY UNCLASSIFIED OFFICE OF INTERNATIONAL PROGRAMS

.criou.

WASHINGTON, DC 20555 TELEX NO:

710-824-0415 eccou~r cassec.rc~

o.r

,n, no rves cv -ru.o.

g O 5*"'

w A, ice w o w nes cAu O ="

,p y

~~e o~ ~ume.

JOSEPH D. LAFi[UR, JR., DEPUTY DIRECTOR 492-7788 h "'^ * " "

THIS SP.4(E FOR USE OF COMMUNICATION UNIT MESSAGE To SE TRAN5MITTED (Un de=Me Sauer med all meas / luim>

NUCLEAR ENERGY BOARD J. H. F. JENNEKINS, PRESIDENT l ATTN: JOHN CUNNINGHAM AECB i

20-22 LOWER HATCH STREET OTTAWA, CANADA i

DUBLIN, IRELAND TLX:

053-3771 j

TLX:

306-10 i

DR. CLYDE MCCLELLAND j

P. ABRAHAM U.S. EMBASSY j

DAE SAFETY REVIEW COMtilTTEE OTTAWA, CANADA i

BHABHA ATOMIC RESEARCH CENTRE TLX:

0533582 TROMBAY, BOMBAY, INDIA i

JU SUNG j

ROY SIMPKINS CCNA l

U.S. EMBASSY 4301 CONNECTICUT AVE, N.W.

l BELGRADE, YUGOSLAVIA SUITE 132 TLX:

11529 WASHINGTON, D. C.

20008 i

i 1.

COPIES OF THE BULLETIN DISCUSSED BELOW WILL BE AIRMAILED DIRECTLY

)

TO YOU.

l c-ON APRIL 21, 1979, NRC ISSUED IE BULLETIN 79-0S8 TO ALL LICENSED BABCOCK & UILCOX REACTOR FACILITIES.

THE BULLETIN REQUIRES ACTIONS TO BE TAKEN BY THE LICENSEES ON:

{1} PROCEDURES AND TRAINING FOR ESTABLISHING AND MAINTAINING NATURAL CIRCULATION, {2} REACTOR VESSEL INTEGRITY CONSIDERATIONS, {3} REDUCING LIKELIHOOD OF AUTOMATIC ACTUATION OF PRESSURIZER PILOT OPERATED RELIEF VALVE DURING ANTICIP ATED TR ANSIENTS,- {tO NEED FOR PROMPT MANUAL TRIP OF REACTOR FOR TRANSIENTS THAT RESULT IN PRESSURE INCREASE IN REACTOR COOLANT SYSTEM, {5} DESIGN REVIEW OF S AFETY-GR ADE, AUTOMATIC REACTOR SCRAM FOR LOSS OF FEEDUATER, TURBINE TRIP OR SIGNIFICANT REDUCTION IN STEAM GENERATOR LEVEL, {b}

PROMPT REPORTING PROCEDURES WHEN REACTOR IS NOT IN CONTROLLED CONDITION OF OPERATION, AND {7} CHANGES TO TECHNICAL SPECIFICATIONS.

LAFLEUR, NRC.

UNCLASSIFIED i

D P.G No.

Peo. C# PCs 1

1 UNCLASSIFI:D

~

' S~ul'ul?s't Er u.s. cevrasvts: parsTisc crrict, is74 sss-4:2 79053 0036f Os. PPwt (el CF,3 101 35.306 80 Dam