ML19340D417
| ML19340D417 | |
| Person / Time | |
|---|---|
| Site: | Allens Creek File:Houston Lighting and Power Company icon.png |
| Issue date: | 12/24/1980 |
| From: | Moon C Office of Nuclear Reactor Regulation |
| To: | DOHERTY, J.F. |
| References | |
| INTV-801224, NUDOCS 8012300550 | |
| Download: ML19340D417 (8) | |
Text
e December 24, 1980 1
UNITED STATES OF AMECCA NUCLEAR REGULATORY C0ftMISSION si e, W rf -)
T 2d BEFORE THE ATOMIC SAFETY AND LICENSING BOARD O';/
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m HOUST0ft LIGHTING & POWER COMPANY
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Docket No. 50-466
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(Allens Creek Nuclear Generating
)
Station, Unit 1)
)
NRC STAFF'S RESPONSE TO INTERVENOR DOHERTY'S FIRST SET OF SPECIAL INTERR0GATORIES 04 HIS CONTENTION 50 P
The NRC Staff responds as follows to the interrogatofies propounded by John Doherty in the captioned proceeding.
1.
As the Grand Gulf-I unit is a BWR-6 design, please consult its FSAR or if necessary the PSAR to reply to the following.
a.
What is the composition of the metal in the jet pump Iold down beam?
^
What is the composition of the metal in the b.
jet pump diffusor?
c.
What is the composition of the metal in the jet pump throat?
l
Response
j 1(a).
Inconel X-750.
l 1(b). ' The diffuser is a bi-metallic component made by welding a Type 304 forged ring to forged Inconel 600 ring, made' to specification ASTM 8166.
1(c). Type 304 stainless steel.
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a
. t 2.
What is the general outcome of any reports by General Electric on a supposed event where a jet pump fails at full power? Please reference the document.
Response
As stited in IE Bulletin No. 80-07, the potential for degradation could lead to jet pump disassembly and possibly reduce the margin of safety during postulated accidents. As reported in the General Electric Company's Service Information Letter (SIL) No. 330, June 9,1980, assumption of a displaced mixer in licensing basis calculations (emergency core cooling sys' tem or ECCS) causes a reflood delay and an increase in peak clad temperature, and that, hence, plant shutdown is required.
It is also reported in SIL No. 330 that continued operation with a displaced mixer can lead to damage to the jet pump and restraint structure that will require significant outage time to repair.
Plant responses to a displaced jet pump mixer as reported in SIL No. 330 are:
Core flow, core plate differential pressure and core power will drop.
The flow direction on the displaced jet pump will change from fomard to reverse.
For the other jet pump on the same riser the flow will drop but continue in the forward direction.
r 1
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. f The flow of other jet pumps in the loop with the displaced jet pump will decrease due to the preferential drive flow distribution to the riser with the inactive jet pump.
The jet pumps in the sound loop will increase their flow due to the decreased internal vessel jet pump flow resistance offered by the inactive jet pump.
3.
Prior to the Feb. 2,1980 report in IE Bulletin No. 80-07, had General Electric ever indicated to the NRC (particularly DORS) that they wodld modify the BWR-6 design from the BWR-3 or BWR-4 design of the jet pump hold down beam, diffuser, or throat because of cracking? If so, indicate what steps General Electric took in the design of the parts with regard to metal composition, shape, or other parameters.
Response
No records of such an indication have been found. None have been identified in the Allens Creek Preliminary Safety Analysis Report. The BWR-4 jet pump hold down beam has been described in SIL No. 330 relative to the BWR-3 as slightly thicker, using a higher preload, and having lower stress levels in the beam. The BWR-3 beam bolt keeper is tack welded to a lock plate saddle that is attached to the side of the beam while the BWR-4 keeper is tack welded -
to a flat lock plate on top of the beam.
. I It is reported that stress calculations and testing of the BWR-4 beam design are under way to characterize its failure mechanism. The Staff would anticipate that calculations and testing of the BWR-4 beam design, if found acceptable for BWR-4's, would later be calculated and tested for BWR-6's with the modifications to be implemented for BWR-6's if shown to be necessary.
4.
What differences are there in the metal com-position of the jet pump hold-down beam between the Grand Gulf BWR-6, and each of the following BWRs?
a.
Dresden Unit #3 b.
Quad Cities #2 c.
Pilgrim Unit #1
Response
4(a).
Dresden Unit #3.
Inconel Alloy X-750.
4(b).
Quad Cities #2.
Not speuified in FSAR.
4(c).
Pilgrim Unit #1. Not specified in FSAR.
5.
IE Bulletin No. 80-07 states, " Failure of the
- o (hold-down) beam assembly resulted in pump decoupling at the diffuser Connection." What changes, if any have been made in the diffuser connection of the BWR-3 and BWR-4 design which are current in the BWR-6 design?
l
Response
The Grand Gulf FSAR does not indicate that any changes have been made I
in the BWR-6 design.
6.
Referring to Fig.1 of IE Bulletin 80-07, would the " Diffuser Connection" be at the top or bottom of the diffuser?
Response
The diffuser connection is at the slip joint at the top of the diffuser.
I 7.
Can you determine the extent of the hold-down failure experienced at a foreign BWR station mentioned on Page 2 of IE Bulletin No. 80-07?
1
Response
A similar hold-down beam failure in a foreign BWR has been described briefly by the General Electric Company in a proprietary report, " Evaluation of Jet Pump Hold-Dowm Beam Failure at Dresden Unit 3," NEDC-24256 Class III, June 1980. The General Electric Company has not advised the NRC Staff that any unique concerns have been indicated by the foreign BWR experience.
i W-
UNITED STATES OF A!! ERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC S_AFETY AND LI_CEi4 SING BOARD In the !!atter of
)
HOUST0*; LIGHTING & PO'c!ER COMPA!;Y Docket No. 50-466
)
(Allens Creek Nuclear Generating
)
Station, Unit 1)
)
l.
AFFIDAVIT OF CALVIN W. MOON I hereby deoose and say under oath that the foregoing NRC St~aff re.sponses to interrogatories propounded by John F. Doherty were prepared by me or under my supervision.
I certify that the answers given are true and correct to the best of my knowledge, information and belief.
o b
Wcrrt) w Calvin W. Modn'
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i Subscribed and sworn to before me this=2'* day of /Mc d% 1980.
1 M '/ A M.
Notary Publicf/
My Corraission expires
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UNITED STATES OF AMERICA NUCLEAR REGULATURY COMMISSION B_E_ FORE THE ATOMIC SAFETY AND LICENSING BOARD E
In the Matter of
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)
HO'JSTON LIGHTING & POWER C0'iPANY Docket No. 50-466 (Allens Creek Nuclear Generatinq
)
Station,Ur.it1)
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CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF'S RESPONSE TO INTERVENOR DOHERTY'S FIRST SET OF SPECIAL INTERR0GATORIES ON HIS CONTENTION 50" and " AFFIDAVIT OF CALVIN W. MOON" in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class, or as indicated by an asterisk by deposit in the Nuclear Regulatory Conaission internal mail system, this 24th day of December,1980:
Sheldon J. Volfe, Esq., Chairman
- Susan Plettman, Esq.
Atomic Safety and Licensing Board Panel David Preister, Esq.
U.S. Nuclear Regulatory Commission Texas Attorney General's Office l
Washington, DC 20555 P.O. Box 12548 Capitol Station i
Dr. E. Leonard Cheatum Austin, Texas 78711 Route 3, Box 350A Watkinsville, Georgia 30677 Hon. Jerry Sliva, Mayor l
City of Wallis, Texas 77485 l
Mr. Gustave A. Linenberger
- l Atomic Safety and Licensing Board Panel Hon. John R. Mikeska U.S. Nuclear Regulatory Commission Austin County Judge E
Washington, DC 20555 P.O. Box 310 Bellville, Texas 77418 Mr. John F. Doherty 4327 Alconbury Street Houston, Texas 77021 J. Gregory Copeland, Esq.
Baker & Botts One Shell Plaza Houston, Texas 77002 Mr. F. H. Potthoff, III Jack Newman, Esq.
1814 Pine Village Lowenstein, Reis, Newman & Axelrad Houston, Texas 77080 1025 Connecticut Avenue, N.W.
Washington, DC 20037 D. Marrack 420 Mulberry Lane Carro Hinderstein Bellaire, Texas 77401 8739 Link Terrace F
Houston, Texas 77025 a
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. 4 Texas Public Interest Margaret Bishop Research Group, Inc.
J. fiorgan Bishoc 11418 Oak Sprina c/o James Scott, Jr., Esq.
Houston, Texas 77043 13935 Ivynount Sugarland, Texas 77478 Brenda A. M Corkle 6140 Darnell Houston, Texas 770/4 Mr. Wayne Rentfro P.O. Box 1335 Rosenberg, Texas 77471 Stephen A. Doggett, Esq.
Pollan, Nicholson & Doggett Rosemary N. Lemer P.O. Box 592 11423 Oak Spring Rosenberg, Texas 77471 Houston, Texas 77043 Bryan L. Baker 1923 Hawthorne Houston, Texas 77098 Robin Griffith Leotis Johnston 1034 Sally Ann 1407 Scenic Ridge Rosenberg, Texas 77471 Houston, Texas 77043 Elinore P. Cunmings Atomic Safety and Licensing
- 926 Horace Mann Arpeal Board Rosenberg, Texas 77471 U.S. Nuclear Regulatory Cornission Washington, DC 20555 Atomic Safety and Licensing
- Board Panel U.S. Nuclear Regulatory Commission Mr. William Perrenad Washington, DC 20555 4070 Merrick Houston, TX 77025 Docketing and Service Section
- Office of the Secretary Carolina Conn U.S. Nuclear Regulatory Cornission 1414 Scenic Ridge Washington, DC 20555 Houston, Texas 77043 Mr. William J. Schuessler U.S. Nuclear Regulatory Comission 5810 Darnell Region IV Houston, Texas 77074 Office of Inspection and Enforcement 611 Ryan Plaza Drive The Honorable Ron Waters Suite 1000 State Representative, District 79 Arlington, Texas 76011 3620 Washington Avenue, No. 362 Houston, TX 77007 f.
A e-Richard L.
ack Counsel for RC Staff
.,