ML20083H317
| ML20083H317 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/05/1984 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20083H320 | List: |
| References | |
| 7867N, NUDOCS 8401090142 | |
| Download: ML20083H317 (4) | |
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N Commonw=lth Edison
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) One First National Plaza. Chicago, lilinois
( j'O 7 Address Reply to: Post Othee Box 767 chicago. lihnois 60690 s
January 5, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Unit 1 Request for Emergency Change to NPF-ll Appendix A Technical Specification Regarding Control Rod Drive Coupling and Control Rod Operability NRC Docket No. 50-373 Reference (a):
C.
W.
Schroeder letter to H.
R. Denton
' dated January 4, 1984.
Dear Mr. Denton:
Reference (a) provided a handwritten request for an emergency change in Technical Specifications for LaSalle County Station Unit 1.
That change was approved on January 4, 1984, by Mr.
T. Novak.
The purpose of this letter is to provide a typewritten, notarized submittal; to clarify the circumstances in which the uncoupled rod was discovered; and to transmit the remittance.
CHANGE REQUEST NPF-ll/84-01 Revise the Control Rod Drive Coupling specification to include Action Statement "c":
"The provisions of Specification 3.0.4 are not applicable."
The same change must also be added to the Contal Rod Operability Specification.
This proposed change is addressed in Attachment A and has re'ceived onsite and offsite review and approval.
Commonwealth Edison Company believes that this change falls within the " Emergency" change classification.
Unit 1 at LaSalle is in the process of restarting following an extended outage.
The unit did go critical and proceeded into run mode.
It was discovered that one control rod would not pass a Control Rod Coupling check.
An attempt at recoupling cas unsuccessful.
Following other testing, the reactor had a planned scram to hot shutdown to allow a control rod sequence change.
Additional attempts at recoupling while shutdown were also unsuccessful.
The existing Unit 1 Technical Specifications did not allow continuation of startup from Hot Shutdown or Operation due to the provisions of Specifi-cation 3.0.4.
Therefore, this falls into the " Emergency" category in which a unit derating or shutdown is required.
In order to allow continued startup and operation of LaSalle County Station Unit 1, an Emergency Technical Specification Change is required and necessary.
0401090142 840105 i
PDR ADOCK 05000373 p f Rg PDR (w
q4 300 1 7 P
H. R. Denton January 5, 1984 Commonwealth Edison Company has reviewed this amendment request and has determined that no significant hazard consideration exists.
Our review is documented in Attachment B.
Pursuant to 10 CFR 170, this change reflects one example of a Class II amendment.
This change has recently (12/16/83) been reviewed, approved, and issued by the NRC on LaSalle County Station Unit 2, NPF-18.
Although it does not qualify for a Class I amendment because the review cas not exactly concurrent with Unit 2, the NRC staff has been aware of Commonwealth Edison Company's intention to upgrade the Unit 1 Technical Specifications to generally match Unit 2 specifications.
As such, a remittance of $1200.00 is enclosed.
To the best of my knowledge and belief the statements contained herein and in the attachment are true and correct.
In some respects these statements are not based on my personal knowledge but upon informa-
. tion furnished by other Commonwealth Edison employees.
Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
Commonwealth Edison is notifying the State of Illinois of our request for this amendment by transmittal of a copy of this letter and its attachments to the designated State Official.
t Enclosed for your use are three (3) signed originals and forty l
(40) copies of this letter and the enclosures.
l If you have any questions concerning this matter, please contact this office.
Very truly yours, l
l l
-- I f S/84 C. W. Schroeder Nuclear Licensing Administrator 1m cc:
NRC Resident Inspector - LSCS G. Wright (State of Illinois)
SUBSCRIBED and SWORN to before 'me this Fr/, day of (h a n o N v
, 1984
.lj t s l{
lxY' n
p NotaIy Public' 7867N
ATTACHMENT A LASALLE COUNTY STATION TECHNICAL' SPECIFICATION CHANGE REQUEST UNIT 1 NPF-11
SUBJECT:
Control Rod Drive Coupling REFERENCES (a):
LSCS NPF-ll Technical Specifications 3.1.3.6 and 3.1.3.1.
(b):
LSCS NPF-18 Technical Specifications 3.1.3.6 and 3.1.3.1.
BACKGROUNO Reference (a) provides the Unit 1 requirements for Control Rod Drive Coupling.
During the preparation, review, and approval of the LSCS Unit 2 technical specifications the NRC Staff allowed the addition of Action Statement C, "The provisions of Specification 3.0.4 are not applicable."
LaSalle County Station Unit 1 is now in the process of starting up and requires this Action Statement to be added to allow completion of startup.
DISCUSSION Commonwealth Edison Company's LaSalle County Station Unit 1 is in the process of restarting following an extended outage.
During the outage, a large number of CRD scram solenoids were rebuilt.
As part of the post-maintenance testing for this work, the licensee specified that the affected CRD's be scrammed at operating reactor pressure and tempera-ture.
In order to acomplish this, the unit was started up in one control rod sequence, and was operated at low power.
As required by technical specifications, whenever a control rod is withdrawn to the full out position, a control rod coupling check is made.
For those rods which cere to be tested, the rods were in a pattern that had them in the full out position.
The rods were then individually scrammed in and again withdrawn to the full cut position, with an additional control rod coupling check.
When this process was performed on control rod 30-19.
the initial coupling check indicated that the rod was coupled.
When the rod was withdrawn following the scram, ling was attempted and failed.the coupling check indic the rod was no longer coupled.
Recoup The rod was then inserted and disarmed in accordance with Specification 3.1.3.6 action a.l.(b).
Continued operation in the same mode (run) was permitted by Technical Specifications and the remaining rods to be scram tested in this pattern were tested.
A planned full core scram was then performed to shutdown for a change of sequence of control rods which would be the sequence for continued operation of the plant.
While in hot shutdown, repeated attempts were made unsuccessfully to recouple the control rod.
i
. The Unit 1 Technical Specifications did not allow continuation of startup from hot shutdown due to the provisions of Specification 3.0.4.
The purpose of this change is to allow mode changes with the affected control rod inserted and disarmed in accordance with the provisions of Specification 3.1.3.6 and Specification 3.1.3.1.
The content of this change has recently been reviewed, approved, and issued by the NRC in NPF-18 for LaSalle County Station Unit 2.
There are, therefore, no unreviewed safety questions in this request.
CPNCLUSION Commonwealth Edison Company believes that this change should be granted on an " Emergency" basis for LaSalle County Station Unit 1 to allow continuation of the startup of the Unit.
(NOTE:
This change was approved by Mr. T. Novak on January 4, 1984.)
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