ML20236D437
| ML20236D437 | |
| Person / Time | |
|---|---|
| Site: | Braidwood |
| Issue date: | 07/22/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 3384K, NUDOCS 8707300449 | |
| Download: ML20236D437 (3) | |
Text
,
7 s
s N
N). Commonw;alth Edison- ~
... s/.
' #w x -g -
-l One First National Plaza, Chicago, Illinois 7'
-} ~ O ]n Address Reply to: Post Office Box 767.
{
s J
.Nd.. Chicago, Illinois 60690 0767
,j d
q 4
July 22. 1987 Mr. Thomas'E. Murley,. Director
- Office of Nuclear Reactor Regulation
'U.S. Nuclear Regulatory' Commission Washington,;DC _20555
Subject:
Braidwood Station Unit 1
' Initial Test Program j
NRC Docket No. 50-456 Reference.(a):. Facility Operating License NPF-72, dated July 2, 1987
'~
Dear Mr. Murley:
Condition C.4 of' reference (a) states that any changes to the Initial. Test Program described in Section 14 of the Byron /Braidwood FSAR, made in accordance with the. provision of 10CFR 50.59, be reported-in accordance with'10CFR.50.59'(b) within one month of such change.
Pursuant'with.this license condition, the purpose of this letter is to notify the NRC of minor deviations from the Braidwood Initial Test L.
Program..These deviations'are provided in Attachment A.
Please address any questions concerning this matter to this office.
Very truly yours,
{
.M :$
S. C. Hunsader i
Nuclear Licensing Administrator cc:
J. Stevens - NRR W. Little - RIII Braidwood Resident Inspector J
8707300449 870722 7
PCR ADOCK 05000456 3384K P
/
e i
_____.___________J
i s.
'A 6
ATTACHMENT A-Start-up Test:
BwSU RD-30, Rev.0 1
FSAR Table:
14.2-63
==
Description:==
The control rods were to be exercised over their full range.of-travel under no flow conditions (all pumps off). This test was executed with one Reactor Coolant Pump in operation.
This change was incorporated as Test Change Request #4 to the referenced test. During post-test review on June 29, 1987, it was discovered that this deviation was at variance with the test abstract as presented in FSAR Table 14.2-63.
This change has been i
reviewed in accordance with 10CFR 50.59, and it has been determined l
that no unreviewed safety question has been introduced.
The rod control system operated as designed. The plant was maintained in Cold Shutdown (Mode 5) during the test. Operation of a single RCP in. Mode 5 is a normal plant configuration, and is within the design basis of the facility.
The possibility of a new or different type of malfunction did q
not exist. The plant configuration was normal, the control rods j
remained trippable throughout the test, and there was no new equipment or mode of operation introduced.
The margin of safety was not impacted because compliance with Technical Specification requirements was maintained. Required I
safety systems were operable and the rods remained trippable at all
(
times.
i Westinghouse has reviewed this deviation and determined that the operation of one RCP as described had no adverse impact on test results.
i i
i l
l 1
i i
\\
(5551z)
i
- j.
e s
-L ATTACHMENT A Start-up Test: BwSU IC-30, Rev.0 FSAR. Table:
14.2-67
==
Description:==
The' subject test is performed to verify indexing and to ensure free passage of the detectors for the incore flux monitor system. The test abstract indicates that the plant is in Hot Shutdown (Mode 4) during this test. This test was conducted while the plant was in Hot Standby (Mode 3).
This variance has been determined to be acceptable based on the provisions of 10CFR 50.59.
The' purpose for the conduct of this test is to verify that the effects of thermal expansion do not impede the free passage of the detectors into all. locations.
By performing this test in Mode 3,
. the impact of thermal expansion more closely resembles the expansion that_is prevalent during power operation.
Because this system is designed for use under operating conditions, this deviation does not impact the probability of an occurrence or consequences of an accident.
The system was operated in its intended manner and under. normal operating conditions. No new equipment'or procedural methodologies were introduced.
Thus, the possibility of a new or different kind of accident has not been introduced.
The margin of safety was maintained because all Technical Specification provisions were observed. The test was conducted under conditions more limiting than those specified in the test abstract. These conditions provide added confidence that the system will perform as designed during power operation.
4 i
)
4 l
l (55512) l