ML18004B733
| ML18004B733 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/20/1987 |
| From: | Watson R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HO-870379-(O), NUDOCS 8703260116 | |
| Download: ML18004B733 (5) | |
Text
REQULAT Y INFORNATION DISTRIBUTIO YSTEN. (R IDS)
ACCESSION NBR: 87032601 16 DOC. DATE: 87/03/20 NOTARIZED:
NO FACIL: 50-400 Shearon Harv is Nuclear Pouer Plant~
Unit fi Carolina AUTH. NAME AUTHOR AFFILIATION WATSON, R. A.
Cav olina Power Cc Light Co.
RECIP. NANE RECIPIENT AFFILIATION Document Contv'ol Branch (Document'ontv ol Desk)
SUBJECT:
Forwards v ept v e Change 2 to Rev 0 to Procedure 9105-S-ff>
"Loss of Feedwater Heatev Test-50/ Poveri " per 10CFR50. 59.
DISTRIBUTION CODE:
BOOID COPIES RECEIVED: LTR g ENCL g SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 8< Related Cov respondence DOCKET osooo4ao NOTES: Application fov permit v eneual filed.
05000400 RECIPIENT ID CODE/MANE PWR-A EB PWR-A FOB PWR-A PD2 PD PWR-A PSB INTERNAL: ACRS IE FILE IE/DGAVT/GAB NRR PWR-B ADTS FT/NTB REQ FIL ai EXTERNAL:'NL(ANDTS ONLY)
LPDR NSlC COPIES LTTR ENCL 1
1 1
6 6
1 1
1 0
1 1
1 1
1 1
1 1
REC IPIENT ID CODE/NANE.
PWR-A EICSB PWR-A PD2 LA BUCKLEY> B PWR-A RSB
NRC PDR PNL QRUELiR COPIES LTTR ENCL 2
2 f
2 2
1 1
a 1
1 1
0 1
1 1
0 f
0 1
1 1
1 1
TOTAL NUNBER OF COPIES REQUIRED:
LTTR 33 ENCL 28
1 bt I I 1
1h I
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CREST Carolina Power & Light Company HARRIS NUCLEAR PROJECT P. 0.
Box 165 New Hill, North Carolina 27562
~A~ Zu i~a/
File Number'.
SHF/10-13510C Letter Number:
HO-870379 (O)
U. S. Nuclear Regulatory Commission Washington, DC 20555 Attn.'NRC Document Control Desk SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1
DOCKET NO. 50-400 LICENSE NO. NPF-63 REPORT IN ACCORDANCE WITH 10CFR50.59 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, Part 50.59, the enclosed report is submitted.
This report fulfills the requirement for a written report within thirty (30) days of a change to the Initial Test Program described in Section 14 of the FSAR as required by license condition 2.C.4.
This report contains a brief description of a procedure which changes the description given in the FSAR.
The description also contains a brief summary of the safety evaluation which shows that the change does not involve an unreviewed safety question or require a change to technical specifications.
Very truly yours, z~
R. A. Watson Vice President Harris Nuclear Project RAW:lah Enclosure cc'.
Dr. J.
N. Grace (NRC RII)
Mr. G. Maxwell (NRC SHNPP) 8703260il6 mQq 0-PDR ADQCK 05000400
.P PDR MEM/H08703790/Page 1/OSl
h.
CHANGE TO PROCEDURE DESCRIBED IN FSAR Title'.
9105-S-ll, Rev. 0, Change 82, Loss of Feedwater Heater Test-50/
Power.
02/20/87 Test Procedure 9105-S-ll has been modified to test the conditions reflected in the FSAR Chapter 15 Safety Analysis and conditions expected to occur during typical plant transients.
These changes deviate from the test abstract currently stated in FSAR Chapter 14.
The objective of this test is to demonstrate
- the, plant response to isolating and/or by passing flow around feedwater heaters.
Also, to determine the consequences of the most severe loss of feedwater heater transient due to single operator or equipment failure.
The subject test is conducted with the plant initially operating at 50% power and at a maximum power allowed by turbine limitations but not to exceed 90% power.
In general the subject change requires the loss of low pressure feedwater heaters gl and g2 to be, tested by first bypassing and then isolating the "A" train heaters gl and 42.
When feedwater temperature has stabilized, temperatures, levels and pressures are then recorded.
The "A'~ Train heaters f/1 and 82 are then returned to service and the above steps are completed for the "B" Train heaters
/$ 1 and g2.
This change demonstrates the effects of losing either the "A" or "B" Train feedwater heaters
$ 1 and 82.
This sequence duplicates the response of the plant to a "high-high" I/1 heater water level alarm.
~Saf et
~Seem ae This transient does not produce a change in feedwater temperature greater than that assumed in the accident analysis (FSAR Section 15.1.1).
- Thus, performance of this procedure as described above does not increase the probability or consequences of analyzed accidents, nor introduce a
different type of accident or equipment malfunction than already evaluated in the FSAR.
Thus no unreviewed safety question exists.
MEM/H08703790/Page 3/OS1