ML18127B105
| ML18127B105 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/25/1977 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| L-77-59 | |
| Download: ML18127B105 (10) | |
Text
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NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL DOCKET NUMBER 50-335 FILE NUMBER TO: S.L. Z~mtu)n FROM:FPL Miami, Fla 33101 R.E, Uhrig DATE OF DOCUMENT 2~25~77 DATE RECEIVED
" 2-28-77
$}LETTER IIORIGINAL CI COP Y~~
DNOTORIZED SUNCLASSIFIED PROP INPUT FORM NUMBER OF COPIES RECEIVED 3 signed 37 CC Ltr noarized 2-25-77 furn info on feedwater hammer test re applicants ltrs of Jan.
21, 1977 & Jan 28, 1977 &'requesting tha the feedwater test be accepted as satisfactory
& that Conditicn C,l of encl 1 h to OL/DPR-67 be deleted
& with attachment
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1 O. BOX 013100, MIAMI, FL 33101 iiIIll)i r~.N FLORIDA POWER & LIGHT COMPANY February 25, 1977 L-77-59 Office of Nuclear Reactor Regulation Attn:
Dennis L. Ziemann, Chief Operating Reactors Branch I2 Division of Operating Reactors U.
S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Ziemann:
Re:
St. Lucie Unit No.
1 Docket No. 50-335 License Condition C
On February 2, 1977, a feedwater hammer test was performed at St. Lucie Unit. 1, in accordance with Preoperational Test Pro-cedure
- 0700080B, Revision 2, and the provisions stated in our letters of January 21, 1977 (L-77-27) and January 28, 1977 (L-77-34).
Representatives of your staff and the Office of Xnspection and Enforcement witnessed the performance of this test.
A copy of the completed test, procedure will be for-warded under separate cover.
As requested by your staff, two tests were performed follow-ing a reactor trip from 40% power (total loss of flow natural circulation test).
The first of these was performed following a two-hour hold period from the time the water level in steam generator 1B dropped below the feed ring.
At the time of both tests, the heat input to the primary system was equal to, or greater than, the decay heat rate generated two hours after shutdown from a minimum of 30% power, following a minimum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of operation.
Auxiliary feedwater flow was initiated at a maximum rate calculated to be 785 gpm.
No indications of feedwater hammer were observed.
The" second test was performed in series with the first.
Recovery of the steam generator was allowed after the first test., Recovery of the steam generator was allowed after 'the first test.
Drain was then initiated as before,'followed by a two-hour hold period.
Auxiliary feedwaterl,flow was in'itiated at a maximum rate indicated to be 300 gpm.'he accuracy of the calcula-tional method of the first test is demonstrated-by the calcu-lation of the flow during the second test to b'e 305 gpm.
Again, no indication of feedwater hammer was observed.
MSV PEOPLE... SERVING PEOPLE
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To:
Re:
Dennis L. Ziemann, NRC St. Lucie Unit No.
1 Docket No. 50-335 License Condition C
February 25, 1977 Page Thus, the feedwater hammer test has been performed in accor-dance with your letter of January 27, 1977.
We have reviewed, the results from the special pressure transducer, the reactor coolant system loose parts monitor, listeners in the contain-ment personnel
- hatch, and a comparison of measurements of the position of pipe restraints before and after the test.
We have seen no indication of the occurrence of a water hammer and, therefore, conclude that the test results are acceptable and meet the full intent of License Condition C.l.
Based on this, we request that the test as performed be accepted as satis-factory and that Condition C.l of Enclosure 1 to Operating License DPR-67 be deleted.
The results of power reactivity coefficient, tests performed at 80%,of rated power in accordance with License Condition C.2 are attached to this letter.
The results of the 50% tests were. reported in our letter of January 21, 1977 (L-77-28)
St. Lucie Unit 1 Startup Report.
To date, the results of these tests have been found satisfactory.
The results of the.
100% tests will be promptly forwarded to you upon completion of the tests.
Based on the acceptable completion of the required tests at 50% and 80% of rated power, we request that Condition C.2 of Enclosure 1 of Operating License DPR-67 be deleted, pending your receipt and review of the 100% test, results.
The~.above requests for changes to the St. Lucie Unit 1 Opera-ting License have been reviewed by the St. Lucie Plant. Facility Review Group and the Florida Power 6 Light Company Nuclear Review Board.
They have concluded that the proposal does not.
involve an unreviewed safety question.
Yours very truly, Robert E. Uhrig Vice President REU/NLR/hlc Attachment cc:
Norman C. Moseley, Region II Robert. Lowenstein, Esq.
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Attachment (L-77-59)
NOMINAL REACTOR POWER 805 ODERATOR TEMPERATURE COEFFICIENT EASURED LIMIT k/k / oF
-.0.22 x 10
<+0.20 x 10 POWER DEFECT COEFFICIENT hk/k /
A MEASURED
-1.10 x 10 LIMIT
(-1.0+0.1) x 10
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STATE OF FLORIDA
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COUNTY OF DADE
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Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belie f, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uhrig Subscribed and sworn to before me this day of OTBRY PUBLIC, in and
- Stat.e of Florida
, Ny commission expires:
or the County of Dade, NOTARY PDEUC STATE OF FLORIDA AT LARGF MYCOMMISSION EXPIRES NOV. 30 1979 50gKD 9lRU CKNERAL INS, UNDERWRl~
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