ML19308D160
| ML19308D160 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/25/1977 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19308D141 | List: |
| References | |
| CS-77-69, NUDOCS 8002270632 | |
| Download: ML19308D160 (2) | |
Text
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CS-77-69 Mr. Norman C. Moseley, Director Office of Inspection and Enforcement Docket No. 50-302 U. S. Nuclear Regulatory Consnission License #DPR-72 230 Peachtree St., N.W., Suite 818 Ref: IE:II:FJ Atlanta, Georgia 30303 50-302/77-5
Dear Mr. Moseley:
We offer the following in response to th noted in the referenced Inspection Reporte apparent item of Noncompliance
" Infraction - Change to Test Prog ram Commitmeg safety evaluation was not performed to determiCo
, a written unreviewed safety question did not exist when th ne that the coefficients at power test was deleted from the 15 pg e reactivity power ascension test program.
Q that this test will be performed at iTable 13-4 of the FSAR states percent in accordance with 10 CFR 50.59(b) becausIt is our posit ncremental power levels."
on was not required to be perfo formed in accordance with the PSAR require the test in question was per rmed FSAR states " predetermined incremental p ements.
Section 13.4.8.2 of the tests performed, and results evaluat d ower levels will be established, that this test is "to determine : eacti i e
at each level".
boron concentration moderator temperaturev ty coefficients as related with Table 13-4 states ous power levels".
this test is one of several to be perfThe note referenced at the end of Trble\\
40, 75, and 100 percent full power plateaTest Procedure (T The sa predetermined power levels to be to require all power tests which are us.
perforned at incremental levels to beThe in required at a_11 increments.
The basis for the 40, 75, and 100 percent procedures and Regulatory Guide 1.68 requirem viewed with no further questions as reported iplateaus was a cross ents.
This cross-index was re-76-20 which also referenced FSAR Amendment #49n your Inspection R associated with the check list.
which incorporated requirements To substantiate our position that the test i 15 percent, we have received correspond s not essential nor practicable at plier which reinforces this portion of the t ance from the Nuclear Steam System sup-est program as it was performed.
L General Office 320s wry-fourm Street soum. P o som no42 St P t 8002 270 [g e ersburg, Fionca 33733 e 813--866-5151 i
w TO:
Mr. Norman C. Meneley 25 April 1977
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Page 2 Work Group whf ah is composed of knowledgeable rTe ementation by the Test Engineer, and the Wuclear Steam System suppliererstio i
g neering, the Architect plementation, the safety evaluation as required by the Plant Review Commit'l documented reviews assured that FSAR commitments e,3 ding a tee Charter. These were met.
In summary, this test was not deleted from the 15 test program; it was not intended to be perf percent power ascension lieve that no further action should be requiredormed at-this plateau.
We be-on this subject.
With regard to the Deviation noted under "VI we offer the following:
Other Significant Findings",
" Deviation Contrary to the requirements of FSAR Table 13 4 age Testing was not adequately performed
,RCS Hot Leak-only two readings of Makeup Tank Level were taken one hon Febru to determine RCS Hot Leakage.
j our apart the 15 percent power increment to determine RCS HThis represe at We acknowledge that Test Procedure TP-80010 ot Leakage. "
Imvel were recorded.at the 15 percent power increment in that only twowas no interview, the plant was undergoing transiAs was noted by the Inspector du ement j
cause of test conditions.
It should be noted that the test and test res lents demonstrated acceptability at the 40, 75 thus, demonstrating system integrity
, and 100 percent power increments, u ts Inasmuch as the test program was completed on 23 A recurrence of items such as this.
pril 1977, there will be no Personnel involved with the performance of th have also been made aware of the requirement tohave e
ances as performed. They tests in strict accordance with the proced perform these surveillance quiremen ts.
ure and Technical Specification re-We find no proprietary information in this r eport.
Should you have any cuss them with you. questions concerning this letter, we will be glad to dis-Very truly yours, FLORIDA POWER CORPORATION DWP/feh b
bl c..Ll W. P. Stewart Director, Power Production i
Nucrear Plant Manager
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