ML19256D165
| ML19256D165 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/18/1977 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Brunner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19256D162 | List: |
| References | |
| GQL-1526, NUDOCS 7910170663 | |
| Download: ML19256D165 (2) | |
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v METROPOLl TAN EDISON COMPANY :a::w m= ci:.:=w=>.z::: :.:. 5: :: = = :.~.=: ;
0FFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 i
Novecber 18, 1977 GQL 1526 i
I Mr. Eldon J. Brunner, Chief Reactor Operations & Nuclear Support 3 ranch U. S. Nuclear Regulatory Ccz:::::ission 631 Park Avenue King of Prussis, Pennsylvania 19h06
Dear Mr. 3 runner:
1 Three Mile Island Nuclear Station, Uni' 1 Operating License No. DPR-50 Docket No. 50-289 j
Inspection Report No. 77-32 I
Inis letter and the attach =ent are in response to your inspection letter of October 31, 1977, concerning Mr. T. Stetka's inspection of TMI-l and the resultant finding of one apparent infraction.
S ncerely, f
i I
J. G. Herbein i
Vice President JGH:DGM:tas t
j Attachnent 1446 289 y9 1 01
i i
'NL.
, 4etropolitan Edison Company
.'hrde Mile Island Nuclear Station Unit 1 (TMI-1) s l
Dceket No. 50-289 License DPR-50 Inspection Number 77-32 l
RESPONSE TO APPARENT VIOLATION Aprarent Infraction Technical Specification h.7 2.1 states "Whenever the control red drive patch panel is locked (after inspection, test, reprogra-ing, or maintenance) each control rod drive mechanism shall be selected from the centrol room and exercised by a movement to two inches or less to verify that the proper rod has responded as shown on the unit computer printout of the rod or on the input to the ccmputer for that rod."
Contrary to the above, en May 9, 1977, control rods were moved more than two inches (up to 10 7 inches) during the performance of procedure 1301-9 2, Control Rod Program - Special Check, that is used to meet the require-ments of Tachnical Specification h.7.2.
Restonse to Apparent Violation
,ye control rods were moved more than 2 inches in violation of the limit t
tated in specification 4.7.2.1.
The data in the inspection report, l
however, does not appear to be correct.
The change in red position for control red 10-H vas 6.4% (8.96 inches).
l The test was done while the reactor was shutdown. Boron concentration in the reactor coolant system provided a shutdown margin of greater than 3% Ak/k even if all the control rods were withdrawn.
The greater than 2 inches movement of the centrol rods did not result in any threat to the
~
health and safety of the public or result in any unsafe condition.
Since the intent of the test is to demonstrate that the correct red responds, the intent of the test was satisfied by the May 9th test and it has been determined that retest is net necessary.
The surveillance test is nor-ally done during shutdown but even if done at power the 2 inches limit is unnecessarily restrictive.
Movement of less than 2 inches is difficult to reliably observe on absciute position indication since the nominal increments in rod positien are 1.h8 inches.
A Technical Specification Change Request vill be submitted upon ec=pletion of the in-house review.
This change vill allev movement of 25 of the red length.
Ihis vill permit a =cre reliable Observation cf the pcsition.
To avoid further items of noncenpliance a Temporary Change Nctice has ' een c
initiated to SP 1301-9 2 to limit scvement to less than 2 inches.
Full cc=pliance was achieved 10/20/77 1446 290
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