ML20091F851
| ML20091F851 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/16/1984 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20091F843 | List: |
| References | |
| 5211-84-2117, NUDOCS 8406040046 | |
| Download: ML20091F851 (3) | |
Text
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4 GPU Nuclear Corporation g
gf Post Office Box 480 Rcute 441 South Middletown, Pennsylvania 17057 0191 717 944-7621 TELEX 84-2386 Writer's Direct Dial Number:
May 16, 1984 5211-84-2117 Dr. Thcmas E. Murley Region I, Regional Adainistrator U. S. Nuclear Regulatory Ccurission 631 Park Avenue King of Prussia, PA.19406
Dear Dr. Murley:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Noti of Violation Pesponse Attachment A to this letter is GPUN response to Appendix A of Inspection Report 50-289/84-02 " Notice of Violation".
Sincerely,
-~
H
. Hukil,
Director, 'IMI-l HIH/ RAS /mle Attachment cc:
R. Conte l
Sworn and Subscribed to Betore nta this i<, xx2 day of wm
, 1984.
- ma r13% n t ~O.c. < f Notary"Public I
DARLA jf AN P,f3RY. NOTARY PUellG
' YlDDil10M 60R0 DAUPHvi COUNTY YY COMMIS560N (1PIRES JUNE 17.1985 Alkemoer. Pennsvtvama Associatut of Ik4sttus
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8406040046 840529 PDR ADOCK 05000289 G
PDR GPU Nuclear Corooration is a subsidiary of the General Public Utilities Corporation
r ATTAQ M NT A FINDING:
A.
License ocndition 2.c(6) (Amendment No. 71, dated August 3,1981) requires, in part, that the licensee implement an Inservice Testing Program, which satisfies the requirements of 10 GR 50.55(a).
10 GR 50.55a(g) requires, in part, the establishment of insedri testing for safety related valves, as further delineated in ASME Code Section XI.
ASME Cbde Section XI,1980 Edition, Winter Addendun, paragraph IW-3413(a) requires that the owner (licensee) specify the limiting value of full stroke time of each power operated valve.
4 Contrary to the above, as of February 14, 1984, the licensee did not specify full' stroke (30 degrees open) times for the Reactor Building Purge Isolation Valves AH-VlB and C, which are safety related valves, in the applicable Inservice Testing procedure.
This is a Severity level IV Violation (Supplement 1).
RESPCNSE:
I.
03rrective Steps Taken and Results Achieved.
5 Testing of the F=+e Building purge valves has been deleted fran Sur veillance Procedure (S.P.) 1300-3R and added to Surveillance Procedure (S.P.) 1300-30 Therefore, no action is required for S.P. 1300-3R.
S.P.1300-30 Rev.17 includes the correct maximun stroke closure times gf
<1 second for AH-VlA and D and <2 sewnds for AH-VlB and C fran the 30 restricted position. These maximum (restricted) stroke times agree with the updated FSAR, Section 5.3.3.2.
On January 30,1984, (for AH-VIA/B/D) and February 12, 1984 (for AH-VlC),
the purge valves were tested using S.P. 1300-30 Performance within the acceptance criteria for maximun stroke time was achieved.
II.
Corrective Steps Which Will Be Taken to Avoid Further Violation.
To prevent a recurrence, the IST coordinator has reviewed the ISP Valve Testing Program and procedures to insure maximun stroke times are specified as required by ASMS Section XI, IW-3413(a). Several Valves have just recently been added to the IST program and these valves do not have maximum stroke times specified as yet in the surveillance procedures.
Maximum stroke time limits for these valves will be specified by June 30,~1984.
III.
Date When Full Octnpliance Will Be Achieved.
Full conpliance has been achieved for the Reactor Building purge valves as identified in this response.
m
. 6,
FIND'ING: -
j B.~
Technical. Specification 6.5.2.5.d requires, in part, that the functionally assigned division (Technical Functions Division) perform independent safety reviews of events which require reporting to the NRC in writing.
Technical Specification 6.5.2.7 requires that the licensee prepare, maintain, and transmit reports of these reviews to the, cognizant Division
.Vice President.-
Contrary to the above, since the effective date of these Technical Specification require ants, April 28, 1982, no i
- pa
- nt safety reviews were performed on licensee event reports subnitted to the NRC in writing; i
i and, consequently, no reprL of independent safety reviews were prepared, maintained or transmitted to the cognizant Division of.Vice President.
This is a Severity Ievel IV Violation (Supplement I).
RESPONSE
I Corrective Steps Taken and Results Adlieved.
Licensee Event Ra@1.i.s frcIn LER 82-14 of Noverober 4,1982, through the present, have been assigned to cognizant individuals for the performance -
l of required Independent Safety Review. Reports of these reviews will bei tranamitted to the cognizant Division Vice President ('IMI-l Division) and' maintained by the Licensee.
l II.
Cbrrective Steps Which Will be Taken to Avoid Further Violation.
Future Licensee Event Reports will be assigned for the performance of after the fact Independent Safety Reviews. The review will be fqu;mally tracked, the results transmitted to the cognizant Division Vice Ptesident
' and maintained by the Licensee. This pro ss will be incorporataid in j the appropriate corporate procedure.
g 1
j III. Date When Full Otznpliance Will Be Achieved 2a v.
/ +
i The appropriate past IER's have been assigned for Independent Saf"ety aeview.
The review process will be controlled by procedure which will be Hvihkd to incorporate the above corrective steps by June 30, 1984.
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