ML19309E843
| ML19309E843 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Zion  |
| Issue date: | 02/15/1980 |
| From: | Telford J NRC - NRC THREE MILE ISLAND TASK FORCE |
| To: | NRC - NRC THREE MILE ISLAND TASK FORCE |
| Shared Package | |
| ML19309E842 | List: |
| References | |
| FOIA-80-186, RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8004240483 | |
| Download: ML19309E843 (5) | |
Text
_ _ _ _
e O
[*,
S(
, i NUCLEAR REGULATORY COMMISSION ENCLOSURE 2 UNITED STATES e
p WASHINGTON, D. C. 20655 FEB 151c90 DOCKET NO.: 50-295 50-304 LICENSEE:
Comonwealth Edison company FACILITY:
Zion Units 1 and 2 On January 21 and 22,1980, the Westinghouse Lessons Learned Team visited the Zion Nuclear Station. The purpose of the visit was to detemine to the extent possible, the status of the implementation of the Category A Lessons Learned requirements. Comonwealth Edison has stated'that all Category A requirements were complete by January 1,1980, or would be com-plete prior to returning each unit to power. On the basis of this commit-ment, Comonwealth was issued a confimatory letter which specified that the NRC be notified in the event that any short tem Lessons Learned items could not be fully implemented by the comitted date.
The basis for judging acceptability of the implementation of each item is the requirements of NUREG-0578 and letter from Harold R. Denton to all operating nuclear power plants dated 10/30/79.
-s v
y0}..s b b.
y T. Telford Lessons Learned Coordinator
Enclosures:
1.
Lessons Learned Status 2.
Attendance List l
8004240
9 e
ENCLOSURE 2 s
ATTENDANCE LIST SIT VISIT JANUARY 21 and 22 e
iATUS OF CATICORY A LESSONS LZARNED ITES ZION STATION Name Company i
T. Pieck CECO D. Scott CECO l
T. Trama CECO I. Polanski CECO W. A. Nestel CICO L. Soth CECO P. R. Kuhner CICO J. Marianyi CECO
- 3. Brasher CECO F. Rescek CECO CICO l
- 3. Schramer F. Lentine CICO J. Woods CECO i
S. Miller CICO C. E. Schumann CECO T. M. Parker CECO i
J. J. Gilmore CECO i
E. Fuerst CICO E. Reeves NRC/NRR N. Anderson NRC/NRR J. F. Burdoin NRC/NRR l
M. B. Fields NRC/NRR J. Kerrigan NRC/NRR l
C. A. Willis NRC/NRR A. Scalker EG&G l
J. Kohler NRC/II i
I O
CW 6
h Reactor Coolant System Vent Design The vent design was reviewed and some additional information was requested to complete the review.
2.2.1.a Shift Supervisor Responsibilities During the site visit on January 21 and 22, 1980, it was determined that directives and procedures necessary to meet this requirement are acceptable.
2.2.1.b Shift Technical Advisor I
The licensee has fully implemented the Shift ie'chnical Advisory (STA) requirement. STAS are on shift and available in the control room l
within -10 minutes following an accident.
2.2.1.c Shift Relief and Turnover procedures l
Shift and relief turnover procedures were reviewed and found acceptable during the site visit.
i 2.2.2.a Control Room Access The licensee has modified procedures for implementing control rocm access requirements and is in conformance with this requirement.
2.2.2.b Onsite Technical Supcort Center The interim onsite technical support center (TSC) has been established in the conference room of the administration building at the Zion plant. This area is readily available to the document center where pertinent plant records and drawings of plant area layouts, systems and equipment are available. Zion is in compliance with this requirement.
2.2.2.c Onsite Ooerational Supoort Center This position was satisfied at the Zion Station by designating the employee's lunch room to be used as the onsite operation center during an energency. This room has a capacity for about 40-50 people and they have direct telephone cannunication with the control room.
~
2.1.5.a Dedicated Hydrogen Control penetrations preliminary review of this item indicates the present design is not single failure proof. Additional information was requested to complete the review.
2.1.5.c Recombiner procedures The licensee is in full compliance with this position.
2.1.6.a Systems Integrity Additional documentation is required to explicitly address systems excluded from the leak control program. Also, the ongoing program for the liquid rad waste system should be described. The report leakage from the containment atmosphere sampling system seems excessive and should be reduced.
Zion is in essential compliance with this item.
2.1.6.b Shielding Review s_.
Additional documentation should be provided to include an explicit statement about vital areas and ensure that all vital areas have been considered.
Zion is in essential compliance with this item.
2.1.7.b Auxiliary Feedwater Flow Indication Zion is in compliance with this item.
2.1.8.a Post Accident Sampling Further documentation is necessary to specifically address the interim sampling methods. Also the training should be promptly canpleted and reported.
2.1.8.b High Range Radiation Monitors Documentation should be expanded to include a description of monitoring and analysis procedures. Procedures are needed for determining releases from containment and from the air ejector.
\\
2.1.8.c In-plant Iodine Monitoring Docwnentation should be supplemented to reflect the present system of purging the cartridges with clean air before counting. The l
submittal also should state that silver zeolite cartridges will be used.
S
l
~
LESSONS LEARNED STATUS Plant: Zion Units 1 & 2 Dates of Visit: January 21 and 22,1980 The following is the status of each lessons Learned item based on the site visit by the Westinghouse implementation team. A list of attendees is attached.
2.1.1 Emergency Power Supply Zion is in compliance with this item.
2.1.2 Performance Testing of Relief and Safety Valves Zion is participating in industry sponsored test programs which the NRC has agreed would satisfy this requirement.
2.1.3.a Direct Indication of Power-Operated Relief Valve and Safety Valve Position The alarm was not installed on the PORV position indicating device.
The licensee stated that they are operating with the PORY block valves closed. They have installed an acoustical system designed by Babcock and Wilcox on the pressurizer safety valves.
Additional information was requested on the environmental and seismic qualification on the acoustic system and on acoustic crosstalk and signal levels on the acoustic monitoring system to complete the review.
2.1.3.b Instrumentation for Detection of Inadequate Core Cooling (Subcooling Meter)
The licensee was asked to provide more information on the uncertainty of temperature measurements and to provide documentation on the selec-tion logic. Zion does not have safety grade wide range pressure indicators. They were asked to provide schedule for upgrading.
2.1.4 Containment Isolation Zion does not fully meet this requirement in the following respects:
1.
Some non-essential systems do not isolate on automatic contain-ment isolation signal.
2.
Several penetrations were identified which do not receive diverse isolation signals.
Additional documentation was requested to pennit a more detailed review.
l l
,