ML20080A720
| ML20080A720 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/15/1983 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20080A714 | List: |
| References | |
| NUDOCS 8307270301 | |
| Download: ML20080A720 (3) | |
Text
F SAFETY EVALUATION BY THE OFFICE OF huCLEAR REACTOR REGULATION RELATED TO ANENDMENT NO. 20 TO FACILITY OPERATING LICENSE DPR-79 TENNESSEE VALLEY AUTHORITY INTRODUCTION On June 21, 1983, TVA requested a temporary change in the surveillance requirements for Sequoyah Unit 2 for the rod drop time, and full length control rod position liuit switches. Sequoyah Unit 2 surveillance requiremat 4.1.3.4.c requires that the rod drop time be raeasured every 18 months plus a 25 percent contingency.
The last test was performed on September 2. 1981. The test results expire on July 21, 1983.
Unit 2 surveillance requirement 4.3.3.5, item 8 requires calibration of the control rod bottom lights in the remote shutdown control room every eighteen months plus a 25 percent contingency. The last test performed was on August 28, 1981. The test results will expire on July 17, 1983.
The present shutdown date for the first Sequoyah Unit 2 refueling outage is August 5, 1983.
This date is based on the fuel currently available in this core, the stage of outage preparation, and the assumed capacity factor for the remainder of the cycle.
The expiration dates for both the rod drop test and the rod bottom lignt calibration will occur before the end of cycle.
EVALUATION The proposed amendment would increase the surveillance period by 20 days. The pre-sent maximum surveillance interval of 688 days (22.5 months) permitted in the Tech-nical Specifications ends on July 17, 1983. The proposed amendment would permit the licensee to schedule the control rod tests and calibration of the limit switches to coincide with the refueling outage date of August 5, 1983, and preclude the loss of i
20 days of core life. The plant would not be restarted, if forced to shutdown on July 17, 1983, because technical requirements associated with the restart for the
' ~,
remaining brief period of time would make it impractical to return to power oper-ation.
The licensee normally conducts such tests during the 18-22.5 month period whenever a forced outage occurs. However, Unit 2 has operated continuously f or 170 days, and it is expected to do so until August 5, 1983.
The increase in the surveillance interval is less than 3 percent of the total allowed interval. This small increase in the surveillance interval would not increase the rod drop time.
Furthermore, the control rods are verified operable every 31 days in accordance with surveillance requirement 4.1.3.1.2.
Also, rod drop times have not been a problea at Westinghouse plants. The testing and experience to date at 8307270301 830715 PDR ADOCK 05000328 P
PDR omer >
sunme >
oney OFFICIAL RECORD COPY usam =-=*o Nac rom ms peoi sscu om
~"%{
U V
CD
'W T3
(
Sequoyah provides a basis for a high degree of confidence that the rods would drop into the core in the required time. Also, the increase in the surveillance interval would not increase the possibility that the rod bottom limit switches will not operate properly. The remaining portion of the circuit will be tested before the extended period is entered to verify the operability of the rod bottom lights in the remote shutdown contr31 room. Also, the rod position indicators, which pro-vide input to the bottom light bistables, have not exhibited calibration problems in the hot condition. A high degree of confidence also exists that the rod bottom lights would work in the remote shutdown control room in the unlikely event they were needed.
ENVIRONMENTAL CONSIDERATION We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any signifi-cant environmental impact.
Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
FINAL NO SIGNIFICANT HAZARDS CONSIDERATION (SHC) DETERMINATION The Commission made a proposed determination that the amendment involves no SHC which was published in the Federal Register (48 FR 29980) on June 29, 1983, and consulted with the State of Tennessee.
No public comments were received and the State of Tennessee did not have any comments. Based on the Commission's final review and the absence of State and Public comments, the Commission has made a final determination that the amendment involves no significant hazards consideration.
CONCLUSION We have concluded, based on the considerations discussed above, that: (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendmer.t will not be inimical to the common defense and security or to the health cnd safety of the public.
Dated: July 15, 1983 Principal Contributors: Carl Stable, Licensing Branch No. 4. DL om)
""'"3'*"
N""
2' OFFICIAL RECORD COPY W U.S.GPO 1933-400-247
- m.. =
r=
July 15, 1983 AMENDMENT NO. 20 TO FACILITY OPERATING LICENSE DPR SEQUOYAH UNIT 2 DISTRIBUTION w/ enclosures:
bec w/ enclosures:
v/' Docket No. 50-32//328 NRC PDR LB #4 r/f Local PDR C. Stahle NSIC M. Duncan TERA DELD A. Rosenthal, ASLAB E. Adensam ASLBP R. Hartfield, MPA ACRS (16)
R. Diggs, ADM W. Jones (10)
D. Ti srinhut /P. Porol o J. Souder T. Farnhart (4)
E. L. Jordan, DEQA: I&E J. M. Taylor, DRP: I&E L. J. Harmon, IE File D. Brinkman, SSPR H. Denton i
.