ML20207J840
| ML20207J840 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/16/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207J837 | List: |
| References | |
| NUDOCS 8701080616 | |
| Download: ML20207J840 (3) | |
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'o UNITED STATES
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- T,,g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 56 TO FACILITY OPERATING LICENSE NO. NPF-1?
SOUTH CAROLINA ELECTRIC & GAS COMPANY S0llTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 INTRODUCTION South Carolina Electric and Gas Company (SCEltG, the licensee) submitted information regarding revisions to the Virgil C. Summer Technical Specifications by letter dated June 20, 1986 from D. A. Nauman (SCE&G) to Harold R. Denton (NRC). The requested amendment involves administrative changes to Technical Specification sections 3/4.5.4, Table 4.3-R, Table 4.3-9, Table 4.3-2, and 3/4.2.4 bases.
The changes involve renumbering of sections, terminology changes for consistency, typographical corrections, and clarification of the notes to Tables 4.3-8 and 4.3 0 as to what instrument analog channel operation tests must demonstrate.
EVALUATION The following is an item-by-item evaluation of the licensee's requested changes to the Technical Specifications:
i (1) Technical Specification paragraphs 3.5.5 and 4.5.5 were renumbered to 3.5.4 and 4.5.5, respectively, to reflect the previous issuance of Amendment 44 l
to the Technical Specifications. This amendment had deleted section 3/4.5.4.
(?) As a result of an internal review, the licensee identified portions of the Technical Specifications dealing with radiation monitors which needed J
clarification. As identified in Tables 4.3-8 and 4.3-9, an analog channel operational test is required of effluent monitoring instrumentation. Notes contained in the tables (Notes 1 and 5 on page 3/4.3-72 and Note 1 on page 3/4.3-791 pertaining to certain monitors indicate that this test shall also demonstrate that automatic isolation of the pathway and control room alarm annunciation occurs if certain conditions exist. One of these conditions (existing item 4 of the notes) is the instrument controls not set in the operate mode. The licensee's position is that when those radiation monitors to which the notes apply are placed in the bypass position (via the Normal /
Bypass switch) for the performance of a test procedure, the monitors are considered inoperable and the applicable action statement is applied.
8701090616 861216 PDR ADOCK 05000395 P
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l The purpose and incorporation of the Normal / Bypass switch in the original design of the systems is to defeat the interlock function during calibration and maintenance to allow implementation of action statements without the i
need to temporarily lift leads and/or install jumpers. Therefore, the Normal / Bypass switch is not considered by the licensee to be one of the instrument controls as stated in existing Item 4 of the notes. To describe the existing system function, the low flow (alann only) and Normal / Bypass switch set in Bypass (alarm only) items were added to existing Notes 1 and 5 on page 3/4 3-72 and to existing Note 1 on page 3/4 3-79.
Table 4.3-8 i
did not reference Note 2 on page 3/4.3-72. Therefore, Note 2 on page 3/4.3-72 was deleted and existing Notes 3, 4 and 5 were renumbered 2, 3 and 4 respectively.
(3)
In a review of Technical Specification Tables 3.3-3, 3.3-5 and 4.3-2, inconsistencies in terminology were discovered by the licensee in three instances. These inconsistencies deal with line items containing terms such as "High-High" or "High 2" that are identified in each of the four tables. Therefore, the licensee proposed that these items be consistently i
identified.
It was also noted that for item 2.C in Table 4.3-2 on page 3/4.3-35, the correct term should be " Reactor Building Pressure - High 3" as opposed to the presently stated "3".
This terminology agrees with the i
j corresponding items found in Tables 3.3-3, 3.3-4 and 3.3-5, and identifies the correct actuation signal for Reactor Building Pressure.
(4) Typographical corrections were made to Technical Specification Page B 3/4 2-5.
This consisted of replacing " thimble" for " thimbles" and "L-11" for "2-11."
The staff has reviewed the information provided in the licensee's submittal and has found that (1) items 1, 3 and 4 above are either administrative or typographical corrections and (2) item 2 is a mixture of administrative and functional definition corrections. The staff has concluded that the administrative and typographical revisions proposed by the licensee are acceptable.
Further-more, the staff concludes that the function corrections to the ANALOG CHANNEL OPERATIONAL TEST Table Notation on pages 3/4 3-72 and 3/4 3-79 (item 2 above) are acceptable.
ENVIRONMENTAL CONSIDERATION This amendment involves a change in the surveillance requirements or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such findings.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9). Pursuant to 10 CFR 51.22(b)
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- no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
CONCLUSION We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the oublic will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulatiors and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: December 16, 1986 Principal Contributors:
Jon B. Hopkins, Project Directorate #2, DPLA Jerry L. Mauck, Electrical, Instrumentation and Control Systems Branch, DPLA I
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