ML20140E042
| ML20140E042 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/19/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20140E030 | List: |
| References | |
| NUDOCS 8603270149 | |
| Download: ML20140E042 (4) | |
Text
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'o UNITED STATES J
8" N
NUCLEAR REGULATORY COMMISSION
-y WASHINGTON, D C. 20555 r,
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.52 TO FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT N0.33 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY McGUIRE NUCLEAR STATION, UNITS 1 AND 2 INTRODUCTION By letter dated April 25 1985 Duke Power Company (the licensee) proposed amendments to the operating lic,enses for McGuire Nuclear Station, Units 1
.and 2, which would change the Technical Specifications in regard to Admin-istrative Controls (Section 6.0) and in regard to reportability requirements associated with the revision of the regulatory requirements of 10 CFR 50.72 and 50.73 as presented in Generic Letter 83-43 dated December 29, 1983.
The
-amendments would also correct a typographical error in Table 4.11-1 in which j
the word " inlet" has been used inadvertently instead of " outlet".
By letters dated November 13 and 26, 1985, and January 28, 1986, the licensee supplemented
+
i the April letter to clarify or provide additional information in support of L
the proposed change to Specification 6.12.
One of the licensee's requests regards Technical Specification 6.10 and has been addressed by separate i
amendment.- Our review of the remaining proposed changes is addressed below.
DISCUSSION In accordance with the licensee's request, these amendments correct the.in-j advertent use of the word " inlet"'for " outlet" in the description of the
~
Discharge and Conventional ~ Waste Water Treatment System Outlet delineated in Specification Table 4.11-1.
l Technical Specification 6.1.2 required that a management directive be re-issued annually to all station personnel stating that the Shift Supervisor l
~(or during his absence from the control room, a designated individual) is j
responsible for the control room command function.. These amendments change Specification 6.1.2 to clarify that the intended recipients of the direc-tive are only Nuclear Production Department Station personnel not vendor,-
contractor, or other personnel.
These amendments correct certain job titles.used in' the Technical Specification.
l The title of " Manager of Nuclear Production," and the title of "Vice. President, Steam Production," are changed to "Vice President, Nuclear Production."
- Similarly, the title " Executive Vice President, Power Operations," is changed to " Executive Vice President, Engineering, Construction and Production." The amendments also delete previous Figure 6.2-1, "Offsite Organization" and Figure 6.2-2, " Station Organization." These two figures were in error in some l
respects, and their inclusion in the Technical _ Specifications was redundant because they are contained in Chapter'13 of the'McGuire Nuclear Station Final 4
j Safety Analysis Report,'and are maintained there.in accordance with annual updating requirements of 10 CFR 50.71.
Page.XXI of the Index is modified to indicate these deletions.
7 8603270149 B60319 PDR ADOCK 05000369 P
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t The amendments add the Superintendent-of Integrated Scheduling.to Specifications 6.5.1.3, 6.5.1.5, 6.6.lb, 6.8.2, and 6.8.3c.
This change allows the Superin-l tendent of Integrated Scheduling to review and/or approve modifications of safety-related structures, systems or components (6.5.1.3), proposed tests and experiments which affect nuclear safety and are not addressed in the FSAR or 4
Technical Specifications (6.5.1.5), REPORTABLE EVENTS (6.6.lb) and procedures specified under Specification 6.8.1 and cha~nges thereto (6.8.2 and 6.8.3c), if e
designated to do so by the Station Manager.
In each of-these cases, the Operating Superintendent, Technical Services Superintendent, and the Maintenance Superintendent each have the same authority as allowed to the Superintendent of 2
Integrated Scheduling.
Since the Superintendent of Integrated Scheduling is
required to meet the same qualifications.as each of these superintendents, no loss of technical review capability occurs; therefore, there is no adverse im-l pact of safety.
l The changes to Technical Specifications 6.5.1.8 and 6.8.1 in these amendments allow the Station Services Superintendent or the Station Manager to review and approve. modifications relating to the Station Security Program and asso-_
1 ciated procedures. Previously that-responsibility was discharged only by the Station Manager. The change facilitates efficient resolution of security-related matters and has no adverse impact on safety. The modifications approved by the Station Services Superintendent are transmitted.to the Vice President, Nuclear Production and to the Director of the Nuclear Safety Review Board.
Also, two typographical errors (one each in 6.5.1.8 and 6.5.1.9)-are corrected a
]
by inserting "12" for "!2".
i t
The Semiannual Radioactive Effluent Release requirements listed in Technical 1
Specification 6.9.1.7 (pg. 6-20) receive minor word changes by these amendments-to make these requirements consistent with 10 CFR.Part 61. A footnote on this page (which excluded requirements for certain waste shipments before January 1, 1984) was outdated and, therefore, is deleted.
These amendments also update and clarify Section 6.9 of the McGuire Technical l
Specifications, which relates to reportability requirements. As presented in q
~ Generic Letter No. 83-43 dated December 19, 1983, the regulations regarding reporting of events (10 CFR Sections 50.72 and 50.73) were changed. Subse-quently, Section 6.9 of McGuire's Technical Specifications was amended to reflect the new reporting requirements. When this section was. amended, however, the references in other parts of the Specifications were not updated. 'These other affected Specifications are 3.3.3.8.c, 3.3.3.9.c, 4.4.5.5.c,-Table _4.4-2, i
3.4.8 (pg. 3/4 4-26), 4.6.1.6, 4.6.1.7, 4.8.1.1.3, 3.11.1.1, 3.11.2.1, and 3/4 t
4-5).
These present amendments, therefore, updated these references. Refer-ences to Specification 6.9.1.11b are deleted because Specification 6.9.1 has been so changed that references to.it are virtually meaningless.- These refer-ences to Specification 6.9.1 are modified on an individual basis to preserve j
present reporting requirements, but to clarify these requirements and remove redundancies in the requirements.
The change to Specification 6.12 by these amendments provides consistency be-
' tween McGuire and Catawba High Radiation Area Technical Specifications 'and reflect the wording of the current draft of Revision 5 to the Standard Technical l
Specifications. The licensee's letter of November 13, 1985, noted that a foot-1 i
. ~ _ _ _.. -.., _ _
note reference (an asterisk) had-been inadvertently omitted in the changes to Specification 6.12.2 as requested April 25, 1985, and provided a corrected re-placement page (6-24) to correct this oversight. The licensee's supplemental letter of November 26, 1985, requested a minor addition (i.e., insertion of the phrase "as defined in 10 CFR Part 20") to Specification 6.12.1 to clarify the intent of this specification as proposed in the April 25, IM5 letter, and thereby avoid misinterpretation. The licensee's letter dated January 28, 1986, provided additional supporting information defining the qualifications of the
" individual qualified in radiation protection techniques" as used in the change to Specification 6.12.1.c consistent with the interpretation associated with 5tandard Technical Specification 6.2.2.d. ~ The change to 6.12, as supplemented, does not significantly affect current radiation protection practices at McGuire, but is largely semantic and is intended to clarify the requirements relative to definition of and access to high radiation areas.
The issuance of McGuire Amendments 32 (Unit 1) and 13 (Unit 2) resulted in the renumbering of several pages in Section 6 of the Technical Specifications.
This resulted in duplication when pages 6-27 and 6-28 were not deleted. Since page 6-27 duplicates 6-25, and 6-28 duplicates 6-26, the present amendments delete pages 6-27 and 6-28 from the Technical Specifications.
EVALUATION Based upon our review, we find each of the above changes to the Technical Specifications by these amendments to be of an administrative nature or (with respect to amendments relating to the Station Services Superintendent and the Supervisor for Integrated Scheduling) to be otherwise acceptable. The admini-strative changes improve the Technical Specifications by updating, clarifying and correcting them.. These changes do not effect any equipment or plant operational procedures. The changes have no adverse affect on safety and are, therefore, acceptable.
As discussed above, the changes involving the Station Services Superintendent and the Superintendent of Integrated Scheduling do not adversely impact on.
safety and are acceptable.
ENVIRONMENTAL CONSIDERATION The amendments relate to changes in recordkeeping, reporting or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assess-ment need be prepared in connection with the issuance of the amendments.
CONCLUSION The Comission made a proposed detemination 'that the amendments involve no significant hazards consideration which was published in the Federal Register (50 FR 32793) on August 14, 1985, and consulted with the state of North Carolina. No public coments were received, and the state of North Carolina did not have any coments.
o We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
.r Principal Contributors:
Darl S. Hood, PWR #4 PWR Licensing-A W. Meinke, Radiological Assessment Branch, DSI R. Latta, Region II M. Runyan, Region II-E. Gruber, Region II Dated:
March 19, 1986 f
,.,.