ML20236D366
| ML20236D366 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/22/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236D362 | List: |
| References | |
| NUDOCS 8710280168 | |
| Download: ML20236D366 (4) | |
Text
_
g>* Al Cug UNITED STATES
+
y y1 g NUCLEAR REGULATORY COMMISSION l
WASHINGTON. D. C. 20555
\\...../
SAFETY _ EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.11 TO FACILITY OPERATING LICENSE NO. NPF-43 DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED FERMI-2 OOCKET NO. 50-341
1.0 INTRODUCTION
By letter dated January 7, 1987, Detroit Edison Company (the licensee) requested changes to the Technical Specifications for Fermi-2.
The request of January 7, 1987, has been supplemented by information provided in letters dated March 6, 1987, and May 20, 1987.
The requested changes would revise the Administrative Controls Section of the Technical Specifications.
The specific changes are aescribed and evaluated below.
2.0 EVALUATION 1.
Figure 6.2.1 Offsite Organization The licensee has revised the offsite organization by establishing the position of Group Vice President to direct the nuclear operations organization.
Reporting to the Group Vice President are the Vice President Nuclear Operations, Vice President Nuclear Engineering and Services, and Director Nuclear Quality Assurance.
g This organization is shown in proposed revised Figure 6.T.1-1.
Reporting to the Vice President Nuclear Operations are the Plant Manager Nuclear Production, Director Nuc1 car Training General, and Director Operator Training.
Reporting to the Vice President Nuclear Engineering and Services are the Director Regulatory Affairs, Director Nuclear Engineering, and Director Nuclear Services.
Reporting to the Director Nuclear Quality Assurance is the quality assurance organization.
We have reviewed this requested change and find it acceptable as it meets the acceptance criteria set forth in Section 13.1 of NUREG-0800, the Standard Review Plan.
8710280168 871022 PDR ADOCK 05000341 P
PDR I-
___________o
4 p.-
1 s
- !i l r
21 Figure 6.2.2-1 Unit Organization j
g nThe licensee has' revised.the unit. organization under-the Plant
.I D Managst,' Nuclear Production whol reports to the Vice. President '
N L
Nuclear.0perttions.
Reporting to the. Plant Manager,; Nuclear'
4 Production are-the Superintendent Services, Radiation Protection
i L!
Engineer, Superintendent Operations, Superintendent Maintenance
.and Modification, and Technical _ Engineer.> The former positions of
. Assistant' Manager Nuclear Production, Assistant to the Superintendent, Radiation Protection.-- Chemical.. Engineer, Reactor Engineer and Nuclear. Fuel Handling Supervisor have been deleted.
The-new positions of^ Plant Manager, Nuclear Production,.. Superintendent-i Services, Radiation Protection Engineer, Operations Support' Engineer, General; Supervisor Radwaste, and General Supervisor l
Chemistry have been. established. - The revised organization is shown-in proposed revised Figure 6.2.2-1.
We~ find:this revised organization' acceptable.-as it retains the necessary support for plant operations and meets:the acceptance 1
. criteria set forth'in Section 13.1.2-13.1.3 of NUREG-0800.
3.
Section 6'.5.1.6 -- Onsite Review Organization (OSR0) Responsibilities The licensee has proposed revisions to the responsibilities of the
'0SRO.
Item a, Section 6.5.1.6, which requires the OSR0 to review all procedures required by. Specification 6.8 and changes thereto, would be deleted and replaced by the requirement that the OSR0 l
review all plant administrative procedures and changes thereto.
A new section would be added that requires the OSRO to review the-safety evaluation for plant procedures and changes thereto completed under the provisions of 10 CFR.50.59 The licensee proposes adding a new Section'6.8.3 which would provide for the review of. procedures other than plant adminic+rftive procedures.
147 We find the requested change acceptable as the review of plant procedures is not deleted (see Section 5.3), and the review of administrative procedures' meets the acceptance criteria set forth in Section 13.5.1 of NUREG-0800.
4.
Section 6.5.3 - Technical Review anc Control 18.* licensee has established a program that requires the procedures requ:ved by Technical Specification 6.8, except for administrative crocedares (see 3. above) to be independently reviewed by quelified ind viduals prior to implementation.
1
- o
(
1
)
f 1 f
The NRC staff initially found the provisions for the review of j
procedures' acceptable except for qualifications of individuals who will perform the reviews and' evaluations, in that the licensee stated that the individuals'shall meet or exceed the qualifications r
l-stated in Sections 4.'3 or 4.4 of ANSI N18.1-1971 for the appropriate i
discipline.
It was the staff's position that individuals shall meet or exceed the qualifications stated in Sections 4.2 or 4.4 of ANSI N18.1-1971-for the appropriate discipline.
In a telecon with the-4 licensee on August 14, 1987, it was determined that reference to l
Section 4.3 of ANSI N18.1-1971 was a typographical error.
The correct reference should be 4.2 or 4.4 of that Standard.
5.
Sections 6.8.2, 6.8.3, and 6.8.4 (Procedural Programs) a.
Section 6.8.2 - This section would be changed to delete the requiremq:t that each procedure required by Section 6.8.1 shall be reviewed by the OSR0 and cpproved by the Assistant Manager -
3 Nuclear.
The revised Section 6.8.2 would require that each plant admini<,trative procedure shall be reviewed in accordance with Specification 6.5.1.6 and approved by the Plant Manager.
b.
Section 6.8.3 - The current Section 6.8.3 that has requirements with respect to temporary changes to procedures would be renumbered Section 6.8.4.
A new Section 6.8.3 would be added that requires each plant procedure requited by Specification E.8.1, other than administrative procedures, shall be reviewed in accordance with Section 6.5.3 and approved by the Plant Manager or other specifically designated individuals.
c.
Section 6.8.4 (formerly Section 6.8.3) - The requirement that temporary changes to procedures shall be reviewed by the 05R0 and approved by the Assistant Manager - Nuclear Production would be deleted. A new requirement would be added that requires the change to be reviewed and approved in accordance with either Section 6.8.2 or 6.8.3 as appropriate.
m s:
We find these requested changes acceptable as they provide for the review and approval of plant procedures that meet the acceptance criteria set forth in Section 13.5.1 of NUREG-0800.
- 6..The licensee has proposed numerous changes in titles throughout Section 6 to reflect the revised organization.
Additionally, there have been several editorial changes.
We have reviewed these changes and find that they reflect the revised organization and/or are editorial corrections and are, therefore, acceptable.
.4
3.0 ENVIRONMENTAL CONSIDERATION
This amendment relates to changes in.recordkeeping, reporting,'or i
administrative procedures or. requirements.
Accordingly,'this amendment meets-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. assessment need. be prepared in connection
'with the issuance of this amendment.
j
4.0 CONCLUSION
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 1
. activities will be conducted in' compliance with the Commission's regula-tions 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.
Principal Contributors:
F. A11enspach, NRR J. Stz'9no, NRR Dated: October 22, 1987
.Ij WQG il o
a
. _ _.