ML17272A237
| ML17272A237 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/10/1979 |
| From: | Collins P Office of Nuclear Reactor Regulation |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901150274 | |
| Download: ML17272A237 (6) | |
Text
IC JAN 10 1979 Docket No. 50-397 MEMORANDUM FOR-FROM:
SUBJECT:
.PLANT NAME:
Steven A. Varga, Chief, LMR Branch t4, DPM
'I Paul F. Collins, Chief, Operator Licensing Branch, DPM
RESPONSE
TO REVIEW PLAN ASSIGNMENT REVIEW OF CONDUCT OF OPERATIONS 1
(SECTIONS 13.2 AND 13.5)
MPPSS Unit 2 DOCKET NUMBER:
50-397
'ICENSING STAGE:
OL Complete
'BRANCH AND PROJECT MANAGER REQUESTING ASSISTANCE:
LMR - M. Lynch REVIEW BRANCH INVOLVED:
DPM:OLB REQUESTED COMPLETION DA'K:
January 8, 1979 DESCRIPTION OF REVIEW:
Review of Conduct of Operation, Sections 13.2 and 13.5 REVIEM STATUS:
First Round questions Me have reviewed Sections 13.2 and 13.5 of the FSAR.
Based on our review, we have determined that the additional information, identified in the enclosure, is necessary fcr us to complete our review.
We will be available to discuss these.items, should the applicant so desire.
Paul F. Collins,'Chief Operator Licensing Branch Division of Project Management
Enclosure:
Attachment A
orricsP OVIlNAIIK+
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cc:
see next page
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440.0 OPERATOR LIGENS ING 'BRANCH 441. 1 (None) 441.2 (13.2.1.1)
Provide a detailed description of the fire protection training and retraining for the initial plant staff and replacement personnel so that the findings addressed in paragraphs 11.6.A-E of Section 13.2 NUREG-75/007 (Rev. 1), Standard Review Plan can be made.
Discrepancies, possibly in termonology, exist between the training programs described in paragraph 13.2.1.1 and those shown in Figure 13.2-1 as follows:
441.3 (None) 1.
The Nuclear Energy training shown in Figure 13.2-1 is not described in paragraph 13.2.1.1.
2.
Basic Nuclear Theory is described in paragraph 13.2. 1. 1.1 but is not shown in Figure 13.2-1.
3.
BWR Fundamentals shown in Figure 13.2-1 but is not described as such in paragraph 13.2.1. 1.
4.
Turbine generator training is shown in Figure 13.2-1 but is not described in paragraph 13.2.1.1.
The termonology must agree between Figure 13.2-1 and the course description.
Provide the contingency plans for additional training for individuals to be licensed prior to criticality, should the fuel loading be delayed from the date indicated in the FSAR.
441.4 (13.2.2.1.2) 441. 5 (13.2.2)
The reactivity manipulations performed to satisfy the requalification requirements 10 CFR Part 55 Appendix A (3a) must be approved by NRC.
The approved BWR manipulations can be found in American National Standard ANSI/ANS 3.1. 1978 paragraph 5.5.1.2.1, control manipulations.
A statement should be included in the program which indicates that the individuals who prepare and grade the Annual Retraining examination are exempt from taking the examination.
A maximum of three licensed personnel may be exempt.
442.1 (13.5.1)
Provide a diagram of. the control room area which indicates the area designated "at the controls."
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