ML19262B605
| ML19262B605 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
| Issue date: | 12/18/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8001030044 | |
| Download: ML19262B605 (6) | |
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NOV 211979 MEM0RAN6UM FOR:
G. A. Arlotto, Dir ector Division of Engineering Standards Of fice of Standards Development FROM:
W. M. Morrison, Assistant Director for General Engineering Standards Division of Engineering Standards Office of Standards Development
SUBJECT:
BACKGROUND INFORMATION ON PROPOSED REVISION 2 TO REGULATORY GUIDE 1.97, " INSTRUMENTATION FOR LIGHT-WATER-COOLED NUCLEAR POWER PLANTS TO ASSESS PLANT AND ENVIRONS CONDITIONS DURING AND FOLLOWING AN ACCIDENT" The proposed revision to Regu btory Guide 1.97 and the Value/ Impact Statement were forwarded to Program Support Branch for editing, printing, and publication for comment on November 9, 1979.
The background information on how major comments from line offices wcre resolved, significant changes subsequent to staff review, and why the particular implementation schedule was chosen are provided below.
Comment Resolution Comment 1:
The title of the guide is not broad enough.
The guide covers more than " plant conditions."
Resolution:
"and Environs" was added to the title to broaden the scope.
Comment 2:
If we are to follow the recommendations as proposed, on the basis of the cla',ifications given, most of the listed instruments will have to be installed on the main panel of the control room. We recommend that a fifth design classification, of lower quality than the proposed four classifications, be developed.
This f?fth classificction would include instruments used for diagnostic purposes, provide useful information other than to the control room operator, or are included as part of our defense-in-depth philosophy.
Resolution: A fifth type was added and was designated and defined as:
Type E - those variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and for continuously assessing such releases, for providing defense-in-depth, and for diagnosis.
Comment 3:
Somehow we need to add a statemert that, for radiological monitoring instruments, the requirements of ANSI N320-19 M apply unless different specifications are provided in the regulatory 5uide.
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Resolution:
The statement was added by a note in Table 1.
Comment 4:
No mention is made of the second part of Criterion 19 pertaining to instrumentation located outside the control room.
Resolution:
The statement in the " Introduction" of the regulatory guide pertaining to Criterion 19 was expanded to include " equipment at appro-priate locations outside the control room be provided with a design capability for prompt hot shutdown of the reactor including necessary instrumentation."
Comment 5:
I was informed '.oday of your decision to delete core temperature measurement from BWR's.
I strongly cppose this deletion.
Resolution:
The core temperature measurement was changed from " temperature in bottom of plenum with a range of 150*F to 700 F" to " core exit temper-ature with a range of 150 F to 2300 F."
Significant Changes Subsequent to Staff Reviaw Several changes were made in the variables listed in Tables 2 and 3 as a result of consideration of comments on wording changes and suggested range changes and to accommodate the addition of the classification designated as Type E.
In addition to the changes made as a result of the comment resolution above, the following significant changes were made:
1.
A statement was added to the Discussion section on the importance of developing, on a reasonable time schedule, the ability to provide direct indication of coolant level in the reactor vessel of PWR's.
2.
The guide was modified to endorse ANS-4.5, Draft 4 dated November 1979, rather than Draft 3 dated September 1979.
This resulted in deletion of eight positions from the guide, because the exceptions taken to portions of Draft 3 have been acceptably modified or deleted in Draft 4.
The fol-lowing positions were deleted:
(a) Position 5 which pertained to the local environment of instrumenta-tion components.
(Section 5.2.1(5)) D,ft 3 limited concern to just
.he instrument, not all instrumentation components.
Draft 4 includes all instrumentation components.
(b) Position 6 which pertained to the performance requirements for Type C instrumentation.
(Section 5.2.2) Draft 2 did not adequately address Type C performance requirements.
Draft 4 includes acceptable performance requirements for type C instrumentation.
(c) Position 8 which pertained to qualification for vibrational loads of the plant.
(Section 6.1.1) Draft 3 limited consideration of vibra-tional loads on the instrument and only during the phase for which 2206 002
G. A. Arlotto 3
the instrument was required.
Draft 4 was modified to include consid-eration of vibrational loads on all components for the duration of the accident or until their function is no longer required.
(d) Position 10 which pertained to location of instrument displays.
(Section 6.1.6)
Draft 3 implied that all instrumentation components should be located accessible to the operator, not just the displays.
Draft 4 was modified to state that displays should be accessible to the operator.
(e) Position 11 which pertained to the importance of Type B instruments.
(Section 6.2.1) Draft 3 contained a statement that Type B instruments constituted an extra set of instrumentation.
The statement was removed in D. aft 4.
(f) Position 13 which pertained to the instrument transient response being determined by the capability of the recorder.
(Sections 6.3.2.3, 6.3.3.3, 6.3.3.4, 6.3.4.3, 6.3.4.4, G.3.5.2, 6.3.5.3, and 6.3.4.5)
Draft 3 contained the statement that the instrument transient response should be set by the recorder capability.
The statement was deleted in Draft 4, and the response is to be established by the requirements of the measurement.
(g) Position 14 which pertained to the acceptability of normal instrument accuracy.
(Sections 6.3.3.3, 6.3.3.4, and 6.3.4.3)
Draft 3 contained a statement that normal instrument accuracy is acceptable.
The statement was deleted in Draft 4 and accuracy is to be established by the requirements of the measurement.
(h) Position 15 which pertained to the qualification of Type C instru-mentation.
(Section 6.4.1)
In Draft 3, the qualification require-ments for Type C instrumentation was confusing but has been clarified in Draft 4.
Implementation Schedule The guide was written for forward-fit, and the first part of the implementation section was written to encourage public participation in the guide development which would be implemented after the active guide is issued.
The second part of the implementation states that part or all of the guide may be applied to operating plants, plants under construction, and plants under review and would be determined on a case-by-case basis.
It is the intention of the staff to meet, during the public comment period, with the various owners' groups to obtain input on backfitting recommendations and impact.
This proposed revision of the guide was reviewed by the ACRS Regulatory Activ-ities Subcommittee on November 7, 1979, and, at the request of the Subcommittee chairman, was reviewed by the full ACRS on November 9, 1979. Concurrence was received for publication for public comment.
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The lead division is DSS and the cognizant individuals in NRR are:
V. Benaroya, DSS; R. Scholl, DOR; L. Soffer, DSE; and P. Stoddart, DSE.
Original signed by W. 3L 3Iorrison W. M. Morrison, Assistant Director for General Engineering Standards Division of Engineering Standards Office of Standards Development bcc:
R. B. Minogue Distribution G. A. Arlotto Central File W. M. Morrison SD Alpha E. C. Wenzinger RSSB WR J. D. Buchaaan RSSB RD A. S. Hintze RSSB Subj.:
6097 Task No.:
RS 917-4 M
/U' CRESS NL SD:RSSB S :RSSB SD:A/D Job I 1 ASHintze:jk ECWenzinger WMMorrison 11/20/79 11Mt.0/79 11/gt /79 11/,.;/79 2206 004