ML17286A577
| ML17286A577 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/30/1991 |
| From: | Meadows T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| TAC-77486, NUDOCS 9102130005 | |
| Download: ML17286A577 (46) | |
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+~*yW UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1450 MARIALANE,SUITE 210.
WALNUTCREEK, CALIFORNIA94596 January 30, 1991 MEMORANDUM FOR:
Docket File
~ Washington Public Power Supply System (WPPSS)
WPPSS Nuclear Unit No.
2 (WNP-2), Docket No. 50-397 FROM:
SUBJECT'
REFERENCES:
Thomas R. Meadows Licensing Examiner MEETING
SUMMARY
- JANUARY 25, 199l MEETING TO DISCUSS WNP-2
RESPONSE
TO NRC EOP INSPECTION TEAM ISSUES (a)
NRC Inspection Report 50-397/90-20 (b)
Response
- Letter, G. Sorensen, dated November 25, 1990 On January 24, 1991, members of the NRC staff met with representatives of WPPSS (the licensee) to discuss the issues presented in reference (a) as requested by reference (b).
A list of the attendees is provided in Enclosure l.
A copy of the licensee s initial corrective action analysis
- summary, presented at this meeting, is provided in Enclosure 2.
The licensee stated that the three deviations from the BWROG EPGs, of concern:
Primary Containment Venting Steam Cooling Termination, and Primary Containment Flooding were referred to NRR for. guidance.
The NRC staff (NRC) acknowledged that that these deviations were designated as open items, and were assigned to the Division of Systems Technology, Reactor Systems and Plant Systems
- Branches, NRP, (TAC 77486).
These items remain open.
The licensee stated that the resolution of Open Item 90-20-05
( Implementation of EOP Caution 1 - RPV Level Instrumentation) involves the completion of their situation based evaluation of the credible.events (fire and unisolated high energy line break in the reactor building), that would require RPV level instrumentation to be considered inoperable.
The licensee stated that the evaluation and corresponding procedural development activities are expected to be completed by March 1991.
The licensee also stated that EOP Caution I will be updated accordingly, and committed to forward the details of this effort to the NRC by March 1991.
This item remains open.
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The licensee stated that the EOP graph errors (Open Item 90-20-06, Calculational Errors in EOP Graphs) were corrected.
An LER (90-019) was issued with a root cause evaluation and supplemental review of all graphed information.
The licensee stated that the cause of this event was personnel error during the procedure revision process.
The licensee committed to correcting their revision process encompassing the wIiters guide, the process for calculation incorporation into technical basis documents, and EOP verification and validation, in order to prevent a recurring event.
The licensee stated that an expanded report of follow-up corrective actions, based on their current review of all EOP calculations will be forwarded via a revised LER by the end of January 1991.
This item remains open.
9102130005 910130 PDR ADDCK 05000397 P
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January 30, 1991 The licensee addressed the remaining issues, primarily Open Item 90-20-04 (Development and Verification and Validation of EOP's and EOP support procedures),
in an analysis summary (Enclosure 2), which details their initial position on these issues.
The licensee clarified that the Completion Status Code 3, "Will Not Be Implemented,"
meant that these items were not of immediate
- concern, in that they had minor safety significance, had little effect on adequate procedure
- guidance, or were not valid.
Furthermore, the licensee stated that all of these issues will be reevaluated during their scheduled revalidation of the entir e population of EOPs, Emergency Support Procedures, and associated flow charts.
This effort would begin after the hiring of a Human
'actors
- Engineer, and a review of the EOP writers guide and associated changes to the EOPs by this individual.
The licensee stated that a detailed completion schedule (supplementing Enclosure
- 2) will be forwarded based on this review, by the end of April 1991.
After a detailed review, the HRC personnel present agreed that Completion Status Code 3 items were properly classified, and stressed the necessity for the licensee to complete the commitment for an expanded action plan.
The NRC stressed that timely resolution to a11 of these issues is expected.
The licensee acknowledged this concern.
Enclosures:
As Stated r
~t.
Thomas R.
Meadows Licensing Examiner cc w/enclosures:
See Attached List Docket Fi1e C. Sorensen, SRI K. Perkins, RY R.
Zimmerman, RV P. Johnson, RV P.
Eng; NRR J. Hermeil, tlRR J. Dyer, HRR J. Kudrick, NRR
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Enclosure 1,
LIST OF ATTENDEES NRC T. Meadows L. Miller G. Galletti WPPSS T. Messersmith J.
Baker S.
McKay G. Sorensen
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ENCLOSURE 2
1990 EOP INSPECTION REPORT ANALYSISSUh&IARY COMPLETION STATUS I =
64 (60.4%)
2=
10
( 9.4%)
3=
32 (30.2%)
1990 EOP INSPECTION REPORT ANALYSISTOTALS WRITERS GUIDE (I OR 2 MPACI)=
7
( 6.6%)
VERIFICATION(I OR 2 IMPACT)=
32 (30.2%)
VALIDATION(1 OR 2 IMPACI)=
17 (16.0%)
OTHER (INCLUDINGNO IMPACT)= 50 (47.2%)
TOTAL 106 TOTAL 106 COMPLETION STATUS I
CORRECTIVE ACTION WILLBE IMPLEMENTED AS NECESSARY 2
WILLAWAITHUMANFACTOR EVALUATION BFFORE DECIDING ON ACTION 3
WILLNOT BE IMPLEMENTED
1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATUS I CORRECTIVE ACTION WILLBE IMPLEMENTED AS ÃECESSARY 2
WILLAWAITHUMANFACTOR EVALUATIONBEFORE DECIDING ON ACTION 2
WILLNOT BE IMPLEMENTED DISCREPANCY (DESCRIFI'ION)
PPM 1.2.3:
Deviation procedure not adequate for EOP's.
PPM 1.3.51:
Independent verification of safety related component labels desired.
WRITER' GUIDE VERIF.
ADMIN VERIF.
TECH.
VALIDATION CLOSURE DATE COhIP.
STATUS COMKIENTS Evaluating deviations with procedure control.
PQC prior to deviation; EOP Coordinator Review.
Non EOP issue.
Label Coordinator to change label PPM.
PPM 2.3.1:
Confusing steps.
PPM 2.3.1:
Confusing controller setting (5% above).
PPM 2.3.1:
No labeling on BD Rad 22 (23) recorders.
PPM 2.3.1:
Valves not in the MEL.
PPM 2.3.3:
Board designation alternates between P827 and K 1(K2).
PPM 2.3.1:
Incorrect switch designation.
PPM 2.3.3:
Switches not keylock.
PPM 2.10.1:
REA-FlC-3A Setpoint not adjustable externally by operator.
1 To be resolved in biennial review.
Several at tempts have been previously made to correct.
Present guidance to be validated ASAP.
Recorders are due to be changed out.
R-6.
Valves are in MEL. Because of software requirements last - must be entered as l.
Hard copy of MEL must be consulted.
GE board designation will be used.
Biennial Review.
Writer's Guide to be changed.
1 Rev. 8 Fixed.
1 To be resolved ASAP.
Willprovide more specific guidance.
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1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATUS I 2
3 CORRECTIVE ACTION WILLBE IMPLEMENTEDAS NECESSARY WILLAWAITHUMANFACTOR EVALUATIONBEFORE DECIDING ON ACTION WILLNOT BE IMPLEMENTED DISCREPANCY g)ESCRIPTION)
PPM 2. 10.1: Building controller thumbwheel -.6 versus
+.6.
PPM 2.10.1:
Controller setting incorrect.
PPM 2.10.1:
No auto position, not enough detail for operators to function. More training required.
PPM 2.10.1:
Platform for Operations.
PPM 2.10.1:
ROA-TIC-3 had no label.
PPM 2. 10.1: Shifting damper control to auto not fully described and locations of fans not accurate.
PPM 3.3.1:
Contains reference to RWP PPM.
IVRITER'S GUIDE VERIF.
ADMIN VERIF.
TECH.
VALIDATION DATE STATUS COMMENTS To be resolved ASAP.
To be resolved ASAP To be resolved in biennial review.
Normal after Start/Stop is commonly referred to as Auto.
TER willbe issued to install permanent scaffold.
Label request issued.
Validation will be performed and any necessary corrective action taken.
Plant management directed inclusion of this PPM.
PPM 3.3.1:
Duplicated step on two pages.
PPM 3.3.1:
GDS verses Graphic display system.
PPM 3.3.1:
Group Isolation attachment does not say where to check.
PPM 3.3.1:
Implicit reference to PPM 4.12.4.6.
PPM 3.3.1:
Incorrect punctuation in a step-Use of AND/OR.
PPM is correct as written.
Not against present writers procedure.
Checking of~I is important.
Format acceptable.
Plant wrih.rs PPM not violated.
Human factors will look at this.
1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATUS I 2
2 CORRECTIVE ACTION WILLBE IMPLEMENTEDAS NECESSARY WILLAWAITHUMANFACTOR EVALUATIONBEFORE DECIDING ON ACTION WILLNQT BE IMPLEMENTED DISCREPANCY (DESCRIPTION)
PPM 3.3.1:
Indicates using printout when the operators use the screen.
PPM 3.3.1:
Note placed after step to which it applies.
PPM 3.3.1:
Pagination incorrect.
PPM 3.3.1:
Panel C verses Board C.
PPM 3.3.1:
Procedure deviation system sometimes results in poor print quality deviations.
PPM 3.3.1:
Referenced section of another PPM incorrect (RCIC).
WRITER'S GUIDE VERIF.
ADMIN VERIF.
TECH.
VALIDATION CLOSURE DATE COMP.
STATUS COMMENTS The printouts are available-will be an 'option to use either the screen or the printout.
Note placed ~f substep to which it applies.
Correct as written.
Pagination has been corrected.
Writer's Guide will be revised.
Process for Pdf's willevolve with procedure upgrade.
Present guidance adequate.
Referenced PPM was revised removing section number.
%'ill be corrected.
PPM 3.3.1:
Referenced section of another PPM incorrect (HPCS).
PPM 3.3.1:
RHR-Y-123A and B cannot be closed from control room.
PPM 3.3.1:
Use of all caps to indicate position and not as labeled.
PPM 3.3.1:
Use of PSI/Sec instead of PSIG/Sec.
PPM 5.0.0:
EOP Caution 1 wording was non-conservative in that the case of temperature "equal to the saturation tcmpcraturc was not cautioned.
Referenced PPM was revised removing section number.
Willbe corrected.
Caution tag controls valves.
Should not be caps.
To be corrected ASAP.
To be corrected ASAP.
Proposed PPM mark-up complete.
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1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATUS I CORRECTIVE ACTION WILLBE IMPLEMENTEDAS NECESSARY 2
WILLAWAITHUMANFACTOR EVALUATIONBEFORE DECIDING ON ACTION 3
WILLNOT BE IMPLEMENTED DISCREPANCY IDESCRIPI'ION)
PPM 5.0.0 The placement of cautions in a separate procedure makes it difficultfor operators to use the information.
Operators should not be required to transition to another location to read cautions.
PPM 5.0.1:
HCTL and PSPL curves contained non-conservative errors relative to their associated calculations.
PPM 5.0.4:
EOP Flowchart Validation only requires that validation for revisions to procedures
"...need only encompasses the changes made to the previously approved procedure.
IVRITER'S GUIDE X
~
VERIF.
ADMIN VERIF.
TECH.
VALIDATION CLOSURE DATE COMP.
STATUS COMMIWiTS Corrected PPM deviation in place.
Verification of all calculations number's will be conducted.
Results willbe forwarded via LER supplement.
PPM 5.0.4 specifies the minimum requirement.
The Operations Procedure Coordinator will determine ifany further increase in validation efforts are required when EOP flowcharts are revised.
Will evaluate current guidance for adequacy.
PPM 5.0.6:
Add the tools required for PPM 5.6.1, SBO to list.
PPM 5.1.1:
Contingency callouts not used for ~v transition to RPV Flooding or Emergency RPV Depressurization.
PPh'I 5.1.1:
PPM step, "IF the continuous SRV nitrogen supply is or becomes unavailable...", should be structured as an override but isn'.
(Inadequate verification.}
I Proposed PPM mark-up complete.
proposed PPM mark-up complete.
PPM is correct as written relative to W.G.
criteria.
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1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATUS I 2
3 CORRECTIVE ACTION WILLBE IMPLEMENTEDAS NECESSARY WILLAWAITIIUMANFACTOR EVALUATIONBEFORE DECIDING ON ACTION WILLNOT BE IMPLEMENTED DISCREPANCY (DESCRIPHON)
PPM 5.1.1:
References to ESP's are formatted with the procedure number alone, without the required title. (Inadequate verification.)
PPM 5.1.1:
The procedure does not use directives in active voice to direct action for a high level task.
(Inadequate verification.)
PPM 5.1.1:
The qualifier "other than is used vice the term "except".
(inadequate verification.)
PPM 5.1.1:
The transition to Primary Containment Flooding on low RPV level is confusing'.
PPM 5.1.2:
A fiowchart structure is used that is not specifically allowed by the Writers Guide.
PPM 5.1.2:
A particular step contains four qualifying terms.
PPM 5.1.2:
AtII'lace in the PPM the abbreviation S.P." was used vice SP".
PPM 5.1.2:
Contingency callouts missing (one for RPV Flooding and one for Emergency RPV Depress).
PPM 5.1.2:
Inconsistent teriltinofogy usaf.
Similar steps should be written using the same terminology.
IVRITER'S GUIDE VERIF.
ADMIN VERIF.
TECH.
VALIDATION CLOSURE COMP.
DATE STATUS COMMENTS Proposed PPM mark-up complete.
Verification checklist to be changed.
Procedure is correct as written.
Proposed PPM mark-up complete.
PPM 5.1.2 does not contain any of the unauthorized fiowchart s~aucture relative to this deficiency.
Proposed PPM mark-up complete.
Simplified structure willbe used.
Proposed PPM mark-up complete.
Note: Allcontingency callouts willbe changed to "NOTES".
Proposed PPM mark-up complete.
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1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATIIS I 2
3 CORRECTIVE ACTION WILLBE IMPLEMENTEDAS NECESSARY WILLAWAITHUMANFACTOR EVALUATIONBEFORE DECIDING ON ACTION WILLNOT BE IMPLEMENTED DISCREPANCY g)ESCRIFHON)
PPM 5.1.2:
Location information for P609 and P611 was given in a format other than specified in the W.G.
PPM 5.1.2:
Periods used in the abbreviation "chg. hdr. isol. valve.
PPM 5.1.2:
PPM contains additional information not specifically required.
PPM 5.1.2:
PPM uses "ATWS/ARI"vice"ATWS-ARI'PM 5.1.2:
The step "Terminate boron injection if initiated" is a conditional step structured in a manner that violates W.G.
requirements.
inadequate verification.}
PPM 5.1.2:
Wording for the step which asks, "Is more than one control rod not fully inserted?", is confusing.
PPM 5.1.3:
"Wait Until" symbol inconsistently used (i.e., ILnn; of the symbols included the words then proceed").
WRITER' GUIDE VERIF.
ADMIN VERIF.
TECH.
VALIDATION CLOSURE COMP DATE STATUS Proposed PPM mark-up complete'.
Proposed PPM mark-up complete.
Validation caused this note to be added and has since proven beneficial to PPM users when dealing with ATWS.
Proposed PPM mark-up complete.
Proposed PPM mark-up complete.
Proposed PPM mark-up complete.
Usage of the "Wait Until symbol willbe eliminated.
Proposed PPM mark-up complete.
PPM 5.1.3:
Suggested working change to a step to eliminate the use of the word "until".
Suggested fit is technically incorrect and doesn't fitcorrect word usage.
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1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATUS I
'2 3
CORRECTIVE ACTION WII.LBE IMPLEMENTEDAS NECESSARY WILLAWAITHUMANFACTOR EVALUATIONBEFORE DECIDINO ON ACTION WILLNOT BE IMPLEMENTED DISCREPANCY (DESCRIPI'ION)
PPM 5.3.1:
Decision blocks use the word "area" when referring to Table 1, while Table I was labelled using the word "room" (relative to locations within the Reactor Building).
PPM 5.5.1:
Ifthe entire procedure is performed, the step sequence of steps 1, 2, 3, 4, and 5 requires the operator to alternate back'and forth between div 1 and div 2 panels.
(PPM did not fullymeet W.G.
requirements.)
PPM 5.5.1:
The PPM specified kelay numbers in steps 1, 2, 3, 4, and 5 and did not use noun names for relays.
PPM 5.5.3:
Fire lockers near hydrant and FP-HT-1F were in poor condition.
PPM 5.5.3:
Gate valve installation not specified in procedure.
PPM 5.5.3:
PPM does not contain a note or caution concerning adverse conditions prior to the step which require opening the T.B.
rollup door.
'lVRITER'S GUIDE VERIF.
ADMIN VERIF.
TECII.
VALIDATION DATE.
STATUS COMMENTS Proposed PPM mark-up complete.
PPM is correct as written.
Rational for step sequence was explained during inspection.
Corrective Action complete.
New fir'e lockers installed.
Added during PQC review but missed in retyping prior to issuance.
The change is complete.
Corrective action comp! ete.
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1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATUS I 2
3 CORRECTIVE ACTION WILLBE IMPLEMENTEDAS NECESSARY WILLAWAITHUMANFACTOR EVALUATIONBEFORE DECIDING ON ACTION WILLNOT BE IMPLEMENTED DISCREPANCY (DESCRIPTION)
PPM 5.5.3:
Prestaged dedicated tools were not available to perform step 2 which required closure of 3 condensate system valves.
PPM 5.5.5:
Step 2 in this procedure is different in format from identical steps 1, 2, 3, and 4 of PPM 5.5.1.
PPM 5.5.8:
Hose adapter used to connect hose to SLC flange not specified as a required tool in the PPM.
PPM 5.5.8:
PPM specified the use and prestaging of crescent wrenches vice box-end or socket drive wrenches.
WRITER' GUIDE VERIF.
ADMIN VERIF.
TECH.
VALIDATION CLOSURE DATE CohIP.
STATUS COhIh ENTS These valves must be closed manually, via their handwheels.
This procedure would only be performed during times where no air or electrical power are available for power assisted valve operators.
Steps are not identical.
Different format used due to differing scope requirements.
Inspection report error.
This adapter is permanently connected to one end of the hose and was therefore not listed separately.
Proposed PPM mark-up complete.
PPM 5.5.8:
PPM uses valve numbers without a noun descriptor.
PPM 5.5.8:
Routing of several hundred feet of rubber hose from the SLC relief valves to RCIC pump suction would be difflcu!tfor one operator.
Consider installing a hose reel or additional operators.
I Proposed PPM mark-up complete.
TER submitted requesting hose reel installation.
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1990 EOP INSPECTION REPORT ANALYSIS COSIPLETION STATUS I 2
2 CORRECTIVE ACTtON WILLBE MPLEMENTED AS NECESSARY WILLAWAITHUhfhN FACTOR EYALUATIONBEFORE DECIDING ON ACTION WILLNOT BE B IPLESIENTED DISCREPANCY (DESCRIPTION)
PPM 5.5.9:
Dyno tape label found on RWCU-Mx-5.
"Dyno tape is temporary and uncontrolled and should not be found on any plant equipment.
PPM 5.5.9:
Note preceding step 16 appears to be inappropriate at this point in the sequence of actions.
PPM 5.5.9:
Step 14.g contains a wording error (i.e.,
should use "ensure" vice "confirm").
PPM 5.5.9:
Steps I3.e and II.e are similar but use slightly different format.
PPM 5.5.9:
The word FILTER is shown in all capital letters (step 10.e) indicating it is exact plant labeling when in fact it should read "LOWFLOW RESET VESSEL A."
PPM 5.5.9:
Two different terms used to refer to the same panel.
PPM 5.5.9:
Valve operators for manual RWCU valves listed is step ll.b are on the floor at the valves, however; they are not dedicated for EOP/ESP use.
PPM 5.5.11:
PPM includes 8 note prior to step 2 that attributes the human cognitivc process of thinking to the RSCS.
N RITER'S GUIDE VERIF.
ADiWGN VERIF.
TECII.
VALIDATIOiN DATE STATUS COil&KNTS Not an EOP issue.
This note is in the correct location.
Proposed PPM mark-up complete.
Proposed PPM mark-up complete.
This is an error in the inspection report.
Proposed PPM mark-up complete.
Valve operators are used for normal operations.
Proposed PPM mark-up complete.
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1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATUS I 2
3 CORRECTIVE ACTION WILLBE IMPLEMENTED AS NECESSARY WILLAWAITHUMANFACTOR EVALUATIONBEFORE DECIDING ON ACTION WILLNOT BE IMPLEMENTED DISCREPANCY (DESCRIPTION)
PPM 5.5. 17: Panel H13-622 had penciled terminal layout markings on the inside of the panel door.
PPM 5.5.17:
Step Sa is not clear on instruction to flood containment.
PPM 5.5.17:
Steps 2 and 3 are "ifstatements" that require the Shift Manager and CRS to concurrently recheck entry conditions while executing all other EOP flowcharts.
These "ifstatements" should be on the flowcharts.
PPM 5.5.18:
Step 3 should be integrated into step 4 as they are not separate actions.
PPM 5.5.19: A white tag (dated 1983) was attached to RHR-V-67 noting the valve had a packing leak.
>VRITER'S GUIDE VERIF.
ADMIN VERIF.
TECH.
VALIDATION CLOSURE DATE COMP.
STATUS COMMENTS Not an EOP issue. Markings had nothing to do with PPM 5.5.17.
Markings have been removed.
Existing guidance is clear and adequate.
Separate overrides exist for the conditions of the "ifstatements" in the appropriate flowcharted EOP's.
These "ifstatements" are relative to PPM 5.5.17 specifically.
PPM is correct as written.
Corrective action complete.
Old outdated tag was removed.
Not an BOP issue.-
PPM 5.5. 19: Specified a 15 ft. step ladder to reach a valve required to be operated.
The prestaged ladder was only 8 ft.
PPM 5.5.19:
Steps 4h and 4i spccificd valve numbers without using noun names.
A 10 ft. ladder was immediately installed and PPM 5.5.19 will be changed to specify a 10 ft. ladder.
Proposed PPM mark-up complete.
Proposed PPM mark-up complctc.
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1990 EOP INSPECTION REPORT ANALYSIS COMPLETION STATUS I
2 2
CORRECTIVE ACTION WILLBE IMPLEMENTED AS NECESSARY WILLAWAITHUMAN FACTOR EVALUATIONBEFORE DECIDING ON ACTION WILLNOT BE IMPLEMENTED DISCREPANCY (DESCRIPTION)
PPM 5.6,1:
(SBO), lists no tools or equipment necessary to perform it.
PPM 5.6.1:
Dyno tape is used to label the open/close lights for PI-VX-262, 263, 264, and 265 as weu as E-CP-DG-RP/3 (D/G droop switch).
PPM 5.6.1:
Step 12b should be evaluated and revised as it incorrectly isolates RCIC high exhaust pressure isolation switches.
PPM 5.6.1:
Step 5. 13 fails to indicate which HPCS and RCIC room doors to open.
(Inadequate verification.)
PPM 5.6.1:
Step 5.19 requires operator to move upstairs to read hydrogen pressure.
Operator believed that hc could also read this information on a local gauge without moving upstairs.
PPM 5.6.1:
Step 5.22 contains a second action that should be located after 5.23.
(Inadequate verification.)
WRITER' GUIDE VERIF.
ADMIN VERIF.
TECH.
VALIDATION CLOSURE DATE COMP.
STATUS COMMENTS While not listed in the PPM, these too!s (2 crescent wrenches) were and are prestaged.
PPM willbe changed.
Proposed PPM mark-up complete.
Label request issued.
Willbe installed.
RFTS submitted to determine necessity of cap removal.
Existing direction is prescriptive and very adequate.
Operator was incorrect.
This pressure cannot be read without moving upstairs.
PPM is correct as written.
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1990 EOP INSPECTION REPORT ANALYSIS CohtPLETION STATUS I 2
2 CORRECTIVE ACTION WILLBE IMPLEMENTEDAS NECESSARY WILLAWAITHUMANFACTOR EVALUATIONBEFORE DECIDING ON ACTION WILLNOT BE IMPLEMENTED DISCREPANCY (DESCRIPTION)
The writers guide allows the use of qualifiers (i.e., except).
'Ihe position of the qualifier clause may cause it to be read after the action is begun.
The writers guide design for "continuation condition" steps splits the condition form in contingent action. The condition is attached to the previous action symbol, suggesting a relationship that may not exist.
The writers guide directions on referencing and branching is unclear.
Definitions of referencing and branching provides no clear distinction.
IVRITER'S GUIDE x
VERIF.
ADMIN VERIF.
TECH.
VALIDATION DATE
~
COMP.
STATUS COMMEN'IS Only IBII;qualifier is allowed to be used-(singular).
Human factors willlook into this.
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January 30't. 1991 RV/jk
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LMILLER 1/zr/91 1/~91 YES /
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DOCKETNO.
50-397 4
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 January 3, 1991 DISTRIBUTION Docket File PD5 Reading DFoster PEng Regulatory Publications Branch MEMORANDUMFOR:
Division of Freedom of Inforinatlon and Publications Services Office of Administration and Resources Management FROM:
SULIECT:
Office of Nuclear Reactor Regulation I
ENVIRONMENTAL ASSESSMENT OF RE(UESTED EXEMPTION FROM 10 CFR 55.45(b)
(2)(ifi) FILING DEADLINE AND 10 CFR 55.45(b)(2)(iv)
One signed original of the Federal Register Notice Identified below Is enclosed for your transmittal to the Office of the Federal Register for publication. Additional conformed copies (
5
) of the Notice are enclosed for your use.
Notice of Receipt of Application for Construction Permit(s) and Operating License(s).
Notice of Receipt of Partial Application for Construction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.
Notice of Consideration of Issuance of Amendment to Facility Operating License. (Call with day insert date).
I Notice of Receipt of Application for Faclllfy License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.
Notice of Availabilityof NRC Draft/Final Environmental Statement.
Notice of Limited Work Authorization.
Notice of Availabilityof Safety Evaluation Report.
Notice of Issuance of Construction Permit(s).
Notice of issuance of Facility Operating License(s) or Amendment(s).
. Clod..
Exemption.
I Notice of Granting Exemption.
K Environmental Assessment.
Notice of Preparation of Environmental Assessment.
Receipt of Petition for Director's Decision Under 10 CFR 2.206.
Issuance of Final Director's Decision Under 10 CFR 2.206.
Other.
Enclosure:
As stated contact: Patricia L. Eng X21361 tgg 1 LA/PD5/ RP3
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DOCKET NO. 50-397 r
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 September 5, 1990 DISTRIBUTION
=-Docket:File PDV R/f DFoster PEng Regulatory Publications Branch MEMORANDUMFOR:
Division of Freedom of Information and Publications Services Office of Administration and Resources Management FROM:
SUBJECT:
ONce of Nuclear Reactor Regulation MASHIhGTON NUCLEAR PLANT UNIT 2 - DENIAL OF NENDi<IENT REQUEST (TAC NO. 7538O)
One signed original of the Federal Register Notice Identified below is enclosed for your transmittal to the Office of the Federal Register for publication. Additional conformed copies (
5
) of the Notice are enclosed for your use.
Notice of Receipt of Application for Construction Permit(s) and Operating License(s).
Notice of Receipt of Partial Application for Construction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.
Notice of Consideration of Issuance of Amendment to Facility Operating License. (Call with
.day Insert date).
Notice of Receipt of Application for Facility License(s); Notice of Availability of. Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.
Notice of Availabilityof NRC Draft/Final Environmental Statement.
Notice of Limited Work Authorliation.
Notice of Availabilityof Safety Evaluation Report.
Notice of Issuance of Construction Permit(s).
Notice of Issuance of Facility Operating License(s) or Amendment(s).
Order.
Exemption.
Notice of Granting Exemption.
Environmental Assessment.
Notice of Preparation of Environmental Assessment.
Receipt of Petition for Director's Decision Under 10 CFR 2.206.
Issuance of Final Director's Decision Under 10 CFR 2.206.
Kl Other:
Oppor tunity for Hearing
Enclosure:
As stated
Contact:
P. Eng 492-1361 DRSP:PDVP DFostp~
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DocKH NO.
50-397 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 September 5,
1990 DISTRIBUTION Docket File PD5 Reading File DFoster PEng Regulatory Publications Branch MEMORANDUMFOR:
Division of Freedom of Information and Publications Services Office of Administration and Resources Management FROM:
ONce of Nudear Reactor Regulation SULIECT:
NUCLEAR PLANT NO. 2:
tlITHDRAMALOF AN NIENDI'lENT REQUEST REqUARDING ACCIDENT MONITORING INSTRUMENTATION (TAC NO. 76673)
One signed original of the Federal Register Notice Identified below ls enclosed for your transmittal to the Office of the Federal Register for publication. Additional conformed copies (
5
) of the Notice are enclosed for your use.
Notice of Receipt of Application for Construction Permit(s) and Operating License(s).
0 Notice of Receipt of partial Application for Construction Permit(s) and Facility License(s): Time,for Submission of Views on Antitrust,Matters.
G Notice of Consideration of Issuance of Amendment to Facility Operating License. (Call with
.day Insert date).
Notice of Receipt of Application for Facility License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.
Notice of Availabilityof NRC OraftiFlnal Environmental Statement.
Notice of Limited Work Authorization.
NotIce of Availabilityof Safety Evaluation Report.
Notice of Issuance of Construction Permit(s).
Notice of issuance of Facility Operating License(s) or Amendment(s).
Order.
Exemption.
Notice of Granting Exemption.
0 Environmental Assessment.
Notice of Preparation of Environmental Assessment.
Receipt of Petition for Director's Decision Under 30 CFR 2.206.
V Issuance of Final Director's Decision Under 10 CFR 2.206.
[g o,h,Notice of Mithdrawa1 of Amendment to Facilit 0 eratin License DRSP/LA/
5 DFoste ogl/PI9 OFFICE ouRNAMa~
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NRC FORM sIe IIO/eoI NRCM 0240 I
'nclosure:
As stated contact: Patricia L. Eng Phone:
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DOCKET NO., 50-397 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 August 27, 1990 DISTRIBUTION Docket File PD5 Reading DFoster
, 'PEng Regulatory Publications Branch MEMORANDUMFOR:
Division of Freedom of Information and Publications Services Office of Administration and Resources Management FROM:
Office of Nuclear Reactor Regulation SULIECT:
WASHINGTON NUCLEAR PLANT NO. 2:
lWITHDRAWAL OF AN AMENDMENT REQUEST REGARDING ACCIDENT HONITORING INSTRUMENTATION (TAC NO. 76168)
CENSE One signed original of the Federaf Register Notice identified below is enclosed for your transmittal to the Office of the Federal Register for publication. Additional conformed copies (
5
) of the Notice are enclosed for your use.
Notice of Receipt of Application foiConstruction Permit(s) and Operating License(s).
Notice of Receipt of Partial Application for Construction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.
Notice of Consideration of Issuance of Amendment to Facility Operating License. (Call with day Insert date).
Notice of Receipt of Application for Facility License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.
Notice of Availabilityof NRC Draft/Final Environmental Statement.
Notice of Limited Work Authorization.
G Notice of Availabilityof Safety Evaluation Report.
Notice of Issuance of Construction Permit(s).
L Notice of fssuance of Facility Operating License(s) or Amendment(s).
Order.
Exemption.
Notice of Granting Exemption.
Environmental Assessment.
Notice of Preparation of Environmental Assessment.
Receipt of Petition for Director's Decision Under 10 CFR 2.206.
Issuance of Final Director's Decision Under 10 CFR 2.206.
El Other.
Enclosure:
,As stated contact:
Patricia L
Eng Phone:
OSSICEW SURNAME OATE g gd/gg NRc FoRM 3re llo/eo) NRcM 0240 OFFICIAL RECORD COPY
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