IR 05000423/1989017
| ML19332E587 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 11/13/1989 |
| From: | Anderson C, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19332E585 | List: |
| References | |
| 50-423-89-17, NUDOCS 8912070414 | |
| Download: ML19332E587 (8) | |
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....: License"No.e.NPF-49:
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- (Licensee:; Northeast"NUc.. lea r: Energy; Company
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y s ',' ;Fa'cility.)Name: l Millstone-NuclearPowerStation Unit'3 j
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IInspection(At: LBedin;'. Connecticut:
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? Inspection C'nductedi September 18-22, 1989'
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IInspectbr: ' -R.Paolpo,4SeniorReactorEngineer,-ORS /EB date.
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LApproved by:
.C. J ;Ahderson, Chief, Plant = System Section'
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y Inspectiont Summary:
Routine Announced Inspection on-September 18-22, 1989 M
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! Areas" Inspected:
The-inspection ~ covered:
1)Iengineering support activities j
cfor the Millstone-3 operating plant..This' included corporate. engineering,.
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- plant engineering, field
- engineering and related quality -assurance 'activitiesn
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?2):close out~of:previously~ identified open EQ issues.
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LResults: -No deficiencies were ~ identified, i
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5PDR ADOCK 05000423
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DETAILS
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k, 1;o:-- Persons' Contacted.
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-Northeast Utility Service Company (NUSCO)'
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- J.FS./ Harris, Engineering Supervisor'(MS-3)
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.W.' J. Hayes, Engineering Technician (EQ)L
- Gi?L. Johnson, Director,; Generation Engineering & Design
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- R.1G. Joshi,. Licensing Engineer
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- B. S. Kaufman,3 Supervisor. Assessment and Staf.f Services
- E. ~J. Laware, Senior. Engineer Technologist
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p T. W :Lyons, Assistant Engineering _ Supervisor (ISI)
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i.- K2 Maier,: Scientist Coordinator-(NE0 Procedures).
W-DFT. McDaniel,EAssistant Engineering Supervisor (Reactor
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Engineering):
- E.. F.7 Murphy, Supervisor -(Cost & Schedule)
. R. P. Necci,sSystems-Manager Generation Mechanical Engineering
- D.-0.'Nordquist, Director Quality Service
VC Papadopo_li,: Senior Engineer (QSD):
R. S. Peterson, Senior Engineer ~(EQ)
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. W. V. ~ Richter,- Assistant Engineering Supervisor _(Electricai/I&C) -
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- A R.1Roby, Systems Manager Generation Electrical Engineering
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- T. A. :Shaffer, Manager I&C Engineering.
- B.-:.A.:Tuthill, Supervisor Qualification Engineering
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^ *G; :P. Vant:Noordennen, Supervisor Nuclear Licensing i
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1P.:D.iWatson, Supervisor General _. Nuclear Training H. ;G.1Woodbury, Engineer (NE0 Procedures) '
- R. J.LYoung,' Supervisor Generation Electrical Engineering
- denotes those personnel present'at exit meeting-of September:'22~,
1989.
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2.0 L:0b'jectives The-objective of the_ inspection was to assess the adequacy of the (licensee's program for engineering support to plant operations including Emodification design and configuration control, interfaces with other W
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. internal and external organizations, management support,' staffing levels
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and' experience,-training, and licensee response to NRC requirements and-requests.
3' 0 L'icensee Commitments
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The licensee's commitments including those to specific codes and standards are contained in the.FSAR and Technical Specifications.
g Procedures reviewed during-this inspection were noted to reference applicable codes and standards, s
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L 4.0 Organization
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The manageme'nt and technical support organization consists of personnel from Northeast Utility Service Company (NUSCO) and Northeast Nuclear Energy Company (NNECo). NUSCO is responsible for the' Northeast Utility
'(NU) headquarters support activities and NNECo is responsible'for the onsite preoperational and operational activities.
These activities are
. coordinated between the organizations with each providing review and
concurrence as appropriate to the organization having the lead responsibility for the activity.
The Nuclear Engineering and Operations (NE&O) group is responsible.for all NU electric generation facility projects; for nuclear, mechanical,
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civil,- electrical and environmental engineering support;. and for nuclear operations at all generating facilities.
The Generation Engineering and Design (GE&D) department through its Generation Mechanical Engineering, Generation Electrical Engineering and Generation Engineering Design groups provides engineering support to the operating plants for Reactor Plant Systems, Balance of Plant Systems, Component Engineering, I&C/
l Electrical, Special and Program Studies and Qualification Engineering.
Within the GE&D. decision-m:Fing-authority is governed by established procedures, principally ti NE&O Procedures. These procedures specify the lines of authority for review and ultimate approval of all safety-related as well as non-safety-related engineering documentation.
All engineering and design documentation requires the approval of the responsible supervisor, as a minimum and, according to the specific document, further approvals in the management chain may be required.
The inspector interviewed supervisors and engineers involved with both onsite and offsite engineering activities.
Plant modification packages were sampled to establish completeness and conformance to engineering procedures.
Packages reviewed include:.'1) PDCR No. MP3-88-014 Rev. O pertaining to Litton-Veam connector replacement, 2) PDCR No. MP3-89-010 Rev. O pertaining to Phase II annunciator replacement and, 3) PDCR No.
MP3-89-010 Rev. O pertaining to the electrical protective relay scheme.
The packages were observed to be complete and in conformance with the controlling procedures. Good interactions between the various responsible engineering groups was observed.
The inspector concluded that the engineering organization is sufficient in structure and depth to provide engineering resolutions to plant problems.
5.0 Staffing The professional staff within GE&D is an experienced staff with an average of 14.5 years of experience with 6-9 years of experience within Northeast Utility. All engineers within GE&D possess the appropriate engineering degree for their discipline.
Staffing level is adequate.
Potential contract personnel are required to submit a resume of their qualifications and experience.
Contract personnel are selected based upon I
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)their resumes-:andLinterviews with theLintended supervisor. Contractor (
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LactiVities~are controlled by licensee supervisors and where. appropriate
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e supported by assigned full" time staff.
Contractor: activity is considered
^1 Lalpart 'of the overall-engineering activity land;is: subject to the saw; audits.
land acceptanceLcriteriaithat govern all GE&D personnel
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. I'n: summary,f thi in'spector. ' determined that; the engineering ' experience arid F-staffing 11eveltare sufficient'and are not~limiti.ng factors in providing.
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tthe' plant; site with' engineering ~ support to accomplish ~ plant. evaluations
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. Communication-
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?The procedures-which cover communication with' the plant -are: contained in
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the NE&O Procedures Manual..They are the, Project Assignment Procedure, Project Description: Procedure, Design and Interface Reviews and Plant
' Design' Change; Record Procedures.. In addition t';
licensee holds several:
-formal meetings;between engineering and plant.se '. Once a. month there
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jis an engineering ~ meeting which includes a discussion of current engineer-
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Ling and design. topics.- There is also a monthly project status meeting 1between plant and corporate personnel to discuss project and level of a
effortistatus'. ; Quality Assurance and Quality Control personnel: attend
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daily-station morning!and daily unittmeetings'
These personnel also meet.
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- withithe plant;and engineering personnel on an informal basis frequently.
Formal' communication is: established via a copy-of-quality:related project assignments.'nd project descriptions.
For, an individual project, there a
is a projectL" kick-of f." meeting attended by project participants. This-
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continuous < interaction between engineering and the plant site;is important for -ef fective communication.
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,7.01 Workload-
Project work load is controlled in accordance with NE&O Procedure No. 3.04, Project Assignments, from a variety of sources, by plant personnel, the engin'eering organization'or the user. Work that does not meet the
- criteria ;in NE0-3,04 is ' typically considered level-of-ef fort and is
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Work load priorities are first established through Generation Engineering and Construction (GE&C) staff interaction with plant management. The process of outlining and prioritizing the project work load for future q
years involves year-round discussions, but is typically most visible i
during the summer months when budgets are submitted.
Overall, plant management has the responsibility for prioritics affecting the plants.
Engineering and-design supervision have the responsibility for
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accomplishing the work within these priorities considering available
,W resources and priority changes as they may occur.
Currently there are
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approximately 60 engineering / design / construction projects, 45 engineering
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studies and 100 level-of-ef fort assignments planned for the 1990 budget
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yearq Of.these-Millstone 3 has 16 projects, 7 studies"and 39
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. level-of-effort 1 assignments.
Projects are tracked by distributed
reports, routed documentation, and regularly scheduled status meetings 1
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through thetproject engineer,-cost engineer and planning l engineer in
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each project /4 Distributed reports include detailed Critical Path Metho~di g'
(CPM) projects; schedules showi_ng individual department activ' i. ties and =
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- their interrelationships, engineering matrices. summarizing.the-critical!
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- m11estones of i.ndividual projects, budget status reports, and con ~struction
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f program; reports,
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- 8,0l ManagementtSupport-
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The organizational structure and the number of employees within the
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(engineering organization;is; established Jointly by functional' management
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1tional Control'. Manpower levels'within the established' limits'are: main-s-
- tained by the-functional organization. Manpower levels are scheduled to
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' remain as;is-through 1990,
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.The Northeast Utilities Capital Program covering Northeast Utilities
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System Companies'is controlled by a Project Evaluation Review Committee-(PERC) madeLup)of officers and management personnel from engineering and budget management.
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29,0L Quality Assurance Quality Assurance / Quality Control (QA/QC) is performed through audits, surveillan'ces,' inspections and in process verifications. ~ Audits are performed based on a schedule that.is issued:at the beginning of the year and periodically revised. QA/QC is directly involved in the review of-work orders and nonconformances in accordance with procedures ACP-QA-2.02C and'NEO-325/ACP-QA-5.01.
Surveillances are performed on a random basis in accordance with ACP-QA-9.07C. Normally,-audits.are addressed in a timely manner with dispositions'being thorough and. corrective actions being implemented within.an acceptable time frame. Trending is performed on all'
. Quality Service -Department (QSD) findings-whether they are audits or'
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surveillances.
Results are published to the director of QSD with an f
! executive' summary zissued to VP's and station and unit superintendents-.
s QA/QC. interfaces with engineerin'g through audits and surveillances of engineering activities'and design modifications.
On large project assign-
ments, QA/QC assigns dedicated personnel to cover only that project, u
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QA/QC does.not perform an' in-line review of. engineering output except for
'QA procurement-specifications and purchase orders to ensure proper QA
, requirements are = specified.
10.0 Training
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The Technical Staff and Manager (TSM) training program consists of three groups divided into indoctrination, initial and continuing training courses.
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Its purpose is to provide the target population with knowledge of plant
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, design and operations.
Indoctrination training courses are completed by new' personnel within-the.first twelve' months of entering the TSM program.
. Initial training courses provide more detailed information and are completed within two years of entering the program.
The continuing training courses contain specific training presented quarterly for plant personnel.
This training includes presentations on current plant and-industry events, significant procedure changes, plant modifications and periodic reviews of selected tapes.
-11.0 Status of Previously Identified Open EQ Issues
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(Closed) Unresolved item _85-34-03 pertaining to qualification status of the Kaman containment High Range Radiation Monitors (HRRM).
The licensee has replaced the two Kaman HRRM'with qualified General Atomics HRRM units.
The licensee indicated that both Kaman HRRMs will remain as installed, however no credit is being taken for-their use.
In addition, both units have been dropped from the EQ master.
list.
This item is closed.
,(Close,d) Unresolved Item 88-04-01 pertaining to the adequacy of
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procedural controls for determining the basis for issuance of JCO's (Justification for Continued Operations),
Procedure No. NEO 2.25 has been. revised to clarify the licensee's position on issuing'JCO's.
In addition the licensee has taken the initiative to develop a new procedure which establishes the ground rules for JCO's. A draft copy, dated August 8, 1989 was being circulated for review.
This item is closed.
{ Closed)UnresolvedItem 88-04-02 pertaining to the qualification
status of the Containment High Range Radiation Monitors (HRRM).
The licensee maintains that memorandum No. 1103866 incorrectly suggested that the HRRM's were being qualified while in use, This finding was addressed in NUSCO memo GSP-87-387 of October 29, 1987.
The conclusion that the HRRM's were qualified is stated in NNECO's letter to the NRC, No. B12671, dated September 30, 1987.
The issue of insulation resistance (IR) was raised by Northeast Utilities in a letter, GSP-86-570, to the vendor on October 14, 1986.
The IR concerns pertained to the factor of 2 accuracy of the HRRM systems.
Subsequently the vendor issued a Part 21 notification of methodology to evaluate the Rockbestos cable used in the installed HRRM's for Millstone 3.
The calculated overall loop accuracy equated to a maximum error of <1R/hr. which is within the accuracy
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guidelines recommended in Regulatory Guide 1.97.
The licensee has completed a Reportability Evaluation #87-2 which indicates the HRRM meets the accuracy statement in RG 1.97.
This item is technically cloced.
(Closed)-UnresolvedItem 88-04-03 pertaining to the potential error
in.the HRRM which could lead to the detector going off-scale at the low end and the green operate light going-off. The licensee.has revised the operations procedure OP-3362, " Radiation Monitor System Display and Control System" to address this concern.
The revision
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was completed May 10, 1988.
In addition, the licensee has included this HRRM alarm response into the Control Room Operator Requalifica-tion Training Program and notified all control room operators of the potential problem.
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This item is closed.
~(Closed)UnresolvedItem 88-04-04 pertaining to the adequacy of the
. licensee's review and response to Information Notice (IN) 84-68,
" Improperly Rated Field Wiring to Solenoid Valves" and formal documentation of calculations considering the impact on aging calculations of self-heating.
The licensee's review and evaluation of IN-84-68 was documented in a letter, NES-38528, dated May 15, 1985.
It stated, in part, that:
" Solenoid Valves manufactured by Target Rock are not. impacted."
Target Rock has performed a test showing that the internal tempera-ture rise is less than the rating of the field wiring (Reference Target Rock Report TRP-4207).
This letter has been added to the EQ file No. 654.
In addition, formal documentation of aging calcula-tions considering self-heating were added to the EQ file to complete the documentation.
This item is closed.
-(Closed) Violation No.- 88-04-05 pertaining to the lack of IR measure-
ments during LOCA transient conditio'ns in testing the Litton-Veam connector.
The licensee determined that the deficiency related only to connectors used in instrument loop applications subject to a LOCA environment.
Twenty-seven Litton Veam connectors were identified for replacement.
Three were replaced with qualified Conax feedthrough type ECSA connectors and twenty-four were replaced with qualified Rosemount Model 353C connectors. Work was completed during the 1989 outage.
This item is close myy=p7 mm%g~e w K, yv
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[(Closed)PotentialViol'ationNo.88-0O06pertainingtoexcessive?
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(Raychem. splice: bends (.less.than;5x' recommended.by Raychem).and-T, %
l splice 1sealslengths less thanithefqualifiedJ2.inchTsea1Llength.
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f*,4 Wheilicensee.:providhd'information;(CECO.;ReportMissuedMarch-1987.)?
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? based'onitestcconducted bycother utility groups'which qualify' splice':
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ibends' of' 2x' cable (diameter and splice' sea)clengths:ofl h-inch; gin.
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.additionk specific'Raychem-training was1provided to ensure thatl
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Th' Marcht 1987/ data wasiadded to: thei,,
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of Raychem> splices.
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if") sed)' Potential Violation-No. 88-04-07l pertaining to fai:1ure to?
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. incorporate heat: shrinks tubing: over-:the pin / conductor-interface off
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- -VAP-241l.s ! Licensee review and evaluation; determined that two-cases 1-
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- harsh environment.; Failure of these two cases.would only ha've
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1mpacted'one valveTposition indication. The four connectors-weres
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Ereplaced withinew connectors with1 heat shrink; tubing ~duringsthe'1989.
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(Thistitemisfclosed.
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- 12.0: Exit'Meetingi
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FThelinspector met with-li_censee management representativess(details paragraph 1.0) on September 22, 1989. =The. inspector summarizednthe' scope
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'During?this =inspe.ction; no. written material.was provided to-the : licensee.
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