ML20147E214
| ML20147E214 | |
| Person / Time | |
|---|---|
| Site: | 05000000 |
| Issue date: | 06/26/1981 |
| From: | Guimond R GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML17342B416 | List: |
| References | |
| FOIA-87-696 IEB-79-01B, IEB-79-1B, NUDOCS 8801210042 | |
| Download: ML20147E214 (132) | |
Text
MUClear AUDIT REPORT l
Pace 1 of 10 March 26,27,30,31 Audit dates (s)
April 1, 1981 Audit No.
0-TMI-81-02 Facility Technical Functions (Home Office)
Reference P.O.
N/A Rev.
N/A Documents:
SEE DEPORT Rev.
Activity item (s)
IE Bulletin 79-01B Attendees Name Title Representing R. J. Guimond (1)(3)(4)
Audit Team Leader GPU T. Iacovides (1)(3) (4)
Auditor GPU (1) Attending Pre-Audit Conference (4) Attending Official Post-Audit (2) Persons contacted during audit Conference (3) Attending Preliminary Post-Audit Conference PURPOSE To assess the Technical Function here office activities for compliance to the requirements of IE Sulletin 79-013.
SUMMATION SEE ATTACHED REPORT (Pages 1-1]).
COMPLETION Ix 1 cion. out r.quir.d ror I 11 I Non conform nce..T.rg.t O.i. _Per Audit Findincs Signed:
Am k
g/
Avcit TSam Leacer e,ncurseo ey:
Audit Approvec by:
Y.
or Orector. QA ager. QA Program C -
l l Reviewed response. Will check implementation by:
2 Re Audit C Follow-up CA O*'
{
l Audit Satisfactorily completed. Closed QA c.,e AOQQO412 6 si 8801210042 880106 l
Pago 2 of 10 Audit 0-TMI-81-02 PERSONS CONTACTED G. R. Braulke (1)(2)(3)
Electrical Engineer GPU I
R. J. Chisolm (1)(3)
Elec. Pwr. & Instrumentation Manager GPU D. K. Croneberger (1)(2)(3)(4) Director Engineering & Design CPU I.
Feinberg (2)(3)
Project Engineer GPU J.
Flynn (4)
Eng. Procedures & Standards CPU i
E.
Gately (2)
Admin. Clerk (Eng. Files)
GPU N. C. Kasanas (1)(4)
Director Quality Assurance GPU F. G. Maus (3)(4)
Supervisor & Environmental Qualification GPU P. B. Magitz (1)(3)(4)
Corp. QA Audit Supervisor GPU Y.
Nagai (3)
Licensing GPU D. G. Slear (2)
TMI-l Project Engineering Manager GPU M. J. Stromberg (1)(3)(4)
Manager QA Program Development & Audit GPU T. E. Tipton (3)*
Director, Licensing & Regulatory Affairs GPU 4
NOTE:
(1) Attending Pre-Audit Conference (2) Persons Contacted During Audit (3) Attending Preliminary Post-Audit Conference (4) Attending Official Post-Audit Conference
- Part Time l'
REFERENCE DOCUMENTS
- 1) D; dng C-302-081, Rev. 19, Emergency Feedwater
- 2) D: -.ng C-302-032, Rev. 2, Main Steam and Feedwater
- 3) Drawing C-302-650, Rev. 18, Reactor Coolant System
- 4) Drawing C-302-610, Rev. 27, Nuclear Services Closed Cooling Water
- 5) IE Bulletin 79-01B, plus Supplement 1, 2, and 3 i
- 6) Engineering Standards (through Amendment 27)
- 7) Engineering Procedure (through Amendment 27)
- 8) Operational Quality Assurance Plan for TMI-1, Rev. 8 i
- 9) Commission order, dated 5/23/80
- 10) NRC Order, dated 10/24/80
- 11) NUREG 0588 Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment i
s 1
N t
I l
Pcg3 3 of 10 Audit 0-TMI-81-02
SUMMARY
(
On December 22, a980, Mr. R. F. Wilson made a request to the QA Audit Section that an audit be performed to verify that procedures were followed on equipment qualification and there is objective evidence that each qualification report had been reviewed and approved by Engineering. The audit included all the requirements of IE Bulletin 79-OlB. The results of the Technical Function Home Office audit (excluding the Spare Parts Program, which will be covered in a separate audit) resulted in the issuance of elevan (11) findings.
Deficiencies found in completeness and acceptability of the Master List are as follows:
(1) No objective evidence that the GPU Engineering Standards nor Engineering Procedures were followed for the establishment of the Master List and qualification documentation file.
(2) No docu=ented evidenea in Central File of a schedule (s) to assure the equipment which have been identified as being susceptible to significant degradation due to thermal and radiation aging are replaced as necessary.
(3) Existing Engineering procedures do not provide appropriate guidance nor has there becn a program intriated to meet the r iuirement of updating and maintaining current the 'entral File as equipment is replaced, further tested, or otherwise further qualified.
(4) "Master List" does not address all equipment that is required to function under postulated accident conditions; also, lacks qualification documenta-tion in Central File for these components, f
(5) Some analyses of environmental qualifications are not sufficiently detailed.
(6) No mechanism demonstrated to assure that all the requirements of the bulletin is being met.
(7) No standard approach regarding file organization and content.
Consequently, the decision of what belongs in the Central File is left largely to the Administrative Clerk (Engineering File Room).
The conclusion drawn from the audit is that =anagement direction to correlate the efforts needed to meet all the requirements of the bulletin is lacking.
DETAILED DISCUSSION QA Walk Through On Reactor Protection and Engineering Feedwater Systems A site inspection was performed by Mr. C. Adams (TMI Audit Section) and the writer on February 11-12, 1981.
The inspection was to verify the adequacy and completeness of the information given in the Component Evaluation Worksheets (CES) for the Emergency Feedwater and Reactor Protection Systems.
Checklists were developed from the CES's for both systems.
1 l
Page 4 of 10 Audit 0-TMI-81-02 The first effort of the inspection required a verification of the electrical equipment associated with these systems.
The following drawings were reviewed to assure that the Master List had not omitted equipment that was required to function.
1)
C-302-081, Rev.'19, Emergency Feedwater 2)
C-302-032, Rev. 2 Main Steam and Feedwater 3)
C-302-650, Rev. 18, Reactor Coolant System 4)
C-302-610, Rev. 27, Nuclear Services Closed Cooling Water Based upon information in the Master List, plus plant preliminary inspections (performed by Mr. C. Adams) and the review of the above drawings, the auditors concluded that the Master List was correct and acceptable with the exception of those items discussed in this report.
(See Inspection Results)
The purpose of the inspection was to verify the information given in the CES with respect to flood level (elevation), plant ID number, manufacturer's name, model number, serial number (if available) and location.
The inspection was found satisfactory except for the noted deficiencies.
(See Inspection Results)
INSPECTION RESULTS Reactor Protection System 1)
Pressure Transmitter RC3 APT 1 (Rosemount) - CES states that the serial number is 74861, the actual number is 74860.
2)
Pressure Transmitter RC3 APT 2 (Rosemount) - pressure transmitter is identified as RC3AT1023; riso, CES states that the serial number is 74860, the actual number is 74861.
3)
Pressure Transmitter RC3BPT1 and PT2 (Rosemount) - CES states that the model number is 1152, actual number on nameplate is 115-2GP9A9270010PB.
4)
Temperature Transmitter RC4A-TE2 and TE3, RC4B-TE2 and TE3 (Rosemount) -
CES s.ates that the model number is 177HW2, nameplate is missing from components, 5)
Electric Penetration Assemblies 204, 205, 313, and 314 (G.E.) - CES states that the model number if F01, actual number on nameplate data states Cat. No. 237X766G16.
Page 5 of 10 Audit 0-TMI-81-02
(
- 1) Motor EF-P2A and P2B (Westinghouse) - CES states only HP450 for model number, actual model number on nameplate is type 68F21661 Type CSP.
- 2) Control panels for EF-V-30A and 30B (Hoffman enclosure) - no CES for the four (4) devices (G.E. type K06RS20AP10B2) and a Stanwick terminal board installed in each panel.
See Audit Finding No. 4.
- 3) Differential Pressure Transmitter EF-FIS-77, 78, and 79 (Barton) - CES states that the model number is 277, model number is not listed on nameplate.
- 4) Differential Pressure Transmitter EF-FIS-78 (Barton) - CES states that the serial number is 277-1789, actual serial number on nameplate is 277A-1791.
- 5) Differential Pressure Transmitter EF-FIS-79 (Barton) - CES states that the serial number is 277-1789, actual serial number en nameplate is 277A-1790.
- 6) Motor Operators EF-V-4 and 5 (Limitorque) - actual installation in plant does not agree with drawing C-302-610 (they are reversed).
- 7) Motor Operator EF-V-4 (limitorque) - CES states that the serial number is 94543A, actual serial number on nameplate is 94544A.
7
- 8) Motor Operator EF-V-5 (Limitorque) - CES states that the serial number is 94544A, actual serial number on nameplate is 94543A.
- 9) Valve Control Centers lA-ES, IB-ES, and IC-ES (ITE Could) - CES states that the model number is 9600, nameplate is missing from Control Centers.
- 10) Valve Control Cer.ter 1C-ES (ITE Gould) - CES states that the location of this component is in the Control / Building Tower, the actual location is in the Auxiliary Building.
- 11) Terminal Box T-421 (State Sliding Link) located in the Turbine Building 326' level had water in box with exces re corrosion on connections (ter=inal strip) informed Mr. C. Ripp (Elec. Foreman) Maintenance Department of the situation; he informed the inspectors that he vill have a man check and correct the problem.
Mr. I. Feinberg (CPU Project Engineer) stated that this problem vill be checked by Engineering on their walk through.
Issued Material Nonconformance Report (MNCR 0039-81).
- 12) Terminal Boxes T620, 621, and 622 - CES does not address, manufacture, model, serial number and function for a?.1 these boxes; nor is there a nameplate on the boxes.
- 13) Terminal Boxes T620, 621, and 622 - No CES in the Master List for the G.E. terminal strips installed in the boxes.
Recommend that this action be added to the Master List, s
Pess 6 of 10 Audit 0-TMI-81-02 f'
All of the above items for both systems were discussed with Mr. I. Feinberg, (Project Engineering).
Information noted during the Q.A. valk through, i.e., serial numbers, model numbers, etc., should be added to the CES's at the next revision (Rev. 5) of the Master List.
_ Audit of Master List and Qualification Documentation The primary purpose of this audit is to assess the controls on how the bulletin was handled for equipment qualification, and that there was objective evidence that each qualification report had been reviewed and approved by Engineering (GPUN). The audit was expanded to include all the requirements of the bulletin.
Checklists were developed from the bulletin (Checklist #1),
available Engineering standards and procedures (Checklist #2).
The Engineering response to the bulletin (Master List) is to identify the equipment that is required and qualified to perform its safety related function in any harsh environment that may result, to bring the plant to, and maintain the plant in, a high safe shutdown condition following the loss of coolant accident (LOCA) or a high energey line break (HELB), and also to identify equipment needed for a cold shutdown.
The Master List. identified a total of seventy-three (73) components (by model number). From this total, a random sample of ten (10) components were selected for review. The components which were selected for audit are as follows:
(
- Main Steam Tag No. PS-600; Static 0-Ring; Model No. 9N-05-RR Pressure Switch
- Core Fleod - Tag No. CT-V-1A; Limitorque; Model No. SM3-4; Motor Operator
- Reactor Building Isolation System - Tag No. SV/AHV/1A2; ASC0; Model No. LB-8316-C35M0; Type N.C.
t
- Make-up - Tag No, MU-P2C; G.E.; Model No. 5K37JG403; Pump Motor
- Make-up - Tag No. MU-V-2B; Limitorque; Model No. SMB-00 Motor Operator i
i
- Decay Heat Removal - Tag No. DH-PlA and 1B; Westinghouse; l
Model No. 350RP TR. 5010S; Pump Motor
- Decay Heat Closed Loop Cooling - Tag No. SV/DCV-19A; ASC0; j
Model No. HT8321-A7; Solenoid Valve l
- Common Equipment - Raychem Heat Shrink Tubing Model No. Themofit; l
1 States Co. Terminal Block Model No. NT; G.E. Electrical t
Pent. Assy. Model No. F01.
l P
1 1
i
Page 7 of 10 Audit 0-THI-81-02 The evaluation of the completeness and accuracy of the engineering response to the bulletin, how items were identified and qualification data gathered, and how the requirements of the bulletin were handled has res.ulted in the issuance of eleven (11) findings.
-1)
No evidence of direction for CPU review of qualification data. This concern is related to the extent of CPU review, comment, resolution of comments, approval and incorporation of vendor documents. Examples of evidence examined, which cause this concern are:
'a)
EDS Calculation 0370-025-023, Rev. O, is not properly signed and j
approved by EDS.
j b) EDS Project Instruction in Volume 1A are not signed and approved by EDS.
c) Limitorque Report No. 600198, dated 1/2/69, is not properly signed and approved by Limitorque for the motor operators.
d)
G.E. Report EPAQ-047 (qualification data for radiation) on the Electrical Penetration Assemblies Model F01 is not signed and/or approved by General Electric.
e) Cayot determine extent or depth of GPU review of Master List 46 Tames I, IA, and VI.
f) QA records and record retention requirements do not appear to have been defined for the project nor are interface controls been identified.
Issued Finding No. 1.
4 2)
IE Bulletin requires that ongoing programs should exist at the plant to review surveillance and maintenance records to assure that equipment which is exhibiting age-related degradatien will be identified and replaced as necessary. There was no documented evidence in the Central i
File of a schedule (s) to assure that equipment which has been identified as being susceptible to significant degradation due to thermal and radia-i tion aging are replaced as necessary.
i Issued Finding So. 2.
i 3)
IE Bulletin requires that complete and auditable records must be available j
and maintained at a central location and must be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
In reviewing existing GPU procedures (Engineering Standards j
and Engineering Procedures), they do not provide appropriate guidance nor is there a program initiated to meet this requirement.
4 Issued Finding No. 3.
c r
y
Page 8 of l'0 Audit 0-TMI-81-02 l
- 4) Components of the Emergency Feedwater/Feedvater System were inspected on the site walk through. The manufacturer's name and model number from the nameplate data was compared to information given in the Com-ponent Evaluation Worksheets (CES) of the Master List.
The Master List identified Control Panels, EF-V-30A and 30B, to function under a LOCA/HELB conditions, with its associated equipment. There was no objective evidence in the CES of the 4 devices (G.E. type K06RS20AP10B2 and a Standwick terminal block installed in each panel. Also lack of qualification documentation in Central File for these components.
Issued Finding No. 4 5)
IE Bulletin requires that complete and auditable records must be available for qualification; and, to be considered valid, these records should describe the qualification method in sufficient detail to verify that all the guidelines have been satisfied. Deficiencies found in completeness and acceptability are as follows:
a.
Main Steam System A review of the Component Evaluation Worksheet (CES) and backup documents for Tag No. PS-600 (Pressure Switch) Model No. 9N-05-RR revealed the following:
- EDS Calculations 0370-025-041 Rev. O, and 0370-02$-042. Rev. O, make no statement about humidity. These are Engineering Analyses for pressure and stress respectively.
CES states the calculations are the qualification data for Relative Humidity.
- FSAR, Chapter 14, is referenced as the qualification documentation for chemical spray.
- Reference 9, Enginetring and Design 17" (1971) 247-280, North Holland Publishing Co. omitted from the file.
- EDS Calculation 0370-027-0CO, 24v. O, qualification data for radiation is not clear on gaseous integrated dose (1 HR) and liquid integrated dose (1 HR). There is no indication as to which dose is applicable.
Issued Finding No. 5 b.
Make-up System A review of the Component Evaluation Worksheet (CES) and backup documentation for Tag No, MU-P2C Pump Motor and MU-V2B Motor Operator revealed the following:
s
Page 9 of 10 Audit 0-TMI-81-02 i
(-
- Tag No. MU-P2C - No backup documentation for letter dated 8/5/80 on radiation and aging.
- Tag No. MU-V2B - Chemical spray qualification is 7.67 PH (Boric Acid) which is not as severe as the specified limits 3
of Note B on CES which states Borated water of 2270 ppm Boron with NADH to raise PH approximately 9.5.
Issued Finding No. 6 S
c.
Decay Heat Removal System
- Unable to correlate References 4 and 5 on CES to qualification data in Volume IV under the Westinghouse tab for pump motors DM-P1A and 13.
- Westinghouse file (Volume IV), Page 17, is not legible.
i Issued Finding No. 7 d.
Decay Heat Closed toop Cooling A review of the Component Evaluation Worksheet (CES) and backup A7 documentation for Tag No. SV/DCV-19A Solenoid Valve HT8321-revealed the following:
- Unable to locate in file Reference 6, Engineering and Design 17" (1971) 247-280 North Holland Publishing Co.
This item is to have the qualification data for radiation.
i
- Unable to locate backup date to Reference 4 (ASCO No. 30A) for operating time, temperature, pressure, and relative humidity.
j
- Unable to correlate model number with what is installed in the plant.
i
- Data sheets 3 and 3A (CES) do not agree on "Outstanding Items".
EDS Calculation 0370-025-004, Rev. O, does not make a conclusion f
for 40 year life (BUNA-N).
t Issued Fidding No. 8 e.
Heat Shrink Tubing (Common Equipment)
\\
Reference 6 Franklin Institute Research Labs Report No. F-C4033-3, dated January 1975 (Qualification for Submergence) does not address the duration of the submergence test.
NUREG 0588 requires that equipment that could be submerged should oe qualified by test for the duration required.
Issued Finding No. 9
{
s
Pase 10 of 10 Audit 0-TMI-81 '
f.
Reactor Building Isolation System EDS Calculation 0370-025-005, Rev. O, Reference 8 on CES for Tag No. SV/AHV-1A2 solenoid valve Model No. LB-8316-C35MO does not address the correct model number.
Issued Finding No. 10 There was no mechanism demonstrated to assure that all the r=quirements of the bulletin are being met.
Central Files do not have a tabulation of other equip-ment or components which are referenced in the Emergency Procedures, but are not relied upon, should be available for review. Justification should also be available so that this non-qualified equipment will not be misleading to the operator.
There is strong evidence that TMI Lessons Learned equipment (NUREG 0578) is not being addressed similar to other existing safety-related equipment.
No TMI Lessons Learned equipment is part of the Master List.
Issued Finding No. 11 RECOMMENDATION 1.
Documented direction be generated in order to assure meeting the requirements of the bulletin, to include organizations, departments, sections, and individuals, (deadquarters and site personnel).
This should include it.ter-face responsibilities and define the corporate position on the bull:iin.
i 2.
A complete review should be taken to assure that the qualification docu-mentation is complete to support adequacy of the equipeent.
3.
Technical Functions take the lead in establishing a training program for corporate and site personnel on the requirements of the bulletin, s
AUDIT Audit No.:
Date:
$UC!GSF FINDING
" -8'-
2
8'"
NONCOMFORMANCE Criteria No..
v Finding 1
of 11 Facihty/ Functions:
Technical Functions HQ REQUIREMENT:
Operational Quality Assurance Plan for TMI-1, Rev. 8 dated April 18,1980, Page III-1, Paragraph 3.1.1 states: "The TMI QA Program requires that activities important to safety be prescribed by documente i procedures, instructions, and/or drawings and that these quality-affecting activities be accocplished in accordance with the documents."
FINDING No evidence of management direction to correlate the ef forts of in' ersectional effort in establishing the Master List and qualificatien doc " 2ntation file.
L2 f a ;
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- " 4 d ~ a, *'e f o il e d n g 2 re e r
- 2rp lu-of M U' '/", W prcredurer th-*
r e,y u m.m kon,., 41 < w,, pe, fe r
- hi r, 2 1.
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g:_ 2tte:hed g: eta-Potentially Reportab'e C Yes C No
& y. - f.'r g:E A,
Cognizant Group / Activity:
Technical Funetions f
.,..%c-g/
Aucitor You are requested to furnish CORRECTIVE ACTION for the finJ'ng by the target date below stating the CAUSE for the deficiency, inc.uaing tne extent of the probtem. ACTION TAKEN by you to prevent recur.
rence, and effective date of implemenntion of CORRECTIVE ACTION.
b b'
AcknoMedging fincing:
~
E g n a t u r e,,'
Date Target Date CORRECTIVE ACTION:
Proviced By
.5 ratw e Cate r
A00e0ted Rejecte3 A.LierTeam sea:er Oate CLOSE OUT:
Aosi Tea. 4:..
Caie C: o.te T'ac e s Cc w FCEM QA IQ) AQQQc41Q
Pcg2 1 of 2 AUDIT Nuclear nuoisa Audit No.:0-TMI-81-02 Date:
4/14/81 f
NONCOMFORMANCE Criteria No.: XVII Finding 2 of 11 Facility / Functions:
Technical Functions HQ REQUIREMENT:
IE Bulletin 79-01B attachment 4 page 16, paragraph 7.0 Aging states:
It is not the staf fs position that all Class It equipment be back titted to demen-strate a specific qualified life for operating plants.
This positica does not, how-ever, exclude equipment usint uterials that have been identified as being suscepti-ble to significant degradation due to thermal and radiation aging.
Component main-tainence or replacement schedules should include considerations of the specific aging characteristics of the component materials. Ongoing programs should exist at the plant to review surveillance and maintenance records to assure that equipment FINDING:
(continued - Page 2)
!;o documented evidence in Central tile of a schedule (s) to assure that equipnent which have been identified as being susceptible to significant degradation due to thermal and radiation aging are replaced as necessary.
Potentially Reportabte C Yes O No Cognizant Group! Activity:
Technical Functions i [ <f
[
Auditor You are requestec to furnish CORRECTIVE ACTION for the finding by the target date below stating the CAUSE for the oeficiency, including the extent of the probtem. ACTION TAKEN by you to prevent recur-rence. and effective date of implementation of CORRECTIVE ACTION.
Acknow! edging finding.
~
~
Sign ature Date Target Cate CORRECTIVE ACTION:
P eviced By 5.gneto e ost.
r Acceptec Re;ecteo Aveio, Team seese, cete CLOSE.OUT:
a.ei 7. m.es: -
paie c omowte' T<eo+9 c oes 7oftM dA 70 i Aoooo4io 8'8
i-Finding 2 (continued)
Page 2 of 2 Requiretnent :
which is exhibiting age related degradation will be identiftsd and replaced as necessary.
N
m Peg 2 1 of 2 AUDIT AUCISSF FINDING Audit No.: 0-TMI-81-02 Date: 4/14/81 f
NONCOMFORMANCE Criteria No.:
V Finding 3 of 11 Facility / Functions:
Technical Functions HQ REQUIREMENT: NRC Order dated 10/24/80.
Order for Modification of License Concerning Environmental Qualification of Safety-Related Electrical Equipment page $ paragraph (b) states in part - By no later than Dec.1,1980, complete and auditable records must be available and maintained at a Central location.....Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
FINDING: Existing CPU procedures (Engineering Standards and Engineering Procedures) do not provide appropriate guidance nor is there a progra:n initiated to meet the above requirerent, e.g.
ECM 070 Task RMSC Containment Isolation en Reactor Trip -
This ECM with S-ECM-135 Rev. O will provide diverse containment isolation signals which will, along with the high radiation signal (SECM-059), assure that radio-active material is not inadvertently transferred out of the reactor building even if a 4 psig isolation signal is not reached. The following purchase requisitions are part of the ECM:
Potentralty Reportable C Yes C No Cognizant Group / Activity:
I'C UC Auditor CAUSE fcr the deficiency, includinYou are requested to furnish CORRECTIVE ACTION for the t
rence. and effective date of imple the extent of the problem. ACTION TAKEN by you to prevent recur-ation
- CORRECTIVE ACTION.
Ackncwie:ging find:ng' S,gnature Date
_ Target Date- - - -
CORRECTIVE ACTION.
Provided By 5.v er.<e oete Accepted Reje:ted.
A.acer Team 6ee:er 04 e CLOSE OUT:
AosiTeam Lee m cete Co puter Treca.< g Cose-FORM da 101 A00oC410 88
Finding 3 (continued)
Page 2 of 2 1.
P.R. 86180 dated 4/23/80 calls for "states" terminal blocks various sizes type ZWM 2.
P.R. 86098 Rev. I dated 4/23/80 calls for Master Specialties Co. switch-li t e uni ts, 10EA1C 2F1J 3N4 (C ) R1V114, 10EA1C 2F 1J 3N4 (A) R1V14 and Indi c a t o r Lite units, 1101A1C1D3F2L2h A(N).
3.
P.R. 86614, dated 4/23/80 calls for Clark D-C Time Delay Relays Type PMT-ON-Delay Cat. No. 713-UPA-DC.
P.R.'s state that all the above items are commercial grade items.
Therefore 1.
No engineering evaluation in ECM package to justify using com=ercial grade items.
2.
No objective evidence how the above is going to be added to the Master List.
3.
No Mechanism demonstrated to assure that all commercial items that are required to be qualified by June 30, 1982 will be replaced by that date.
M Nuclear $"Eu0
" " * " " * " o-rni-81-02 o teanuel NONCOMFORMANCE 4
Criteria No.:
III-Finding of 11 Fa cility, Functions:
Technical Funced ons HQ REQUIREMENT: IE Bulletin 79-01B page 2, paragraph 1 under Action To be Taken By Licensees states in part: Provido a "master list" of all Engineering Safety Feature Sys tems... required to f un: tion under postulated accident conditions......
For each system within (including cables, EPA's terminal blocks, etc.)
FINDING: Components o' the Emergency Feedvater/Feedwater System was inspected on the site walk thru.
The manufacturer's name and model number from the nameplate data wAs compared to information given in the component evaluation work sheets (CES) of the Master List.
The master list identified the following Control Panels EF-V 30A & 30B, to function under a LOCA/HELB conditions, with its associated equipment.
.No objective evidence in the master list (no CES) of the 4 devices (CE type K06RS20AP1082) and a Stanwick Terminal Bd. installed in each Panel. Also lack of qualification documentation in Central File for these components.
Potentially Reportable C Yes C No Cognizant Group Activity:
Technical Functions M
<~ ~
Auditor
(
You are recuested to furnish CORRECTIVE ACTION for the finding by the target date beiow stating the CAUSE for the cefic.ency, including the estent of the prco;em. ACTION TAKEN by you to prevent recut-rence, and effective cate of smo:ementat.on of CORRECTIVE ACTION.
s
(
Acknowiecging 'ine!n;;
Signature Date Target Date CORRECTIVE ACTION:
Proviced By 5 a are e Dete Accepted Re,ecteo A.s ior Te e see:,,
sete l
CLOSE OUT.
A.:e 7es
.ee:e-Oe'e Co~ csie Treoma ;oce-
, maw awow o..
i
Pa;;e 1 of 2 AUDIT Audit No.: 0-TMI-81-02 Date: 4/14/81 Nuclear nuoisa l
NONCOMFORMANCE Criteria No.: XVII Finding 5
of 11 FacilN/ Functions. __
Technical Function HQ REQU'AEMENT: IE Bulletin 79-01B attachment 4 page 17, paragraph 8.0 Documentation states in part. Complete and auditable records must be available for qualification
.to be considered valid. These records should describe the qualification method in sufficient detail to verify that all of the guidelines have been satisfied.
FINDING: Main Steam - Tag No. PS-600 Pressure Switch Model No. 9N-05-RR a) Component Evaluation work sheet (CES) ref erences E.D.S. calculation 0370-025-041 Rev. O and 0370-025-042 Rev. O as the qualification data for Relative Humidity.
Both calculations are Engineering Analysis for Pressure and Stress respectively, as such they make no statement about humidity.
b) FSAR Chapter 14 is referenced as the qualification documentation for Chemical Spray.
The FSAR should be the specification requirement not the qualification.
Potentially Reportable O Yes O No Cognizant Group / Activity:
Technical Functions 7 i 7/
Auditor You are requested to furnish CORRECTIVE ACTION for the finding by the target date below stating the CAUSE for the deficiency, including the extent of the problem, ACTION TAKEN by you to prevent recur-rence, and effective date of implementation of CORRECTIVE ACTION.
/.
Acknowledging findu.1:
Signature Date Target Date CORRECTIVE ACTION:
Provided By 5.gna ture oate Accepted / Rejected:
Auditor Tear 9 Le60e' Cste CLC5'i OUT:
l' AwotTeam tes:e-0.te I
Computer tracaing Cow FORM QA fo1 AoOoo41o 18
F1.iding 5 (continued)
Page 2 of 2 1
1
- c) Unable to locate reference 9 Engineering and Design 17" (1971) 247-280, North Holland Publishing Co. in the central file. As qualification back-up data this book should be in the file.
d) EDS Calculation 0370-025-003 Rev. O is the qualification data for radiation.
Pages 4 and 6 of the calculation do not agree on gaseous integrated dose (1HR) and liquid integrated dose (1HR).
page 4 reads -
gas = 1.05 x 106 raas and liquid = 4 x 105 rads page 6 reads -
gas and liquid = 4 x 105 rads and liquid = 1.05 x 106 rads NOTE: There is no indication as to which dose is applicable.
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Audit No.: 0-TMI-81-02 Date: 4/14/37
@lggf NONCOMFORMANCE Criteria No..
XVII Finding 6 of 11 Facility / Functions:
Technical Functions H0 REQUIREMENT: IE Bulletin 79-01B attachmerit 4, page 17, paragraph 8.0 Docu:tentation states in part: Complete and auditable records must be available for qualification
....to be consice ed valid. These records should describe the qualification method in sufficient detail to verify that all of the guidelines have been satisf'ted.
FINDING: Make-Up Svstem a)
Tag No. MU-P2C Pump Hotor (5K37JG403) sheet 6 of 39.
No back up documentation for letter dated 8/5/80 on Radiation (Documentation reference 4) and aging (40 yr. Life) b) Tag No. MU-V-2B Motor operator (S!G-00) S/N10039 0.N. 33763-5C. System Component Evaluation Work Sheer. states that this component for chemical spray qualification is 7.67 PH (Boric Acid) this is not as severe as the specified limits of Note B which states Borated Water of 2270 ppm Boran with NA0d to raise PHO9.5 Potentially Reportable O ves O No Cognizant Group / Activity:
Technical Funetions
/,
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,.... ~ ~
Auditor You are requested to furnish wnHtiCTIVE ACTION for the finding by the target date below stating the CAUSE for the dericiency, including the extent of the probtem. ACTION TAKEN by you te prevent recur-rence, and effective date of implementat?on of CORRECTIVE ACTION.
/,
Acknowledging finding:
Signature Date Target Date CORRECTIVE ACTION:
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o,i, Acceoted Rejected:
i A4 tor Team Leace, Ca'e CLOSE OUT.
Aot Tea ces:e*
oste Computer Tracong Coce.
I FORM Q.A 701 AQo00410 88 1
1 1
Pcge 1 of 2 AlJDIT Audit No.: 0-TMI-81-02 Date:
4/14/81
. $UC!OSE FINDING NONCOMFORMANCE Criteria No.:
XVII Finding 7 of 11 Facility / Functions:
Technical Function HQ REQUIREMENT: IE Bulletin 79-01B attachment 4 page 17, paragraph 8.0 Documentation states in part complete and auditable records must be available for qualification to be considered valid. These records should describe the qualification method in suf ficient detail to verify that all of the guidelines have been s a':is f ied.
FINDING: Decay Heat Removal System a) Unable to correlate the qualification data in Volume IV under the Westinghouse tab, to reference 4 & 5 on the Component Evaluation work sheets (CES) for Pump Motors (Tag No. DH-P1A & 1B). Reference I is identified as Westinghouse General Order No. AL-33940-L and reference 5 is identitied as Environmental Qualification of Class IE Mot:or for Nuclear Out-of-Containment Use, Westinghouse Large Motor Div.,
WCAP-8754 Rev.1 The qualification data does not reference AL-33940-L nor WCAP-8754 Rev. 1.
Potentially Reportable C Yes C No Technical Functions M'
^
- - O Cognizant Group / Activity:
Audito-You are requested to 'urnish CORF.ECTIVE ACTION for the finding by the target date below stating the CAUSE for the deficiency, including the extent of the problem. ACTION TAKEN by you to prevent recut-rence, and effective date of implementation of CORRECTIVE ACTION.
Acknowledging finding:
/
signature Date Target Date CORRECTIVE ACTION:
Provided By S'gnature Date Accepted Rejected:
AvC4 tor Team Leacer Ca'e Av3tTeam Leacer Cate Co, suir Tracting coe,
e FORM OA 701 A0000410 88
Finding 7 (continued)
Page 2 of 2 I
b) Westinghouse file (Volume IV) page 17 is not legible.
Page 1 of 2 AUDIT Audit No.: 0-TMI-81-02 Date: 4/14/81
$UC!OSE FINDING NONCOMFORMANCE Criteria No.: XVII Finding 8 of 11 Facility / Functions:
REQUIREMENT: IE' Bulletin 79-01B attachment 4 page 17, paragraph 8.0 Documentation states in part. Complete and auditable records must be available for qualification
.....to be considered valid. These records should d1 scribe the qualification method in sufficient detail to verify that all of the guidelines have been satisfied y
FINDING:
Decay Heat Closed Loop Cooling a) Tag No. SV/DCV-19A Solenoid Valve (HI8321-A7) ASCO. Unable to locate in file documentation reference 6 - Engineering and Design 17" (1971) 247-280 North Holland Publishing Co.
This item is reference to have the qualification data for Radiation, b) Tag No. SV/DCV-19A - System Component Evaluation WorkSheet - Unable to locate back-up data to reference 4 (ASCO Catalog No. 30A) for operating time, temperature, pressure, and Relative Humidity, c) Unable to correlate Model Number with what is installed in the plant. Component Potentially Reportable O Yes C No Cognizant Group / Activity:
Technical Functions 7j<
_f'
/
Auditor You are requested to furnish CORRECTIVE ACTION for the find;ng by the target date below stating the CAUSE for tno ceficiency, including the exten' of the problem. ACTION TAKEN by you to prevent recur-reace, and effective date of irrplementation of CORRECTIVE ACTION,
.s Acknowledging f;nding:
Signature Oate Target Date CORRECTIVE ACTION:
i l
Provided By S.gnatu e care r
Accepted'Rejectec:
Auc. tor Tesan Le3ce' Oate CLOSE OUT:
Avei ream go. w o.,,
Computer Track.ng Coce-FORM QA fo) AOOOo41o 88
Finding 8 (continued)
Page 2 of 2 Evaluation Work sheet states that model number installed is HT-8321-A7. Per Mr. Hays of ASCO (see Report of Conversation dated 8/13/80 f rom J. E. Thompson (EDS) to Thomas Hays Jr. (ASCO)). A prefix of HT indicates a Class H coil.
Where there is no prefix, the solenoid has a Class A coil. Record of conver-sation dated 8/13/30 nor EDS letter 0370-025-NY-003 dated 6/11/80 f rom J. V.
Moran to T.
P.. Hays, Jr. (ASCO) address a Model Number HT8321-A7.
d) Data sheets 3 and 3A (CES) do not agree on "Outstanding Items".
Sheet 3 states there are no outstanding items, but sheet 3A note 2 states - Coils to be re-placed with new HT coil per purchase requisition HEN 0172. This tag no. (SV/DCV-19A) is not part of Purchase Order 100222 (P.R. 3330-0008 which superceeded MEN-0172) having its coil replaced.
e) EDS Calculation 0370-025-004 Rev. O "Maximum Temperature" of BUNA-N for 40 year life (aging).
This calculation does~ cot make a conclusion for 40 year life.
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Page 1 of 2 AUDIT Audit No.: 0-TMI-81-02 Date: 4/14/81
.$UC!OSE FINDING NONCOMFORMANCE Criteria No.:
XVII Finding 9 of 11 Facility / Functions:
Technical Function HQ REQUIREMENT: IE Bulletin 79-01B attachment 4 page 17, paragraph 8.0 Documentation states in part Complete and auditable records must be available for qualification
.....to be considered valid. These records should describe the qualification method in sufficient detail to verify that all of the guidelines have been satisfied.
FINDING:
_ Heat Shrink Tubing (Common Equipment)
Raychem Thermofit (cable splice).
System Component Evaluation Work Sheet states that submergence qualification is required, and the required operating time is duration of the accident.
NU Reg. 0588 page 12 paragraph 5 states in part.....
Where equipment could be submerged, it should be identified and demonstrated to be qualified by test for the duration required. Work sheet states that reference 6 is the qualification for submergence (Franklin Institute Research Labs Report No. F-C4033-3, dated Jan. 1975). This report does not address the duration of the Pototially Reportab!e O Yes O No Cognizant Group / Activity:
/-
/
Auditor You are regeested to furnish CORRECTIVE ACTION for the findi9g by the target date be'ow stating th CAUSE for the deficiency, including the extent of the problem, ACTION TAKEN by you to prevent recur-rence, and effective date of implementation of CORRECTIVE ACTION.
Acknowledging finding:
Signature Date Target Cate CORRECTIVE ACTION:
Provided By S gnawee care AC ected' Rejected:
Avo: tor Team Leaoer cate CLOSE-OUT:
Awe i ream tes:er o.ie Computer Traceg Coces FORM QA 7ol Aoooo41o 88
f Finding 9 (continued)
Page 2 of 2 submergence test. Therefore, NU Reg. 0588 page 12 paragraph 5 requirement was not met.
s
ENuclear 7r u8ua
^ " " ' ' " "
-'"1-81-02 Oa,e
. m,,1 NONCOMFORMANCE Criteria No.: xyII Finding 10 of 11 t
Technical Functions HQ Facility / Functions:
REQUIREMENT: IE Bulletin 79-01B attachment 4 page 17, paragraph 8.0 Documentation states in part. Complete and auditable records must be available for qualification
.....to be considered valid. These records should describe the qualification method in sufficient detail to verify that all of the guidelines have been satisfied FINDING: Reactor Building Isolation System Tag No. SV/AtiV-1A2 Solenoid Valve Model No. LB-8316-C35MO type N.C.
EDS calculation 0370-025-005 Rev. 0 (ref.8) does not address the correct Model Number. Calculation is based on a Class H coil (Part No. HT...) the Model installed in plant is a Class B coil (Part No. LB...).
See record of conversation dated 8/13/81 for prefixes on HT & LB EDS to ASCO.
Potentially Reportable O Yes C No Technical Functions q'2 j.
[
Cognizant Group / Activity:
- /
Auditor You are requested to furnish CORRECTIVE ACTION for the finding by the target date below steting the CAUSE for the deficiency, including the extent of the problem. ACTION TAKEN by you to prevent recur-rence, and effective date of implementat:on of CORRECTIVE ACTION.
f tv Acknowiedging fincng:
Signature Date Target Oate CORRECTIVE ACTION:
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s,,,.is,.
oit.
A ccep ted. Rej e cted:
g,g I
l CLOSE OUT:
Aw 1t Tee, Le,w
,.e t e l
Comester Tracong Cox FORM QA 7o1 AooC0410 88 i
r-Page 1 of 3 AUDIT Audit No.: 0-TMI-81-02 Date: 4/14/81
-(UClG8rnriilING NONCOMFORMANCE criteria Noa III Finding 11 of 11 Facility / Functions:
REQUIREMENT: IE Bulletin 79-OlB page 1 states in part:
IE Bulletin No. 79-01 required the licensee to perform a detailed review of the environ = ental qualification of Class IE electrical equipment to ensure that the equipment will function under (i.e. during and following) postulated accident conditions.
FINDING: No mechanism demonstrated to assure that all the requirements of the bull-etin is being met.
The following are examples of the lack of compliance:
1.
IE Bulletin 79-01B attachment no. 4 page 14, paragraph 6 states: The equipment qualification program should include an as-built inspection in the field to verify that equipment was installed as it was tested. Particular emphasis should be placed on common problems such as protective enclosures installed upside down with drain holes at the top and penetrations in equipment housings for electrical connections being left unsealed or susceptible to moisture incursion through stranded conductors.
Potentially Reportable O Yes O No Cognizant Group / Activity:
Technical Functions
_, [
Auditor You are requested to furnish CORRECTIVE ACTION for the finding by the taiget date below Stating the f
CAUSE for the cefi:iency, :ncluding the cxtent of the problem, ACTION TAKEN by you to preveret recur.
rence, and effective date of impt tatier/af CORRECTIVE ACTION.
Acknow! edging findir'g-be
/
$$gnature/
Date Targe! Date CORRECTIVE ACTION.
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Provided Gy 5 gmature Date l
Accepted: Rejected:
l CLOSE.OUT:
4.4tres-tes:,
c te Comeuter Tracacg Cooes l
FoRN4 QA foi Aoooo41o 88 l
l
O Finding 11 (continued)
Page 2 of 3 k'
Also stated in Commission Order dated 5/23/80 page 11 first paragraph.
2.
lE Bulletin 79-01B attachment no. 4, page 13, paragraph 5.3.1 last sentence states:
As a general rule, the time required to remain functional assumed for dose cal-culations should be at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Also Supplement #2 answer 12 to question 12, 3.
IE Bulletin 79-OlB supplement #1 answer 2 to question 2 states: A tabulation of other equipment or components which are referenced in the Emergency Procedures but are not relied upon should be avaflable for NRC review. Justification should also be available so that this non-qualified equipment will not-be misleading to the operator.
4.
IE Bulletin 79-01B supplement #1 answer 7 to question 7 states:
Spare parts are required to meet the same criteria ss the installed electrical equipment or com-ponent resulting from the evaluatio of IEB 79-01B.
5.
IE Bulletin 79-OiB supplement #1 arewer 11 to question 11 states in part:......
if equipment is available which meets the requirements of IEEE323-74 it should be used.
6.
IE Bulletin 79-OlB supplement #2 answer 1 to question 1 states in part........
qualification to assure functioning in mild environments must be completed by June 30, 1982 also stated in Commission Order dated 5/23/80 page 12, all equip-ment to be qualified also NRC order dated 9/3/80 page 3.
7.
IE Bulletin 79-OlB supplement #2 answer 5 to question 5 states in part.......
equipment which is or wi'l be installed due to TM1 Lessons Learned should be addressed similar to other existing safety-related equipment (e.g. saturation meter, sump level indicators, etc.)
8.
IE Bulletin 79-01B supplement #2 answer 8 to question 8 states in part: The central location sdould be at the utilities corporata headquarters or plant site....
The staff will accept summary test reports maintained at the utility's central j
file which reference the actual test reports and data available in a single location at ene NSSS vendor's facility. The Licensee / Applicant must make the determination that necessary information and documentation, to support qualification of equip-cent is in conformance with DOR gaideliaes and NUREG-0588. This vendor information file must be maintained current, auditable and available throughout the life of the referencing plant.
9.
IE Bulletin '/9-01B supplement #2 answer 16 to question 16 states in part....The QA programs should accommodato any increased secpe due to the new environmental qualification documentacion requirements.
Procedures incorporated by the licensee for data acquisition should be documented and available for staff review upon request.........
Part 50, Appendix B of the code of Federal Regulations states the the applicant /
licensee shall be responsible for the establishment and execution of quality assurance programs. Specifically in purchasing parts or components, it is the responsibility of the licensee / applicant to ensure that the applicable quality assurance procedures for their plant are met.
10.
IE Bulletin 79-01B supplement #2 answer 17 to question 17 states in part.... Af ter May 1980, all parts used to replace presently installed parts shall be qualified to Category I of NUREG-0588 "unless there are sound reasons to the contrary".......
Justification for deviation from Category I or NUREG-0588 shall be documented by the licensee and records shall be available for audit.
11.
IE Bulletin 79-01B supplement #2 answer 21 to question 21 states in part......
TMI Lessons Learned instrumentation will be considered in the February 1,1981 SER. This equipment is subject to the sam.i requirements as other safety-related electrical equipment............
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Finding 11 (continued)
_Page 3.of 3 12.
IE Bulletin 79-01B supplement #3 invokes NUREG 737 INI Action Plan equipment into the 79-01B Bulletin.
13.
Commission Memorandum and Order dated 5/23/80 page 7 states in part.........
Licensees of operating reactors are to comply with these requirements so that-the applicable equipment in all operating plants shall meet the DOR Guidelines or NUREG-0588........The guidelines leave open the question of what standard will be applied to replacement parts in operating plants. Unless there are sound reasons to the contrary, the 1974 standard in NUREG-0588 will apply.
14.'
GPU letter TMI-1/E1650 dated 12/3/80 to distribution from D. K. Croneberger and D. G. Slear:
Paragraph 1 New Applications states in part:....... Analysis which may include
-sufficiently documented operating history or partial type testing is acceptable for justifying the environmental adequacy of the items in controlled environments.
Partial type testing as mentioned here refers to tests performed by manufacturers to confirm that the design of their item is adequate for its intended use as a commercial grade item.
This statement does not meet the requirements of the Bulletin.
Supplement 1 answer 11 to question 11 states in part......if equipment is available which meets the requirements of IEEE323-74 it should be used. Supplement 2 answer 17 to question 17 states in part: After May 1980, all parts used to replace presently installed parts shall be qualified to Category I of NUREG-0588 unless there are sound reasons to the contrary.... Justification for deviation from Category I of NUREG-0588 shall be documented by the licens2e and records shall.
be available for audit......
The f oregoing indicates that project direction was lacking to define respon-sibility. Technical supervision was not adequate to assure accuracy / completeness.
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inter-Office Memorandum I
. ate June 25, 1981 Muclear a^"
Subject Audit 0-TMI-81-02 Technical Functions Home Office Activities for Compliance of IE Bulletin 79-OlB To Location R. F. Wilson Headquarters Vice President-Technical Functions The subject audit report is attached for your information. A preliminary Post-Audit Conference was held on April 15, 1981, with the responsible individuals.
The results of the audit, as identified herein were presented and discussed. The official Post-Audit Conference was held on May 8, 1981.
Audit responses for findings 2 through 11 were received and reviewed.
The Audit Department comments to the responses for findings 2 through 11 is documented in memo QA/4186, dated 6/25/81, which is attached to this report.
You are requested to assure that a revised response for each finding (1 through 11) are provided to the QA Program Development and Audit Department by 7/7/81.
The corrective action response for each finding must state the cause for the deficiency, including the extent of the problem, action taken by you to prevent recurrence, and effective date on implementation of corrective action.
If you have any quest.iens, please con:act R. J. Guimond on Extension 6395.
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. STROMBERG Manager-QA Program 7)I Development & Audit KJS /RJG/ lab Attachment cc:
SEE DISTRIBUTION Fo r n 6 96 l
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g 6/25/81 QA/4161 P. R. Clark - Deputy Chief Operating Executive cc:
R. J. Chisolm - Electric Power & Instrumentation Manager
/
D. K. Croneberger - Manager, Engineering and Design i
R. F. Fenti - Site (TMI) QA Audit Manager J. G. Herbein - Director, Nuclear Assurance N. C. Kazanas - Director, Quality Assurance F. G. Maus - Supervisor Environmental Qualification M. A. Nelson - Chairman, PORC (TMI-1)
W. F. Schmauss - GRC Chairman D. G. Slear - TMI-1 Project Engineering Manager J. R. Thorpe - GORB Chairman R. J. Guimond - Audit Team Leader T.
Iacovides - Audit Team Member R. N. Whitesel - Nuclear Safety Assessment Director
h, a.
Inter Office Memorandum
\\
{.
ate June 25, 1981 mjNuclear g
Sutyect Audit C-TMI-81-02 Technical Functions Activities (Home Office) IE Bulletin 79-01B To Location Headquarters D. K. Croneberger Director, Engineering and Design The responses to the subject audit findings 2-11 have been reviewed and found unacceptable.
You are requested to furnish a revised response for each finding, stating the cause for the deficiency, including the extent of the problem, action :aken by you to prevent recurrence, and effective date of implementation of corrective action.
L'e request the:
it be submitted as soon as possible, but no later than July 7, 19S1.
Please no:e that all ccrrective acticn responses must be signed and da:cd.
FINDING d2 No decurented evidence in Central File of a schedule (s) to assure : hat equipment which have been identified as being susceptible to signifi-cant degrada:icn due :o thermal and radiation aginr; are replaced as ne:essary.
Corrective Acticn
Response
1.
Let:er from P. A. Levine to D. M. Shevlin, da:ed 2/5/31, identifies the equipment requiring pericdic replacement.
A copy of :nis let:er is in HQ EQ files.
The letter references TMI-1 Procedure AP 1054 2.
TMI-1 will be required to establish a plan to review surveillance and main:enance records to deter-ine if replacement is required.
Comnent to Corrective Action Response The above corrective action does not address:
1.
Cause for the deft:1ency 2.
Extent of the problem FolA 47 076 3.
Action taken to prevent recurrence Effective date of implementation 6//[
A Paintenance Schedule cust be adde'! to the Central Files to demens:ra:c that equipment which is identified in the master list and the preventative f
maintenance program as being susceptible to significant degradation due :o ther al and radiatien aging will be replaced as necessary.
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Page 2 of 11 Audit 0-TMI-81-02 D. K. Croneberger
. FINDING /13 Existing GPU. procedures (Engineering Standards and Engineering Procedures) do not provide appropriate guidance nor is there a program initiated to =eet the requirement of "By no later than Dec. 1, 1980 complete and auditable records must be available and maintained at a Central location,
Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified",
e.g., ECM 070 Task RMSC Containment Isolation on Reactor Trip.
This ECM with S-ECM-135, Rev. O, will provide diverse containment isolation signals which will, along with tha high radiation signal (S-ECM-059), assure that radioactive material is not inadvertently transferred out of the Reactor Building even if a 4 psig isolation signal is not reached.
The following purchase requisitions are part of the ECM:
1.
P.R. 86180, dated 4/03/80 - States terminal blocks.
P.R. 86095, Rev. 1, dated 4/23/60 - >bster Specialists Co.,
switch-lite units and indicator lite units.
3.
P.R. 86615, dated 4/23/80 - Clark D-C Time Delay Relays All purchase requisitions state tnat Lil the above items are commercial I
grade items; therefore, 1.
This item was deleted at the official exit conference and a response is not required.
2 No objective esidence how the above is geing to 5,e added to -he Master List.
3.
No mechanism demonstrated to assure that all ccmmercial items that are required to be qualified by June 30, 1982, will be replaced by that date.
Corrective Action Respense (Refer to finding conclusion numbers 203) The EQ procedure, current'f in preparation, will assure compliance.
Conte nt to Corrective Action Rescons,e This response is unacceptable in that action does not state the cause for the deficiency, including the extent of the problem, and the effec.1ve date of implementation.
1
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Page.3 of 11 Audit 0-TMI-82-0:
D. K. Croneberger
-t f
FINDING id Components of the Emergency Feedvater/Feedwater. System were inspected on the site walk-through. The manufacturer's name and model + ueber from-the nameplate data was compared to information given in the com-ponent evaluation worksheets (CES) of the Master List.
The Master List identified the following Control Panels EF-V-30A & 305, to function under a LOCA/HELB condition, with its associated equipmeat. No objective evidence in the Master List (no CES) of the 4 devices (GE type K06RS20 AP10B2) and a Stanwick terminal block installed in each panel. Also lack of qualification documentation in central files for these components.
Corrective Action
Response
If these components are still required, they will be added to the Master List and CES will be prepared.
Co=nent to Corrective Ac tion Response This response does not address the cause of the deficiency, including t..e extent of the proble=, actien taken to prevent recurrence and the effective date of implementaticn of corrective action.
Let ce bring to your attention the rr;uirement of Enclosure 1 cf the Sulletin, "Action to be Ta'ren by
(
i Lice'..ee", Paragraph 2, "For each Class IE electrical equip:ert iten ident)-
fied in Ice: 1 (Master List) provide written evidence of its envirennental qualifications to support the capability of the item te function under postulated accidenc cenditions.
For these Class. IE electrical equipeen items not having adequate qualificatien data available, 1:entify yeur plans for determining qualifications of those ite=s and your schedule for cor;;et-ing this action".
In that the above items were net reported in the subr.ittal (Master List) and/cr corrected within a reasonable time, a Notice of Vicia-tion =ay bc f orthconing by the SRC, which will subj ect GPL'N to a Civil Penalty under 10CFR2.
FINDINO #$
Cocplete and auditable records must be available fer qualification.
to be considered valid. These records should describe the qualification method in sufficient detail to verify that all of the guidelines have been satisfied.
4 s
- ~ - " * - - - - - - - " - ' - " " " '
Page 4 of 11 Audit 0-TMI-Sl-02 D. K. Croneberpcr Main Steam System Tac No. PS-600 Pressure Switch Model No. 9N R R. '
A.. Component Evaluation 'a'orksheet (CES) references E.D.S. calculation 0370-025-041, Rev. O and 0370-025-042, Rev. O, as the qualification data.for Relative Humidity.
Both calculations are Engineering Analysis for Pressure and Stress respectively, as such, they make no statement about humidity.
B.
FSAR Chapter 14 is referenced as the qualification documentation for chemical spray. 'The FSAR should be the specificatica require-ment not the' qualification.
C.
Unable to locate Reference 9, Engineering and Design 17" (1971) 247-280, North Holland Publishing Co. in the central file as qualification backup data; this book should be in the file.
D.
EDS Calculation 0370-025-003, Rev. O, is the qualification data for radiation.
Pages 4 and 6 of the calculation do not agree en gaseous integrated dese (lHR) and liquid integrated dose (IMF).
6 Page 4 reads - gas = 1.05 x 10 rads and liquid = 4 x 195 rads Page 6 reads - gas and liquid = 4 x 105 rads and liquid = 1.05 x 106 rads NOTE: There is no indication as to which dose is applicabic.
I Corrective Action
Response
A.
Conclusion vill be added to the calculations.
B.
esference vill be clarified.
C.
The applicable chapter frc= the ORNL book, "The Cse of Plastics
& Elaste=ers in Nuclear Radiation", is now in file.
D.
Calculacion vill be corrected.
Com=ent to Corrective Action Response i
A.
Corrective action for Items A, B, and D is unacceptable because the action does not state the cause for the deficiency, action taken to prevent recurrence, and the effective date of implementatien.
B.
Ite: C is unacceptable because the chapter f ree the ORNL is not in the file.
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Page 5 ef 11 Audie 0-TMI-SI-02 D. K. Creneberger I.
FINDING e6 Complete and auditable records must be available for qualification.
to be considered valid.
These records should describe the qualification rethod in sufficient detail to verify that all of the guidelines have been satisfied.
Make-Up System A.
Tag No. MU-P2C Pump Motor (5K37JG402), Sheet 6 of 39.
No backup documentation for letter dated 3/5/80 en Radiation (Documentation Reference 4) and aging (40 year life).
B.
Tag No. MU-V-23 Motor Operator (SME-00) S/N 10039 D.N. 33763-SC.
CES states that this component for chemical spray qualificatien is 7.67 PH (Bot ic Acid) this is no: as severe as the specified limits of Note B, which sta:es Borated Water of 2270 ppm Boran with NA0H te raise Ph approxi a:el;. 9.5.
qorrec:ive Ac:1:n
Response
A.
GE will be tasked to suppl;. the decueentaticn.
S.
The Conpener.: Evaluati:n '. crkshee t (CES) vill be corrected.
Cc==ent to Cerrective Action Response The response is unacceptable.
The corrective actier d:es not s: ate the cause for tne deficiency, including the exten: of the problem, actica taken to prevent recurrence, and effec:1ve date of implementation ef corrective actien.
FINDING 87 Decay Heat Renoval Syster Unable to correlate the qualification da:e in Volume IV under the A.
Westin3heuse tab, to References 4 and 5 en the CES's for pump : ters (Tag No. DH-?lA and 13).
Reference 4 is iden:ified as Westinghcuse General Order No. AL-33940-L and r tierence 51. identified as Environmental Qualifica:icn of Class IE Motor for Nuclear Out-ef-Containeent Use, Westingheuse large Motor Div., WCAP-875;, Rev. 1.
The qualification da:a does no: reference AL-339:0-L ner WCAP-8754 Rev. 1.
3.
Westinghouse file (Volume IV), Page 17 is not legible.
Page 6'of 11 Audit 0-TM1-81-02 D. K. Croneberger
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Corrective Action
Response
A.
Sheet has been added identifying WCAP 6754, Rev. 1, Westinghouse General Order No. AL-33940-L will be obtained.
B.
A legible copy of Volueen IV, Westinghouse, Page 17, will be obtained.
Comment to Corrective Action Response A.
Unable to locate sheet identifying WCAP 8754, Rev. 1 in file.
Corrective action is unacceptable.
B.
The response is unacceptable. Corrective action does not address the cause for the deficiency, including the extent of the problem, action taken to prevent recurrence, and effective date of implemen-tation fer Items A and S.
FJNDING dB Decay Heat Closed too; Coelinc A.
Tag No. SV/DCV-19A Selenoid Valve (HT3301-A7) ASCO.
Unable te locate in file aceutentaticn Reference 6, Engineering and Design 17" f
(1971) 247-280 North Holland Publishing Co.
This ite is reference to have the qualification date for radiation.
s 3.
Tag No. SV/DCV-19A-CES-Unable to locate backup data te Reference 4 (ASCO Catalog No. 30A) for operating time, terpcrature, pressure, and Relative Humidity.
C.
Unable to correlate tedel number with what is installed in the plant.
CES states that model number installed is HI-8321-A7.
Per Mr. Hays of ASCO, see report of conversation dated S/13/80 from J. E. Theepsen (EDS) to Thomas Hays, Jr. (ASCO). A prefix of HT indicates a Class H l
coil. Where there is not prefix, the solenoid has a Class A coil.
Record of conversation dated 8/13/30 nor EDS letter 0370-025-NY-003 dated 6/11/80 frc J. V. Moran to T. R. Hays, Jr. (ASCO) address a Medel Number HTS 3:1-A7.
D.
Data sheets 3 and 3A (CES) do not agree on "Outstanding Items".
Sheet 3 states there are no outstanding items, but Sheet 3A, Note 2, states, "Coils to be replaced with new HT coil per purchase requisiti:n MEN 0172. This tag no. (SV/DCV-19A) is not part of Pur:hase Order 100222 (P.R. 3330-0005 which superseded MEN-0172) having its coil replaced."
E.
EDS Calculation 0370-025-004, Rev. O, "Maximum Temperature" of SUNA-N fer 40 year life (aging).
This calculatien does not make a conclusion for 40 year life.
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Psge 7 of 11 Audit 0-T.'!1-S I -0 2 D. K. Croneberger i
e Correction Acticn
Response
A.
See Finding SC.
B, D, E.
Component Evaluation k'orksheets vill be clarified.
C.
Model number of installed coil will be verified.
Co==ent to Corrective Action Response A.
Unable to loca:e reference data in file.
The corrective action for Ite: A is unacceptable.
B.
The response is unacceptable.
Corrective actien does not address the casue for the deficiency, including the extent of the prcbler, action taken to prevent recurrence, and effective date of implementati:n.
FINDING 8'9 Heat Shrink Tubine Raychen Therref t: (cacle splice) - CES sta:es tha submergence qualiffca: ion is required, and the required opera:ing :ite is duration of the accident.
?
SuReg 0558, Page 12, Paragraph 5 states, in part, ".
. where equipment could be subterged, it should be iden:ified and der.cns: rated to be qualified by test for the duratien required." L'orksheet s:ates that Reference 6 is the qualificatien fcr submergen:e (Franklin Institute Research Labr Reper'.
No. F-C '033-3 dated Januarv 1975).
This report does net address the dura-tion of the submergen:e :est.
Theref ore, NuReg 05SS, Page 12, Paragraph 5, requirecent was not ret.
Corrective Ac:ica
Response
The submergence requirement vill be verified.
If it is required, adequate qualification data vill be provided.
Cotrent to Corrective Action Resp nse The response is unaccep:able.
Corrective action does no: sta:e the cause for the deficiency, including the ex:ent of the problem, ac:10n taken :o preven: recurrence, and effec:1ve date of ir.pler.entation.
l x.
Page 8 of 11 Audit 0-!M1-51-02 D. K. Croneborger f
FINDING 1f10 Reactor Bufiding Iselation Syste:
Tag no. SV/AHV-1A2 Solenoid Valve Model No. LB-8315-C35MO type N.C.
EDS Calculatien 0370-025-004, Rev. O. (Ref. S) does not address the correct model number.
Calculation is based on Class H coil (Part No.
. HT.
.) the model installed in plant is a Class B coil (Part No.
LB.
.).
See record of conversation dated 8/13/S1 for prefixes on HT and LB EDS to ASCO.
Corrective Action
Response
PurchaseLRequest MEN 0172 erders re;1acement HT type coil.
Content to Cerrective Action Resoonse The response is unacceptable for the following reasons:
1.
The corrective acticn dces nc: s: ate :na: the Syste: Component Worksheet will be ccrrec:ed to reflect :he new H! coil.
L Corrective ac: ion dees not state tha: the model number (ott g
nameplate) will be changed to reflect that a HT coil is installed.
1 3.
How is configuration of the compenen: going to be controlled?
I (HT coil installed in a Class B coil cc penen: LB-331e-C35MO) 4 Corrective actica does not acdress cause for the deficiency, including the extent of the problem, action taken te preven:
recurrence, and effective date of implemen:a:1on.
NOTE: Purchase Requisition 3330-0008 supersedes P.R. MEN 0172.
FINDING 011 i
k a
No techanis: demonstra:ed to assure that all the requirements of the bulletin is being met, e.g.:
f 1.
As-buil: inspec:icn in :he field to verify that equipment was installed as it was tes:ed.
2.
The time required to retain func:fonal assumed for dose calculations should be at least I hour.
3.
A :abulation of other equipment or cc:ponents whica are referenced in :he Energen:y Procedures but are not relied upon should be available for NRC review. Justificatien should also be available so that this non-qualified equipment will not be misleading to :he opera:1on.
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Page 9 of.11 Audie 0-TMI-SI-02 D. K. Croneber_:er
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4 Spare parts are. required to ree; the same criteria as the installed electrical equipment or component resulting from the evaluation ef IE379-01S.
5.
If equipeent is available which meets the requirements of IEEE-323-74,-it should be used.
6.
Qualification to assure functioning in mild environrents must be complet'ed by June 30, 1982.
7.
Equipment which is or will be installed due to TMI Lessons Learned should be addressed similar to other existing safety-related equipment.
B.
The licensee / applicant nust make the de:ereination that necessary inf ormation and doeurentation, to supper: qualification of eqeiprent g
is in conformance with DOR guidelines and NuReg 0585.
Sunnary tes:
reports maintained at the utility's central file which reference :he ac:ual test reports and da:a available in a single locetien at :he NSSS vendor's facility vill be a :eptable.
9.
The QA program (s) sheuld accommodate any increased scope due to the new environment qualift:ation dccurentation requirctents.
10.
Af ter May 1950, all parts used to replace presently insta31ed par:s.
I shall be quality to Cctegory I of SuF,eg 0558 unless there are sound
(
reasons to the contrary. Justificati:n for deviation fr:n Categ:ry I l
of NeReg 0538 shall be decueen:ed by the licensee and records shall be available fcr audit.
L 11.
TMI Lessons Learned instrumen:ati:n is subject to the requireeents as other safety-rela:ed ele :rical equipmen:.
11.
Supple =en: n3 to IIS79-013 invokes NuReg 0737 TMI Acticn Plan equipment into the bulletin.
i 13.
I Licensees of eperating reactors are to cceply with :hese requirements
(
so.that the applicable equi;=ent in all opera:ing plants shall meet i
the DOR Guidelines or NuReg 0588.
(Unless there are sound reasons to the contrary, the 1974 standard in SuReg 0588 vill apply.)
14 GPU letter TMI-1/I1653, da:ed 12/3/80, :o Distribu:1:n fr::
D. K. Croneberger and D. G. Slear, Paragraph 1, New Acelica:1 ens, i
sta:es, in par:, "Analysis which may include sufficiently documented 1
opera:ing histery or par:ial type tes:ing is acceptable f er justifying the environ: ental adequacy of the items in controlled environ ents.
Partial type testing as centiened here refers to tes:s performed by i
canufacturers to confirm that the design of their ite is adequate for j
its intended use as a ec=cercial grade iten."
This statemen: does ne:
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Page 10 of 11 Audit 0-TM1-81-02 D. K. Croneberger
{
meet the requirements of the bulletin.
Supplement 1, Answer 11 te Questien 11, states, in part, ".
.if equipment is ava!1able which eeets the requirenents of IEEE323-74, i: should be used."
Supplerent 2, Answer 17 to Question 17 s:ates, in part, "After May 1930, all parts used to replacc presently installed parts shall be qualified to Category I of NUREC OSSS unless there are sound reasons to the contrary.
. Justification for deviation from Category I of NL* REC 0588 shall be doeurented by the licensee and records shall be available for audit The foregoing indicates that project directien was lacking to define responsibility. Technical supervision was not adequate to assure accuracy /ccepleteness.
Corrective Action
Response
1.
Reperts en :he si:e walk through of February 11-12, 1981 (by CA) and April 7-5, 1981 (by Engineering) will be added to the EQ file.
1-14 GPU will ec= ply vi:h II Bulletin 79-013 as ccnple:el:. as possible.
The procedure and criteria decuments now in prepara:icn will descrire how this will be accomplished.
Connents :o Cerrective Action Response 1.
The resp:nse is unacceptable.
Corrective a :icn dces not address :he casue fer the deficiency, including :he ex:ent of the problem, a::icn taken te ;reven: recurrence, and effe::1ve da:e c implementa: ion.
It is agreed tha: :he descrepancies noted in the QA and Engineering site walk throughs should be added te the CES at :he next revisi:n.
however, a clarificatien is needed to explain the prinary purpose for the QA walk through.
The walk through was to verify the adequacy and comple:eness of the information given in the co:ponent evaluatien worksheets (CES) wi:h respect to floed level (elevatien), plan:
.D.
number, =anuf acturer's na:e, model number, serial number (if available) and location.
The Energency Feedwater and Reactor Protection Systers were selected on a sampling basis.
It was not the intent ef the walk
- hrough to verify that equipmen: was installed as it was tested; ner verify : hat equi;nen: was left unsealed or suscep:ible to nois:ure (i.e., drain heles at :he top of enclosures).
Based on the QA and Engineering walk throughs, a 1000 inspection for all systems iden:ified in :he Master Lis: is warranted.
This inspection could include the adequacy and ec=pleteness of the."a s:er Lis: and :he ins:alla: ion requirement of the bulletin.
2.
As to the response to Items 2-14, GPU tust eceply with all the require-ments of :he bulle:1n, er to jus:ify :he deviatiens from the requirenen:a in an audi:able manner.
A
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- cm R. J. Guttond Audi: Team Leader lab
Page 11of 11 Audit 0-TMI-SI-02 D. K. Croneberger.
f P. R. Clark - Deputy Chief Operating Executive ec:
R. F. Fenti - Site QA Audit Supervisor J. G. Herbein - Director, Nuclear Assurance T.
Iacovides - Audit Team Member N. C. Kazanas - Director, Quality Assurance F. G. Maus.- Supervisor, Environmental Qualificatior M. A. Nelson - PORC Chairman W. F. Schmauss - GRC Chairman D. G. Slear - TMI-l Project Engineering Manager M. J. Stromberg - Manager-QA Program Development and Audit J. R. Thorpe - Director, Licensing and Reg. Affairs and GORB Chairman R. F. Wilson - Vice President-Technical Functions R. N. Whitesel - Nuclear Safety Assessment Director Audit File 0-TMI-81-02 l
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EP&I/83/1095
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r OCT 111983 s
j October 7, 1983
-Muclear Subject TMI-l Equipment Environmental Qualification Meeting with the NRC.
O R. J. Chisholm Location Parsippany - CHB Manager - Electrical Power & Instrumen.
The meeting was at Bethesda, Md on October 5, 1983. The purpose was to resolve qualification deficiencies identified by the NRC SER process.
Participating were representatives from GPUN Tech Functions and from three NRC branches, Also the morning session, Robert Pollard of the UCS was present as an in'tervenor.
at The meeting proceeded as expected with no surpriscs, interventions, or new issues.
GPUN had requested this meeting last February because we could not understand what responses were required to the deficiencies cited in the SER, dated December 10, 1982.
The deficiencies were identified in a Technical Evaluation Report (TER) which was an attachment to the SER. The TER was generated by the Franklin Research Corporation under contract to the NRC. Based upon the meeting we now know how to respond to close out the deficiencies. These deficiencies are in regard to docu-mentation and testing and should not result in any equipment changes.
In order to close out the SER, GPUN is required to anewer in writing the deficienc k cited in the TER for 70 items.
Since many of the deficiencies are generic the l
result will be answers on about 20 items.
We committed tc, advise the NRC in approx-imately two weeks as to when we could answer the SER.
After the NRC Equipment Qualification Branch is basically satisfied with the GPUS responce, the program will be transferred to the Inspection and Enforcement Branch, We will then be audited at both TMI snd Parsippany. The Parsippany audit will be to verify that we have the necessary documentation.
The TMI audit will be to verify that the proper maintenance is being performed on environmentally qualified equipment.
f%/%
F. G. Maus Electrical Equipment Qual. Manager FGM:ljn cc: E. T. Danus, Engineer l
P. E. Boucher, Engineer J. J. Colitz, Plant Engineering Director TMI-l D. K. Croneberger, Director - Engineering & Design R. J. Guimond, QA Auditor L. W. Harding, Engineer, PWR Licensing J. W. Langenbach, Manager - Planning & Special Projects g 4, j 9_ p eg D. M. Shoviin, Manager - Plant Maintenance TMI-l Manager PWR Licensing einberg, Project Engineer - TMI Projects
,P. A, Levine, Engineer Senior 1, TMI-l j
M. G, Snyder, Preventive Maintenance Manager, TM1-1 f f/w
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Intar6ffl30 Memorandum #
October 11, 1983
{
E&L:
5102 5 Heeting with NRC on 84'C' Environmental Qualification Manager, PWR Licensing Cherry Hill To Location J. S. Wetmore Attendees:
L. W. Harding (GPUN)
J. Van Vliet (NRR)
A. Finkel (I&E)
F. G.11aus R. LaGrange T. Lee (I&E)
P. E. Boucher P. Shemanski R. Pollard (UCS)
The purpose of the meeting with NRC was to come to an understanding of the outstanding deficiencies of the NRC TER/SER dated December 10, 1982 on Environmental Qualification. Also discussed in the meeting were possible resolutions of each deficiency. GPUN will then supply a letter to NRC docu-menting the meeting of October 5 with proposed resolution of each deficiency.
However, a letter within a week or two is required providing a schedule as to when that letter discussing resolution will be sent.
Attached is an item by item discussion of each deficiency and proposed resolu-tion for items in Category I.B. and II.A.
Category II.C associated with qualified life or replacement schedule are concerned with such items as lub-ricant: but may also include orientation as opposed to that tested. Analyses should be in central file.
Category IV items are those items for which NRC has not reviewed in detail due to lack of FRC review of GPUN documentation.
NRC was interested in how we responded to safety /nonsafety grade system inter-action. We found no interaction problems as developed in our responses to IE Notice 79-22. This appeared to be acceptable to R. LaGrange.
NRC, in a phone call with J. Van Vliet on October 6, indicated that justifica-tion for continued operation may be required for some items.
He~will check with his reviewers.
8~
L. W. Harding Senior Licensin, Engineer LWH:mt cc:
F. G. fiaus > Electrical Equipment Qual. tianager I. Boucher - EP&I Engineer
(,. W. Smyth - Manager Tlil-1 Licensing P. A. Levine - Tf11-1 Engineer Senior R. Guimond - QA Auditor J. S. Wetmore - ifanager, PWR Licensing I. Feinberg - Project Engineer l
Aooooe4s
EQUIPMENT QUALIFICATION DEFICIENCIES TER Deficiencies J
Eoutpment Description 1 2 3 4 5 6 7A 7B 7C 70 7E 8 9 10 11 12 13 14 15 16 1
Limitorque INA SMB xxx Motor valve op.
2 1.imitorque MVA SMB2 xxxx 3
Limitorque MVA SMB3 xxx 6
Limitorque MVA SMB000 xxx 7
Limitorque MVO SMB000 xxxx 10 Limitorque MVA SBJ xxxx x
11 L 51 torque MVA SIE0 xxxx x
14 Limitorque MVA SMB00 xxxx x
15 Limitorque MYA SMB000 xxxx x
26 ASCO Sol Val LB8210C94 x
Solenoid valve 28 ASCO Sol. Val 8300068G xx 29 ASCO Sol. Val 8300C68G
,x 32 ASCO Sol. Yal LB83146 xx 45 Westinghouse Frame 182T xxx x
Motor 46 Westinghouse HP700 xxx x
49 Westinghouse HP250 xxx x
50 Westinghouse HP350 xxx x
51 Westinghouse HP450 xxx x x x x x x 53 Victoreen x
Display Rad monitor 57 Static "0" Ring xx x
x x x x Press switch 60 Bailey RP1211C x
F/P Transd.
l 66 NAMCO D2400X x
Lat. switch 67 NAMCO D1200G2 x
xx 71 Fisher Gov. 304 x
Cold shutdown 78 Foxboro EllGH2 xx x trans x
79 Foxboro EllA!!
x x
81 Foxboro EllGMSAEl xx x
x 93 Foxboro E13DIK x
90 GEMS LS800 x
level switch 106 Kertie cable x
107 Continental wire x
108 Raychem cable splice x
109 GE penetration F01 xx xx 111 GE terminal block EB25 x
114 Conax connector SA1000 xx 115 Conax connector PL14B2 xx 116 GE Thyrector CR2095100DJA x
118 Limitorque INA SitB000 xxxx 119 Limitorque INA SIS 000 xxx 120 Limitorque INA Sits 000 xxxx
l QUALIFICATION DEFICIENCIES
SUMMARY
- C.8TEGORIES IB, IIA, IIB Total 7 of NRC r9quirement Deficiencies NRC Requirement Deficiencies Deficiencies =120 1
Documentation 20 7E steam exposure 2
2 Similarity 30 8 spray 1
3 Aging evaluation 24 9 submergence 0
4 Qualified life 21 10 radiation 1
5 Aging program 0
11 test sequence 2
6 Aging simulation 5
12 test failure 0
7A Peak temperature 5
13 function test 0
(
'78 Peak pressure 2
14 instrument accuracy 0 7C Duration 2
15 duration margin 2
7D Profile envelope 3
16 margins 0
1 1
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Equipment Qualification Deficiencies / Resolution I.
Specific A.
Limitorque tiotor Operators Generally Limitorque tiotor Operators include a motor switch, brakes, grease reliefs and lubrication which are subject to en-vironmental qualification.
(Seals are allowed to leak and are, therefore, not as critical).
NOTE:
I&E is planning to issue a notice shortly which will describe quality control problems (wiring and terminal blocks) experienced by Phil. Elect, associated with Limitorque Operators.
I&E is encouraging sampling disassembly.
GPUN has performed a walkdown of each Limitorque for serial and models nos. Correspondence and test report fr m Limitorque are located in our central file.
Items 1, 3,118 - 120 [WDG V-3; DHV 1&2; CAV-13; tiUV-2; WDL V-303]
GPUN central file contains the necessary references to show simi-larity. Further, Limitorques were preaged and cualifted life was esatblished in B0050.
Item 2[AHV-1]
GPUN central file contains the necessary references to show similarity. An analysis of similarity of the Ding Brakes with those tested verified by the manufacturer will be obtained and filed.
Items 6&7 [CFY-3, 2; CAV-1, 2, 3&F; ICV-2]
GPUN central file will contain a document which will indicate that these valves (motor operators) do not perform a safety function during a containment accident and that their failure will not af-e feet other safety rela,ted equipment or mislead the operator.
Items 10, 11, 14 & 15 [FWV-5; EFV-2; FWV-92; & EFV-1]
GPUN central file contains the necessary references to show simi-larity. GPUN will develop an analysis (thermal lag) which will show that the operator will operate through the temperstare spike (326*F).
4
. B.
ASCO Solenoids There are no ASCO solenoid valves required to be qualified inside containment. New high temperature coil replaced existing coils.
Items 27, 28 and 29, [FWV-17; EFV-30; FW-16]
An analysis will be filed which documents similarity of the model tested to the model at THI-1.
Seal replacement is part of the com-puterized maintenance program.
Item 26 [EFV-30; FWV-16]
For FWV-16's, an analysis will be 3erformed using the MSLB p*ofile or worst case steamline break to slow that the valve completes its function prior to being subjected to an environment for which the solenoid is not qualified.
For EFV-30's, the valves are being upgraded to safety grade as part of our commitment made in the ASLB hearing during the Cycle 6 refueling. Therfore, these valves solenoids will be replaced con-sistent with :iarch 1985 rule date.
J C.
Westinghouse Motors Items 45, 46, 49, 50 & 51 [MUP-4; MVP-1; BSP-1; DHP-1; EFP-2]
Motor lead insulation motor to lead splices and bearing lubricant will be addressed for aging and qualified life and an analysis of the motor tested and that installed in the plant will be per-formed.
EFP-2 will be analyzed for thermal lag to show that the temperature peak in the Intermediate B1dg. can be withstood.
Steam pressure will also be analyzed and evaluated.
D.
Victoreen l
Item 53 [RM-A2; R!t-A5; Rit-A6]
i These radiation monitors (RM-A5 & RM-A6) are indicators for LOCA and are located outside containment and, therefore, subject to a less hostile environment. RM-A2 is located in containment and is l
required for RB isolation. RB isolation is performed.also by other diverse means such as RB pressure (4f). This item requires further development.
E.
Static 0 Ring Item 51 [FW Isolation Pressure Switch (600-607)]
This switch is '
ted inside containment and must function fol-l lowing a steam.Ine break in containment. For items required to l
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m
' k function in less than 15 minutes, one hour margin must be shown.
NRC wants us to investigate a small steam line break to see over what range of time the switch would function. The pressure switch was not tested for high pressure steam. NRC recommends either test or replacement, since the box around switch is not sealed.
F.
Bailey Item 60[AtmosphericDumpValves(E/PConverter)]
The NEMA III housing (AI) of the converter provides no real guaran-tee against steam pressure and humidity. NRC will not accept analysis; only testing or replacement.
G.
NAMCO Items 66 & 67 [ftSY6 Limit Switch (LS); MSV13 Limit Switch]
GPUN wil' review the function of the LS in relationship to Emergency Procedures to show that failure will not mislead the operator. Under LOCA and itSLB sufficient flow to the OTSGs is provided by a single motor driven pump. The steam driven pump is only used for station blackout which does not produce a harsh en-vironment. Valve operation and EFW Turbine driven pump operation can be verified by using qualified instrumentation for EFW flow and OTSG level. An analysis of the housing would be necessary.
!!SV Valve position can be verified independent of the limit switches by using qualified instrumentation for ERl flow and OTSG 1evel. The solenoid valves are continuously energized to keep the j
valve closed; loss of elactrical power causes the valve to open and
(
supply steam to the EFW turbine driven pump steam supply contrel valve. Failure of 115-V13A/B would not affect operation of the two EFU motor driven pumes. Failure of itS-Y13A/B in the open position may result in lifting relief MS-VlA/B. Failure of MS-V13A/B in the closed position may isolate steam to the turbine driven ERf pump.
H.
Fisher Item 71 [MSV-4 Gov]
The function of the atmospheric dump valves during liSLB will be investigated.
If required'for liSLB, the housing will be analyzed to show it envelopes the environment.
I.
Foxboro Items 78,79&81[RL3PT;RBPT282;SP60PT]
The Foxboro Transmitter report is complete for the E 13 series.
Applicability of the Ell series to the report must be performed by analysis.
~
V 4
I Item 93[RBEFT-20]
Reference to the Utility Report on Foxboro transmitters is all that is necessary for qualification.
J.
GEMS Item 98[WDL-LS116]
Reactor Building Sump Level is used in the recirculation mode to ensure proper net positive suction head for the DHR pumps. Tnis instrument if not considered here will have to be considered under post accident instruments (RG 1.97).
II.
Generic A.
Xerite Cable (Item 106)
GPUN needs to show by analysis (letter from vendor) that the pro-duction runs which we have are the same composite as those tested.
B.
Ray Chem Cable Splice (Item 108) t Same as Item 106 above.
.C.
GE Penetration (Item 109)
?
The penetration needs to be reevaluated versus the penetration in-l stalled particularly for radiation. EPRI has performed some work which may be helpful (Note sheet 51).
j D.
GE Terminal Block (Item III)
We need to confirm that the test report is applicable to our 3
terminal blocks. These F blocks have been qualified by other i
i utilites.
E.
Conax Connectors (Items 114 & 115)
GPUN needs to show that the the test information applies to the conax connectors at THI-1.
F.
GE Thyrectors (Item 116)
The GI Thyrectors have been replaced by Square D.
A new SCEW sheet will be sent when the modification is turned over to operations.
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Inter Office Memorandum i
EP&I 81/0176 Au.ust 21. '
Nudear
~
Audit 0-TMI-81-02 Subject Technical Functions Compliance with IEB 79-01B To Mr. J. Stromberg Parsippany This memo transmits to you our corrective actions resulting from the audit.
The audit findings resulted mainly from two causes: (1) Lack of a GPU Nuclear Procedure and (2) Open items on our response to IEB 79-01B.
The procedure for environmental qualification, EP-031 is now being prepared for issue.
It is scheduled to be issued on 9/1/81.
Revision 5 of our response to IEB 79-OlB is ready for submittal to the NRC by licensing.
The environmental qualification of Class lE electrical components in a harsh environment is almost complete. We have, for a few components, disagreed with the NRC's criteria.
This is permissible under IEB 79-OlB, as long as adequate justification is provided.
This justification has been provided with our response.
If you have any questions, contact me.
P6. Afw F. G. Maus Supervisor Environmental Oualification FGM/b1 cci P.E. Boucher P.R. Clark R.J. Chisholm D.K. Croneberger R.F. Fenti J.G. Herbein H.P. Hukill N.C. Kazanas MAA. Nelson W.F. Schmauss D.G. Slear fcI g - f 7-6 f' 6 J.R. Thorpe R.J. Guimond O//6 j
T. Iacovides R.F. Wilson R.N. Whitesel E.Q. File AOoOOb48
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AUDIT Audit No.:
Date:
NUCbCF FINDING
" 02 W 8 '8 '
NONCOMFORMANCE Criteria No.'
V Finding i
of 11 Facility / Functions:
Technical Functions HQ REQUIREMENT:
Operational Quality Assurance Plan for THI-1, Rev. 8 dated April 18, 1980, Page III-1, Paragraph 3.1.1 states: "The TMI QA Program requires that activities important to safety be prescribed by documente.1 procedures, ittstructions, and/or drawings and that these quality-affecLing activities be accocplished in accordance with the documents."
FINDING:
No evidence of canagement direction to correlate the ef forts of intersectional effort in establishing the Master List' and qualification
- " felledng tre : = p1 " ef'iV/ d '/
documentation file.
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Potentially Reportable O Yes O No Cognizant GroupIActivity:
Technical Functions
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Aud) tor You are requested to furnish CORRECTIVE ACTION for the finding by the target date below stating the CAUSE for the deficiency, including the extent of the problem, ACTION TAKEN by you to prevent recur-rence, and effective date of imple ~Pn tion of CORRECTIVE ACTION.
b b/
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signature /
Date Target Date CORRECTIVE ACTION:
Procedure EP-0311s scheduled to be issued 9/1/81.
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AUDIT Audit Ns.: q _pg g _ g g _9 3 Dete:
4/14/81 NE FINDING 1.
NONCOMFORMANCE Criteria No.
- G'II F6n,4irst 2 of 11 t
Technical Functions ll')
Facilit3 Functions:
t REQUIREMENT: IE Bulletin 79-013 attachment 4 paae 16, paragraph 7.0 A g states:
It is not the staffs position that all Class IC equipment be br.ck 'it ted to demon-strate a specific qualified life for operatinr. plants.
This position uoes not, how-ever, exclude equipment using materials that have been identified as being suscepti-l ble to significant degradation due to thermal and radiation aging.
Component main-tainence or replacemer.t schedules should include considerations of the specific f
aging characteristics of the component materials.
Ongoing programs should exist at l
the plant to review surveillanc.e and mainten1nce records to assure that equipment FINDING:
(centinued - Page 2) l No documented evidence in Central file of a schedule (s) to assure that equipment i
which have been identified as being susceptible to significant degradation dua to thermal and radiation acing are replac,:d as necessary.
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Potentially Peportaole C Yes C No 4
8 Cognitant Group Activity.
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Auditor i
You are recuested to furnish CORRECTIVE ACTION for the finding by the target date below stating the CAUSE for the deficiency, including the extent of the problem. ACTION TAKEN by you to prevent recur.
reace, anc effective date of.mp!ementation of CORRECTIVE ACTION.
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a AcknoMedging finding e
t Signature C'a t e Target Date i
1 CORRECTIVE ACTION:
I 1.
Technical Function prepared component work sheets identify the equipment requiring periodic replacement.
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2.
TMI-l review or the verk sheets (P.A. Levine Ltr. to D.M. Shoylin dated 2/5/81) identified to Maintenance The Limited Life components.
3.
TMI-l maintenance is establishing a replacement schedule and surveillance plan to review preventative maintenance records to identify, document, g
g replacement of Limited Life items. -
and schedule I
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Finding 2 (continued) pagg.2 of 2 Requirement:
t which is exhibiting age related degradation will be tant'.f'ed and replaced as necessary, d$y, & /refs2 S.a L s ;^. y f (.$ ) J b f +=~*
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Peg 2 1 of 2 AUDIT Audit No.: 0-TM1-81-02 Date: 4/14/81 YUC!GSI FINDING f
NONCOMFORMANCE criteria No.:
V Finding 3 of 11 Facility / Functions:
Technical Functions HQ REQUIREMENT: NRC Order dated 10/24/80. Order for Modification of License Concerning Environmental Qualification of Safety-Related Electrical Equipment page 5 paragraph (b) states in part - By no later than Dec. 1, 1980, complete and auditable records must be available and maintained at a Central location.....Thereaf ter, such records should be updated and maintained current as equipment is replaced, further tested, or othervise further qualified.
FINDING: Existing CPU procedures (Engineering Standards and Engineering Procedures) do not provide appropriate guidance nor is there a program initiated to meet the above requirenent, e.g.
ECM 070 Task RMSC Containment Isolation on Reactor Trip -
This ECM with S-ECM-135 Rev. 0 will provide diverse containment isolation signals which will, along with the high radiation signal (SECM-059), assure that radio-active material is not inadvertently transferred out of the reactor building even it a 4 psig isolation signal is not reached.
The following purchase requisitions are part of the ECM:
, Potentially Peportacle C Yes O No Cognizant Grovo Actmty:
Technical Functions 1.,
$e -
Aucator You are reat.ested to furnish CORRECTIVE ACTION for the finding by the target cate below stating tre l
CAUSE for the ceficiency, inc!ucin the extent of the problem. ACTION TAKEN by you to prevent recur-rence, anc effectne cate of imple a
tion CORRECTIVE ACTION.
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>gnature Date Target Date tORRECTIVE ACTION:
1.
Technical Functions EQ procedure shall insure divisional compliance with exist-ing requirements.
Procedure #EP-031 is scheduled to be issued 9/1/81.
2.
EQ data vill be filed within the Technical Functions Central Files and not in design work packages.
3.
GPDi has not coc:mitted to qualifying all commercial items by June 30, 1982.
Justification worksheets are being prepared for using coc:mercial grade items.
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Finding 3'
(continued)
Page 2 of 2 1.
P.R. 86180 dated 4/23/80 calls for "states" terminal blocks ' various sizes' type ZWM 2.
P.R. 86098 Rev. 1 dated 4/23/80 calls for Master Specialties Co. switch-lite units 10EA1C2F1J3N4(C)R1V114,10EA1C2FlJ3N4(A)R1V14 and Indicator Lite units,1102A1C1D3F2L2N1(N).
3.
P.R. 86614 dated 4/23/80 calls for Clark D-C Time Delay Relays Type PMT-ON-Delay Cat. No. 713-UPA-DC.
P.R.'s state that all the above items are commercial grade items.
Therefore:
1.
No engineering evaluation in ECM package to justify using commercial grade items.
2.
No objective evidence how the above is going to be added to the Master List.
3.
No Mechanism demonstrated to assure that all commercial items that are I
required to be qualified by June 30, 1982 will be replaced by that date.
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l AU0lT Audit No.
o TMI-81-02 Date: 4/14/g1 Nuclear riN0iNO l
NONCOMFORMANCE 4
11 Criteria No..
III Finding of l
l Facihty/ Functions:
'Lechnical Functions HQ REQUIREMENT: IE Bulletin 79-01B page 2, paragraph 1 under Action To be Taken By Licensees states in part:
Provide a "master list" of all Engineering Safety 1
Feature Systems... required to function under postulated accident conditions......
For each system within (including cables, EPA's terminal blocks, etc.)
FINDING: Components of the Emergency Feedwater/Feedwater System was inspected on the I
site walk thru.
The manufacturer's name and model number from the nameplate data was compared to information given in the component evaluation work sheets l
(CES) of the Master List. The master list identified the following Control Panels EF-V-30A 6 308, to function under a LOCA/HELB conditions, with its associated equipment. No objective evidence in the master list (no CES) of the 4 devices (CE type K0bRS20AP10B2) and a Stanwick Terminal Bd. installed in each Panel.
Also la'ck of qualification documentation in Central File for these components.
Potenoally Reportable C Yes C No e nical Functions
.] r
,,,, j Cognaant Group! Activity.
Auditor You are requested to furnish CORRECTIVE ACTION for the finding by the target date below stating the j
CAUSE for the deficienc3. including the extent of the problem. ACTION TAKEN by you to prevent recur.
rence, and effective date of implementation of CORRFCTIVE ACTION.
A Acknowledging finding.
I 2
1 Signature De Target Date i
CORRECTIVE ACTION:
Items identified in walkdown (April 7-8, 1981) Ayt incorporated into Rev. 5 of the Qualification report.
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Page 1 of 2
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AUDIT Audit NL: 0-TMI-81-02 0:t : 4/14/81 MNE FINDING NONCOMFORMANCE Criterie No.: XVll Finding 5
of 11 Technical Function HQ Facility: Functions:
(
REQUIREMENT: IE Bulletin 79-OlB attachment 4 page 17, paragraph 8.0 Documentation i
states in part. Complete and auditable records must be available for qualification I
....to be considered valid. These records should describe the qualification method in sufficient detail to verify that all of the guidelines have been satisfied.
l FINDING: Main Steam - Tag No. PS-600 Pressute Switch Model No. 9N-05-RR a) Component Evaluation work sheet (CES) references E.D.S. calculation 0370-025-041 Rev. O and 0370-025-042 Rev. O as the qualification data for Relative Humidity.
Both calculations are Engineering Analysis for Pressure and Stress respectively, as such they make no statement about humidity, b)
FSAR Chapter 14 is referenced as the qualification documentation for Chemical Spray.
The FSAR should be the specification requirement not the qualification.
Potentia'ly Reportable O yes O No Cognaant Group Activity:
Technical Functions
> 7 You are requested to furnish CORRECTIVE ACTION for the finding by the target date below stating the CAUSE for the deficiency, including the extent of the problem. ACTION TAKEN by you to prevent recur-rence, and effective d3te of implementation of CORRECTIVE ACTION.
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Acknowledging finding:
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Signature Date Target Date i
CORRECTIVE ACTION:
1 i
a) Pressure switch mounted in a sealed container therefore no need for.idditional qualification.
b) Component will perform prior to the initiation of the chemical spray and therefore need not be qualified for chemical spray, c) Reference 9 is now in File.
?
d) Page 6 of 9 in Calc. 0370-025-003 Rev. 1, dated 6/10/81 has been rinvised t state that inside containment both gas and liquid are present therefore 1.05 X 106 rads should be used.
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Finding 5 (continued)
Page 2 of 2 c) Unable to locato reference 9 Engineering and Design 17" (1971) 247-280, North Holland Publishing Co. in the central file. As qualification back-up data this book should be in the file, d) EDS Calculation 0370-025-003 Rev. O is the qualification data for radiation.
Pages 4 and 6 of the calculation do not agree on gaseous integrated dose (1HR) and liquid integrated dose (1HR).
page 4 reads -
gas = 1.05 x 106 raos and liquid = 4 x 105 rads page 6 reads -
gas and liquid = 4 x 105 rads and liquid = 1.05 x 106 rads NOTE: There is no indication as to which dose is applicable.
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-TMI-81-02 cats: 6ft:fg1 E
OF FINDING NONCOMFORMANCE Criteria No.'
gII Finding 6 of 11 4
1 i
Facility / Func tions :
Technical Functions H0 l
l REQUIREMENT: IE Bulletin 79-01B attachment 4, page 17, paragraph 8.0 Documentation _
states in partt Complete and auditable records must be available for qualification a
....to be considered valid.
These records should describe the qualification method in sufficient detail to verify that all of the guidelines have been satisfied, e
i FINDING: Make-Up Svstem a) Tag No. MU-P2C Pump Motor (5K37JC403) sheet 6 of 39.
No back up documentation for letter dated 8/5/80 on Radiation (Documentation reference 4) and aging (40 yr. life)
' b)
Tag No. MU-V-2B Motor operator (SMB-00) S/N10039 0.N. 33763-5C. System Component Evaluation Work Sheet states that this component for chemical spray qualification is 7.67 PH (Boric Acid) this is not as severe as the specified limits of Note B which states Borated Water of 2270 ppm Boran with NA0d to raise PHO9.5 Potentially Reportable O ves O No Cognizant Group! Activity.
Techr.{ cal Functions Avoitor I
You are requested to furnish CORRECTIVE ACTION foi the finding by the target date beloW 5tating the C AUSE for the deficiency, including the entent of the problem. ACTION TAKEN by you to prevent recur -
i rence, and effective date of implementation of CORRECTIVE ACTION.
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Acknowledging find:ng
$$gnature Date Target Date s'
CORRECTIVE ACTION.
a & b) Component Evaluation Worksheet Rev. 5 establishes proper documentation.
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FORM GA 101 AoOOQ410 68
Page 1 of 2 i
AUDIT Audis' Ns.: 0-TMI-81-02 Date:
4/14/81 Nuclear nuoisa l
NONCOMFORMANCE Criteria No.
XVII Finding 7 of 11 I
i Technical Function HQ F acilit y t Func tion s:
REQUIREMENT: IE Bulletin 79-01B attachment 4 page 17, paragraph 8.0 Documentation states in part complete and auditable records must be available f or qualification
..... to be considered valid.
These records should describe the qua.lification method in sufficient detail to verify that all of the guidelines have been satisfied.
Decay Meat Removal System a)FINDINO:
Unable to correlate the qualification data in Volume IV under the Westinghouse tab, to reference 4 6 5 on the Component Evaluation work sheets (CES) for Pump Motcrs (Tag No. DH-P1A & IB).
Reference 4 is identified as Westinghouse General Order No. AL-33940-L and reference 5 is identified as Environmental Qualification of Class IE Motor for Nuclear Out-of-Containment Use Westinghouse Large Motor Div.,
WCAP-8754 Rev.1 The qualification data does not reference AL-33940-L nor WCAP-8154 Rev. 1.
Potentially Reportable O ves O No I
Tecanical Functions r
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Cogni: ant Group wetivity:
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Avaitor I
You.,re requested to furnish CORRECTIVE ACTION for the finding by the target date below stating the CAUSE for the deficiency, including the extent of the Oroblem. ACTION TAKEN by you to prevent recur.
i rence, and effective date of implementation of CORRECTIVE ACTION.
l
.v Ack nowledging finding.
[ -
Signature Dee Target Date l
CORRECTIVE ACTION:
I ai Note 4 References Order No. NA-58132-L7 which verifies motor data covered within WCAP-8754 Rev. 1 qualification.
b) Vol. IV Westinghouse Page 17 was replaced with legible copy. j J
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Finding 7 (continued)
Page 2 of 2 i
b) Westinghouse file (Volume IV) page 17 is not legille.
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P ac,e 1 of 2 AUDIT Autit N;.: 0-TM1-81-02 Dat:: 4/14/81 Nuclear nN0iNo NONCOMFORMANCE Crit.ein too.
xvii Finding 8 of 11 f
I f aCthty! Functions:
REQUIREMENT: IE Bulletin 79-01B attachment 4 page 17, paragraph 8.0 Documentation states in part.
Complete ar.d auditable records must be available for qualification
.....to be considered valid. These records should describe the qual,1fication method in sufficient detail to verify that all of the guidelines have been satisfied.
FINDING:
Decay Heat Closed Loop Cooling a) Tag No. SV/DCV-19A Solenoid Valve (HT8321-A7) ASCO. Unable to locate in file documentation reference 6 - Engineering and Design 17" (1971) 247-280 North Holland i
Publishing Co.
This item is reference to have the qualification data for Radiation, b) Tag No. SV/DCV-19A - System Component Evaluation WorkSheet Unable to locate back-j up data to reference 4 (ASCO Catalog No. 30A) for operating time, temperature, pressure, and Relative Humidity, c) Ur.ab le to correlate Model Number with what is installed in the plant.
Component Potentially Reportable C Yes O No y
Cogn' tant Group Actmty:
Technical Functions
}
Auditor You are requested to furnish CORRECTIVE ACTION for the finding by the target date below stating the I
CAUSE for the deficiency, including the extent of the problem. ACTION TAKEN by you to prevent recur-rence. and effective date of implementation of CORRECTIVE ACTION.
O f*,
Acknowledging find ng.
6 Signature Date Target Date I'
CORRECTIVE ACTION:
e a) Reference has been added to the Documentation Files, b)
Cat. #30A page 40 identifies unit as explosion prcof, watertight, and for con-tinuous duty.
Model number HT identifies to Cat. #30A page 84 high temp.
coils to 176 F, high humidity, and radiation resistant, c) Model number of installed coil was verified Note #5 was deleted.
d) Sheet 3A Note 2 deleted, e) Calculation states that valve may be operated at 104.2 F for 40 years.
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Finding 8 (continued)
Page 2 of 2 f
Evaluation Work sheet states that model number installed is HT-8321-A7. Per Mr. Hays of ASCO (see Report of Conversation dated 8/13/80 f rom J. E. Thompson (EDS) to Thomas Hays Jr. (ASCO)). A prefix of HT indicates a Class H coil.
Where there is no prefix, the solenoid has a Class A coil.
Record of conver-sation dated 8/13/80 nor EDS letter 0370-025-NY-003 dated 6/11/80 from J. V.
Moran to T. R. Hays, Jr. (ASCO) address a Model Number HT8321-A7.
d) Data sheets 3 and 3A (CES) do not agree on "Outstanding Items".
Sheet 3 states there are no outstanding items, but sheet 3A note 2 states - Coils to be re-placed with new HT coil per purchase requisition MEN 0172. This tag no. (SV/DCV-19A) is not part of Purchase Order 100222 (P.R. 3330-0008 which superceeded MEN-0172) having its coil replaced.
e) EDS Calculation 0370-025-004 Rev. O "Maximum Temperature" of BUNA-N for 40 year life (aging).
This calculatien does not make a conclusion for 40 year life.
Pags i of 2 AUDIT Audit No.: 0-TMI-81-02 0:te: 4/14/81 MNSF FINDING NONCOMFORMANCE Crit ria No.:
xvii Finung 9 of 11
(
Facilit y ' Functions:
Technical Function HQ
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REQUIREMENT: IE Bulletin 79-01B attachment 4 page 17, paragrapa 8.0 Documentation states in part Complete and auditable records must be available for qualification
.....to be considered valid. These records should describe the qualification method in sufficient detail to verify that all of the guidelines have been satisfied.
FINDING:
Heat Shrink Tubing (Cormon Equipment)
Raychem Ther=ofit (cable splice).
System Component Evaluation Work Sheet states that submergence qualification is required, and the required operating time is duration of the accident.
.NU Reg. 0588 page 12 paragraph 5 states in part.....
Nere equipment could be submerged, it should be identified and demonstrated to be i
qualified by test for the duration required.
Work sheet states that reference 6 is the qualification for submergence (Franklin Institute Research Labs Report No F-C4033-3, dated Jan. 1975).
This report does not address the duration of the Potentially Reportable O Yes I.J No j,[
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Cognaant Group' Activity:
Technical Functions 1
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Auditor You are requested to furnish CORRECTIVE ACTION for the finding by the target date below stating the CAUSE for the deficiency, including the extent of the problem, ACTION TAKEN by you to prevent re vt-tence, and effective date of implementation of CORRECTIVE ACTION, I
-( [.
p Acknowledging finding-8 Signature Da t e Target Date 6
f CORRECTIVE ACTION:
1 i
Work sheet was corrected to show that heat shrink tubing is not submerged.
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Page 2 of 2 submergence test. Therefore. NU Reg. 0588 page 12 paragraph 5 requirement was not met.
9 I
2 o.t.:
4f14f31 E FINDING NONCOMFORMANCE Criteria No.'
xyII Finding 10 of 11 l
8 I
FacilityFunctians:
Technical Functions HQ 3
REQUIREMENT IE Bulletin 79-01B attachment 4 page 17, paragraph 8.0 Documentation states in part.
Complete and auditable records must be available for qualification
.....to be considered valid. These records should describe the qualification method in sufficient detail to verify that all of the guidelines have been satisfied FINDING:
Reactor Building Isolation System Tag No. SV/AHV-1A2 Solenoid Valve Model No. LB-8316-C35MO type N.C.
EDS calculation 0370-025-005 Rev. 0 (ref.8) does not address the correct Model Number. Calculation is based on a Class H coil (Part No. HT...) the Model installed in plant 13 a Class B coil (Part No. LB...).
See record of conversation dated 8/13/81 for prefixes on HT 6 LB EDS to ASCO, Potentially Reportable O yes O No Cognizant Group Activity:
Technical Functions
[ - [/
Auditor You are requested to furnish CORRECTIVE ACTION for the finoing by the target date below stating the CAUSE for the deficiency, including the entent of the problem. ACTION TAKEN by you to prevent recur-rence, and effective date of ep'ementaton of CORRECTIVE ACTION, i
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Acknowledging finding.
Signature Due Target Date i
CORRECTIVE ACTION:
)
i i
Work sheet corrected to show that Purchase Order 100222 will replace coil with new HT coil.
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Comwe' Tracting Code F C A *A Q A TD i AooOo41o 88
Page 1 of 3 AUDIT Audit No.: 0-TMI-81-02 Date: 4/14/81 i
MNSF FINDING NONCOMFORMANCE Criteria No.
III Finding 11 of 11 i
Technical Functions HQ Faahty Funca:.s.
REQUIREMENT: IE Bulletin 79-OlB page 1 states in part:
IE Bulletin No. 79-01 required the licensee to perform a detailed review of the environmental qualification i
l of Class IE electrical equipment to ensure that the equipment will function under (i.e. during and following) postulated accident conditions.
FINDING: No cechanism demonstrated to assure that all the requirements of the bull-etin is being met.
The following are examples f the lack of compliance 1E Bulletin 79-01B attachment no. 4 page 14, paragraph 6 states:
The equipment l
qualification program should include an as-built inspection in the field to verify that equipment was installed as it was tested. Particular emphasis should be placed on common proble.s such as protective enclosures installed upside down with drain holes at the top and penetrations in equipment housings for electrical connections being left unsealed or susceptible to moisture incursion through stranded conductors.
I Potentiauy Reportabte O Yes O No j > f " k,,.
Cognizant Group Activity:
Technical Functions Auditor You are reauested to furnish C9RRECTIVE ACTION for the finding by the target date below stat;ng the CAUSE for the deficiency inclL ding the extent of the problem. ACTION TAKEN by you to prevent recut-rence..snd effective date of imp' tat.erhf CORRECTIVE ACTION.
Acknowieaging finding:
d hw_e b
h Signatur Date Target Date i
CORRECTIVE ACTION:
"h Field walkdown 4/7/81 conducted by EDS and CPU is on file within the EDCC.
Compo-nant Rev. 5 work sheets include applicable data.
4 to 14) GPUN will comply with IE Bulletin 79-01B as completely as possible. Where exceptions are taken to 79-01B requirements, they are detailed in CPUN's response to 79-01B.
EQ Procedure EP-031 describing our qualification program is scheduled to be issued 9/1/RI.
7 & 11) THI-2 Lessons Learned 1% 3s requiring environmental qualification include qualification requirements ir. their design.NRC s bmittal requirements will be Pros ded $y erb h/
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Finding 11 (continued)
Page 2 of 3 Also stated in Commission Order dated 5/23/00 page 11 first paragraph.
l l.
IE Bulletin 79-01B attachment no. 4, page 15, paragraph 5.3.1 last sentence states:
As a general rule, the time required to remain functional assumed for dose cal-culationa should be at least I hour. Also Supplement #2 answer 12 to question 12.
IE Bulletin 79-018 supplement #1 answer 2 to question 2 states: A tabulation C
of other equipment or components which are referenced in the Emergency Procedures but are not relied upon should be available for NRC review. Justification should also be available so that this non-qualified equipment will not be misleading to the operator.
IE Bulletin 79-OlB supplement #1 answer 7 to question 7 states:
Spare parts are 4
required to meet the same criteria as the installed electrical equipment or com-ponent resulting from-the evaluation of IES79-013.IE Bulletin 79-018 supple is equipment is available which meets the requirements of IEEE323-74 it should be used, k IE Bulletin 79-018 supplement #2 answer 1 to question 1 states in part........
qualification to assure functioning in miid environments must be completed by June 30, 1982 also stated in Commission order dated 5/23/80 page 12, all equip-ment to be qualified also NRC order dated 9/3/80 page 3.
a 7b IE Bulletin 79-018 supplement #2 answer 5 to question 5 states in part.......
equipment which is or will be installed due to WI Lessons Learned should be addiessed similar to other existing safety-related equipment (e.g. saturation ceter, sump level indicators, etc.)
i i
6(IEBulletin79-01Bsupplement#2 answer 8toquestion8statesinpart:
The Q central location should be at the utilities corporate headquarters or plant site....
- s..I The staff will accept summary test reports maintained at the utility's central 9
ile which reference the actual test reports and data available in a sitigle location at the NSSS vendor's facility. The Licensee / Applicant must make the determination
{ )o \\fpi that necessary information and documentation, to support qualification of equip-ment 14. in conformance with DOR guidelines and NUREG-0588.
This vendor information l
0 file cust be maintained current, auditable and available throughout the life of the referencing plant.
IE Bulletin 79-01B supplement #2 answer 16 to question 16 states in part....The QA programs should accommodate any increased scope due to the new environmental qualification documentation requirements.
Procedurer incorporated by the licensee for data acquisition should be documented and ava11 ably for staff review upon request.........
7 Part 50. Appendix B of the code of Federal Regulations states the the applicant!
licenses shall be responsible for the establishment and execution of quality assurance programs. Specifically in purchasing parts or components, it is the l
responsibility of the licensee / applicant to ensure that the applicable quality
{
t assurance procedures for their plant are met.
ID.
IE Bulletin 79-01B supplement #2 answer 17 to question 17 states in part.... Af ter May 1980, all parts used to replace presently installed parts shall be qualified to Category I of NUREG-0588 "unless there are sound reasons to the, contrary".......
Justification ' er deviation from Category I or NUREG-0588 shall be documented by the licensee and rere-d3 shall be available for audit, j
IE Bulletin 79-01B supplement #2 answer 21 to question 21 states in part......
21 Lessons Learned instrumentation will be considered in the February 1, 1981 f
SER. This equipment is subject to the same requirements as other safety-related electrical equipment............
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f, Finding 11 (continued)
Page 3 of 3 s
1 21 IE Bulletin 79-018 supplement #3 invokes NUREG 737 TMI Action Plan equipment into the 79-01B Bulletin.
Aj Ccemission Memorandum and Order dated 5/23/80 page 7 states in part.........
i I.icensees of operating reactors are to comply with these requirements,so that t
the applicable equipment in all operating plants shall meet the DOR Guidelines l
or NUREG-0588........The guidelines leave open the question of what standard will be applied to replacement parts in operating plants. Unless there are sound reasons to the contrary, the 1974 standard in NUREG-0588 will apply.
1.
GPU letter ntI-1/E1650 dated 12/3/80 to distribution from D. K. Cronsberger and D. G. Slear:
Paragraph 1 New Applications states in part:....... Analysis which may include sufficiently documented operating history or partial type testing is acceptable for justifying the environmental rdequacy of the items in controlled environments.
Partial type testing as mentioned here refers to tests performed by manufacturers k
o confirm that the design of their item is arkquate for its intended use as a p
commercial grade item.
This statement does not meet the requirements of the Bulletin.
Supplement 1 i
'p p
answer 11 to question 11 states in part......if equipment is available which g
meets the requirements of IEEE323-74 it should be used.
Supplement 2 answer h q/ 17 to question 11 states in part:
After May 1980, all parts used to replace Y
presently installed parts shall be qualified to Category I of NUREG-0588 unless
{
there are sound reasons to the contrary.... Justification f or deviation f rem ategory 1 of NUREG-0588 shall be docueented by the licensee and records shall lable for audit......
The foregoing indicates that project direction was lacking to define respon-f sibility.
Technical supervision was not adequate to assure accuracy / completeness.
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Muclear/op-Date I
EP-031 Equipment Environmental
.p, eject Qualification To D. Croneberger Location Headquarters Per ou. agreement, I am forwarding to you our comments on EP-031 for your disposition and corrective action.
1.
Section/ Paragraph 2.0 a.
EP-014 - Procedure for Station Design Criteria Document This procedure has not been issued.
b.
Reference to Oyster Creek Environmental Qualification should be included.
2.
Section/ Paragraph 4.1 This section calls Procedure EP-014 Project Criteria Document; whereas Section 2.0 calls it Station Design Criteria Document.
This should be clarified.
3.
Section/ Paragraph 4.2.3 How thic is going to be accomplished should be stated.
Procedure should specify method of accuculating data and source of data.
Section 4.7.1 is not specific in how Section 4.2.3 is going to be accomplished.
4.
Section/ Paragraph 4.3 General Requirements for Other Divisions:
What other divisions fall under this scope?
Further implementation of these requirements has not been stated in the procedure.
Procedure should state the responsibilities, activities, and reporting requirements for the following organizations:
a.
Technical Function Engineering f.
Material Management b.
Plant Engineering g.
Information Management c.
Plant Maintenance (Parsippany & Sites) d.
Plant Operations h.
Warehousing e.
Quality Assurance 1.
EDCC j.
Training pz n U6 ape A0000648
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Pcge 2 cf D. Croneberger 5.
Section/ Paragraph 4.5.3 Review should also include documents regarding Oyster Creek 6.
Appendix A-1 a.
MEP distribution to licensing and their submittal to NRC has not been specified in Section 4.5.
b.
It is not stated in Section 4.5 who is responsible for review /
comment of criteria documents under Station Operations, 7.
Appendix A-2 Functions of DDCC has not been explained in Section 4.6 (e.g. the interface between EDCC and DDCC).
8.
Appendix A-3 a.
What departments within the generating station interface with the management of engineering projects for the development of Environmental Qualification data.
This liason should be described in the body of the procedure.
b.
It is not stated in Section 4.7 who is responsible for review /
comment of environmental equipment data under Station Operations.
General Comments The procedure does not address nor reference all the implementing procedu:es needed to assure that all the requirements of the Bulletin is being met.
In other words, this procedure falls far short of standing alone for the effort needed to assure that the Master List is maintained current and auditable.
Additional Comments 1.
ES-Oll Methodology and Content of GPUN Quality Classification List, Rev. 4 and EP-Oli Quality Classification List, Rev. O, which are reference documents in EP-031 do not incorporate the environmental qualification equipment in total for TMI-1 and Oyster Creek (e.g. Monitor equipment for NUREG 0737).
J 2.
ES-011 does list the TMI submittal in the Reference Section; but the Oyster Creek submittal is omitted.
The Bulletin (79-018) which is going to be codified in Regulator Guide 1.89, Rev.1, is not addressed in the bpdy of the procedures.
Reference to the E.Q. requirements should be addressed in the following paragraphs per proceduret
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Page 3 of 3 D. Croneberger
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ES-ll I
)
5.2(3) - either 79-OlB or Reg. Guide 1.89, Rev.1 (which is out a.
for comments) b.
Appendix A - Note 2 (same as "a" above)
Appendix B
.^,.2.lF - I believe Relative Humidity & Aging should c.
be added.
d.
Appendix B 2.9 (same as "a" above) e.
Appendix C - all E.Q. equipment must be listed f.
Appendix E - all E.O. equipment must be listed EP-011 a.
3.1(3) either 79-013 or Reg. Guide 1.89, Rev. 1 r
Should you have any questions regarding this memo, please contact me.
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< UINuclear momorendum
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Open Audit Finding Date:
April 4, 1984 Audit 10-THI-81-02 PDA/84-107 From:
R. J. Guimond Location. Cherry Hill Building To:
M. J. Stromberg
REFERENCE:
(1) Open Audit Findings (2) Letter EP&I/82/0400 (3) QDR-84-003 The verification of the proposed corrective action in Reference #2, F. G. Maus to P. B. Magitz, dated 2/5/d2, (latest proposed corrective action to audit from Tech.
Functions) resulted in the close out of Finding 7b only.
Findings 1, 3, Sa, 6a, 10, 11.4, 11.8, and 11.14 are still considered open. Listed below, by finding numbers, are my coments to the proposed corrective action:
Finding #1 - no evidence of management direction in establishing the master 1
11ct (submittal) and qualification of documentation file.
Tech. Functions Procedure EP-031 has been revised and reformatted into Corporate Procedure 1C00-ADM-7317.01, "Equipment Environmental Qualification" and is going tnrough approval cycle; when issued, it will close out EQ Program issued without proper concurrence of the Vice Presidenthp)er,gpcedure wasf6 portion of finding.
(NOTE: QDR84-003issuedinthatth Procedure 1000-ADli-1218.01.)
An effort has been initiated by Tech. Functions to transfer all EQ documenta-tion from the control of the EQ section to the control / custody of ED&CC. File will be eventually transferred to the respective sites. When complettd, turn-over and control of documentation file will satisfy documentation portion of finding.
l 2)
Finding #3 - existing GPUN Engineering standards and procedures do not provide,
I appropri6te guidance in the development and maintenance of EQ documentation file; however, issuance of 1000-ADM-7317.01 will correct the problem.
i 3)
Finding #5a - (Portions b, c, and d are closed) - calculations 0370-025-041 and 04z require conclusions about humidity to be stated.
Verbal corrective l
action received from the Director-Tech. Functions Engineering; calculations to I
date have not y6t been revised.
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ATTACIMDrT 4 Page 2 M. J. Strockerg
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't Finding #6g - (Portion b closed) - no backup documentation available for 4 1
}. fforrective action being worked on in conjunction with open NRC Ietter dated 8/5/80 on radiation and aging for Tag #W-P2C, pump motor.
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Finding #10 - The response to this findin is only a artial answer to the
- problem, corrective action must address hat the app icable drawings have been changed to reflect the modified solenoids.
Unlass the drawings are changed, incorrect replacements may be ordered.
Configuration of this component must be controlled.
- 6), Finding #11 - Items 4, 8, and 14 (Items 1-3, 5-7, 9-13 are closed.)
11.4 Spare Parts - assessment in progress, investigating if warehouse has
/
been purged of non-qualified items and if the qualified life of the y.
equipment is being violated.
s 11.8 GPUN must assure that NSSS records are actual test reports; they f\\
F-support qualification of the equipment; are in conformance with DOR guideline, and NUREG 0588; and are maintained current, auditable, and available throughout life of the plants.
11.14 a)
Revised response required from Tech. Functions to note that procedure (TAP-011) will sup/3/80. previously issuad guidelines by ersede letter THI-1/E1650, dated 12 b)
Spare parts problem being treated by assessment in progress.
7$
/ R. J. GUIMOND lab Attachment cc:
B. A. Bader I
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U C O a r j [,f 1
Proposed Corrective Action to ect Audit 0-TMI-81-02
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L To D. K. Croneberger Location Headquarters
REFERENCE:
(1) Letter F. G. Maus to P. B. Magitz (2) Letter EP&I/82/0400, dated 2/5/82 PDA/82 159, dated Tha verification of the proposed corrective action in Reference 1 above resulted in the clore out of Finding 7b only.
Findings 1, 3, Sa, 6a, 10, 11.4, 11.8, and 11.14 are still concidered open.
Listed below are our comments to the proposed corrective action by finding numbers.
FINDING #1 - This finding was written because there was a lack of a written policy and guidelines for an overall Environmental Qualification Program (Corporate and sites), describing in detail the responsibilities, activities, and reporting requirements for all divisions.
This condition still exists as of today.
Thus, there is a limited management involve-ment in the control of activities for this program at all three locations.
Per our agreement, we have reviewed Procedure EP-031 and have submitted our comments to you in Reference 2 above, which we pointed out the inadequacy of this procedure to constitute on its own the Environmental Qualification Program.
Furthermore, it is inadequate in that it does not address all of Technical Functions responsibilities and activities for this program.
With the lack of an adequate written pro 8 ram and coordination, it makes it difficult and cumbersome to verify that all requirements of the Bulletin (79-01B) is being properly addressed by all divisions.
FINDING #3 - The QA Audit Section cannot accept the proposed corrective l
action response which states that an internal QA memo constitutes the formalize program to assure that complete and auditable records will be i
updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
Furthermore, Procedure TAP-Oll, "Purchase Requisitions", Rev. 2, does not l
reference the Environmental Qualification requirements for the Technical l
Function activities.
FINDING #5a - Per our agreement, Technical Functions will add a conclusion to the calculations.
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FINDING 66a - QA has reviewed the proposed corrective action which ref erenced NUS letter dated July 6,1981, Project 1961, as the backup documentation for Reference 4 (G.E. letter to EDS, dated 8/5/80).
This letter is unacceptable as the backup documentation for G.E.
letter for the following reasons:
1.
This document ir for insulation life data and not for radiation.
The analysis in this report is for Mean Time to Failure (MTTF).
2.
The calculations in the report cover Class B and Class F insulation only. The insulation for the motor installed in TMI is Class A.
No actual test data or operating history data in this report for radiation.
Reference #4 nor NUS letter is in sufficient detail; it only makes a statement without backup documentation.
FINDING #10 - The response to this finding is only a partial answer to the problem.
Replacement / spare parts will be purchased from draw-ings.
Corrective action must address that the applicable drawings have been changed to reflect the modified solenoids.
(Configuration l
of this component must be controlled.)
FINDING #11.4 - Answer does not really address the problem.
EP-031 is inadequate in that it does not address what is needed in the spare parts / replacement program to assure that qualified life of the equipment is not violated.
FINDING #11.8 - GPUN must assure ourselves that the records are:
1.
actual test reports (not summary reports);
2.
support qualification of the equipment; 3.
in conformance with DOR guidelines and NUREG 0588; and, 4.
maintained current, auditable, and available throughout the life of the plants.
FINDING #11.14 - QA does concur with the response; but,.our concern is with the statement which states that a partial-type test, as mentioned here, refers to tests performed by manufacturers to confirm that the design of their item is adequate for its intended use as a commercial grade item.
In most cases, a functional type test does not include environmental conditions; therefore, this corrective action is not adequate.
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f,4-Ff ft(L ljs JgZg Nuclear memorandum cas
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Subject:
Assessment of Environmental Qualification Date:
May 16, 1984 (E.Q.) Documentation Files for TMI-1 PDA/84-140 l
From:
L cation:
R. J. Guimond Cherry Hill Building To:
R. J. Chisolm Manager-Electrical Power & Instrum.
An assessment of the Environmental Qualification (EQ) files was performed during the period from December 27, 1983, to February 1, 1984. This assessment was performed by three QA people in the Cherry Hill Building.
It covered selected components from the E.Q. Documentation file in ED&CC and evaluated documentation to 10CFR50.49 and 10CFR40, Appendix B, requirements.
Preliminary meetings were held with QA and the Electrical equipment Qualification Manager during the weeks of March 5 and 12, 1984 Based on these discussions, a subsequent review was performed. This report presents the details and conclusions of the assessment.
Any questions or requests for clarification on the assessment or the attached report may be directed to myself at X.2224.
l l $.. n h I
v'R. J. Guinond QA/EQ Coordinator lab l
Attachment l
l cc:
B. A. Bader QA Prog. Dev. & Audit Manager l
P. E. Boucher Engineer, E.Q.
l J. J. Colitz Plant Eng. Director D. K. Croneberger Director, Engineering & Design N. C. Kazanas Director,QA R. W. Liscom Team Member F. G. Maus Electrical Equipment Qualification Manager D. M. Shovlin Manager, Plant Maintenance Unit 1 g g g7, (, g J. C. Solakiewicz Team Monber M. J. Stromberg Manager, QA Pro ram Development & Audit
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Wayne Manager, QA Des gn & Procurement gj I
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Page 1 I.
PURPOSE
(
A.
Evaluate.the qualification documentation in accordance with 10CFR50.49 "Environmental Qualification (E.Q.) of Electric Equipment Important to Safety for Nuclear Power Plants" and 10CFR50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants", requirements.
B.
Identify equipment for which qualification documentation is adequate or deficient.
II. SCOPE 10CFR50.49 states thut the safety of nuclear power plants include the requirement that the qualification of safety-related electrical equipment be substantiated by auditable documentation that establishes the ability of the equipment to function as specified. Technical Functions Division requested that QA perform an assessment of this c'ocumentation. Technical Functions' letter (EP&I/83/1174, dated December 6, 1983), requested the assessment to evaluate the technical adequacy and completeness of the E.Q. Documentation file for THI-l to meet the requirements of 10CFR50.49 and 10CFR50, Appendix B.
Information Notices of E.Q. test failures and the following general subjects were evaluated:
A.
Do the Qualification Test Reports envelope the environmental conditions which are specified in TDR-282, "THI-1 Qualified Equipment Locations and Environments", Rev. 2.
B.
Do the qualification files include the following environmental parameters g
from 10CFR50.49 and are they based on:
1.
Performance Specification (under conditions existing during and following design basis accidents) 2.
Voltage, frequency, load, and other electrical characteristics (for which the performance specified in accordance with Item 1 above can be ensured) 3.
Temperature and Pressure 4.
Humidity 5.
Chemical Effects 6.
Radiation 7.
Aging 8.
Submergence
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Page 2 f
C.
Was each item of electrical equipment qualified by one of the acceptable methods listed of 10CFR50.497
- 1. Testing an identical item of equipment under identical conditions with a supporting analysis to show that the equipment to be qualified is acceptable.
- 2. Testing a similar item of equipment with supporting analysis to show that the equipment to be qualified is acceptable.
- 3. Experience with identical or similar equipment under similar conditions with supporting analysis; or
- 4. Analysis in combination with partial type test data that supports the analytical assumptions and conclusions.
D.
Are requirements established for record retention, such as duration, location, and assigned responsibility?
NOTE: This assessment covered only a records review.
It did not cov2r surveillance requirements; maintenance; equipment mounting; and replacement program.
III.
SUMMARY
to the report identifies those components that were originally selected to be reviewed. They were randomly selected from the SCEW sheets submittal to the NRC. Therefore, the scope was limited to equipment that must function to mitigate the consequences of a loss-of-coolant accident (LOCA) or high energy line break (HELB) and equipment whose environment is adversely affected by those events (not mild ?quipment). Using the SCEW sheet for each component, the records werefrelative to:
rded 1.
ISEFR50.49 Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants Requirements.
TDR-282, Revision 2,]THI-1QualifiedEquipmentLocationsandEnvironments.
NRC Information Noti (:es of Environmental Qualification Test Failures.
Qualification Documegtation.
Analysis and/or justification of qualification.
,- References in the analysis.
Tne review was limited to records found in the E.Q. files, except in the case of standards.
If records were not in these files, they were assumed to not exist. Because locations were not specified on the SCEW sheets, the worse case condition was assumed from TDR-282.
Page 3 Conclusions
[
A.
E.Q. files are maintained in ED&CC by the Environmental Qualification
- Section, g
8.
Of the 19 components selected as a sample to be reviewed, 15 components were reviewed in depth. Of these @ all but I had some type of discrepancy as noted in Attachment #2. These discrepancies noted were categorized into 7 generic deficiencies.
C.
The Qualification Test Reports do not appear to envelope environmental conditions specified in TDR-282 because locations of the components are not specified. Therefore, some environmental parameters (such as humidity, radiation, etc.) could not be established.
D.
The qualification documentation appear to include the environmental parameters required except for those discrepancies which are noted in the Deficiency Section of this report.
(Also see Attachments #2 and #3.)
E.
The qualification documentation appears to be qualified by one of the 4 acceptable methods listed in 10CFR50.49.
F.
There is no documented program that addresses the control of the documentation within the E.Q. files.
G.
Although people have the book of SCEW sheets, they do not always know if they have the latest revision.
This was primarily noted by the two site people on the assessment Deficiencies A.
Operational Quality Assurance Plan, Page 51, Para. 3.3.1, "Quality Assurance Records Policy" states, in part, that: "QA records...
covered under the scope of the QA Program shall be identified, reviewed, retained, and retrievable.. QA records systems shall be described and t
controlled by approved written procedures and instructions.". Contrary to the above, the Environmental Qualification file is not prescribed by l
an approved written procedure and/or instruction. This had previously l
been pointed out in audit #0-THI-81-02 Finding #1.
B.
In reviewing the E.Q. Documentation files, cases were found where test reports, summary test reports and other data mentioned in the records l
were not included in the qualification file.
(See attachment #2 for l
details.)
l l
C.
In reviewing the E.Q. Documentation, cases were found where test reports are inconclusive to permit verification of qualified life.
(See Attachment #2 for details.)
D.
In reviewing the E.Q. Documentation, cases were found where analysis does not support qualified life.
(See Attachment #2 for details.)
i l
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E.
In reviewing the E.Q. Documentation, cases were found where the SCEW sheets'do not include qualified life data for shelf-life item (lubrication) when applicable.
F.
The data for voltage, frequency, load and other electrical characteristics could not be located in the E.Q. Documentation file.
G.
In reviewing the E.Q. Documentation, cases were found which did not allow 1, O proper review, i.e., inconsistencies in data, calculation errors, typos, etc.
(See Attachments #2 and #3 for details.)
Recomendations
[ fl The qualification file should be purged to get rid of outdated and f
unrelated documentation.
w ]
B.
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j The MasteryList and SCEW sheets submittal to the NRC should be issued as e,
d a Contro11 Manual so that users know if they have the latest revision in their possession.
C.
Elevation and location of the installed components should be added to the y/
SCEW sheets. This will eliminate the worst case assumptions when using TDR-282 THI-1 Qualified Equipment Locations and Environments for 3
verification purposes, IV. ENVIRONMENTAL QUALIFICATION PROGRAM BACKGROUND y
d 'f 'D General Design Criteria 1 and 4 specify that safety-related electrical equip ent in nuclear facilities must be capable of performing their 3jj safety-related function under all normal, abnormal, and accident conditions.
On May 23, 1980, the NRC Commissioners issued memorandum and order CLI-80-21, which stated tnat the D0R guidelines and NUREG 0588 set the requirements that licensees must meet regarding the environmental qualification of safety-related electrical equipment to satisfy 10CFR50, Appendix A, General Design Criteria (GDC)-4.
In addition, the NRC staff issued IE Bulletin 79-018. One of the requirements of the order required that each licensee provide a report (submittal) by November 1, 1980, documenting the qualification of safety-related electrical equipment.
In addition, it required the establishment of a file location for the maintenance of all equipment qualification records.
The file was mandated to be established by i
December 1, 1980.
This information file must be maintained current, auditable and available throughout the life of the plan; it also must contain I
the information necessary to verify the qualification adequacy of all safety-related electrical equipment.
The GPUN response to IE Bulletin 79-01B (Master List SCEW Sheets) is to l
identify the equipment that is required and qualified to perform its l
safety-related functions in any harsh environment that may result, to bring the plant to and maintain the plant in, a safety shutdown condition following l
the loss of coolant accident or high energy line break.
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ATTACHMENT 1 l
COMPONENTS SELECTED FOR EVALUATION 1.
Feedwater/Emerg. Feedwater: Tag No. FW-V-16A (SV3 and SV4) - ASCO Solenoid Valve Model No. LB-8210C94 2.
Make-up - Tag No. SV-MUV Ross Solenoid Valve Model ?!o. 2674A4011 (Cat. 233C93) 3.
Make-UP: Tag. MU-P1A - Westinghouse HP-700 - Frame 688.55 S.O. 68F20835 4.
Rx Building Cooling River Water: Tag No. RR-V-4C - Limitorque Operator (Motor) - Model No. SMB 0.N. 336542-N - S.N. 94839A 5.
Hydrogen Recomb. (NUREG 0737 Equipment): Tag No. LS12V22A-SA - Target Rock Position Ind. Switch - Model No. P/N 1009671 (Solenoid 80Z-14-003) 6.
Comon Equipment: Tag No. Various - General Electric - Elect. Pent. Assy.
Model No. F01 7.
Main Steam: Tag No. PS-605 - Static-0-Ring; Pressure Switch - hodel No.
9N-05-RR 8.
Nuclear Service Closed Loop Cooling System:
Tag No. NS-V Limitorque -
Motor Operator - Model No. SMB-00 9.
Additional Accident Monitoring Equip /RCS:
Tag No. SP1A-LT2 - Bailey Level Transmitter - Model No. BY8B41X-A 10.
Decay Heat Closed Loop Cooling: Tag. No. LSA/DCV-19A - Limit Switch - Model No. SL-2-B2 11.
Decay Heat: Tag No. DH-V Limitorque - Motor Operator - Model No. SMB-3 12.
Eng. Safeguards Actuation System: Tag No. PT-282 - Foxboro Pressure Transmitter - Model No. EllAM 13 Eng. Safeguards Actuation System: Tag. No. PS-287 - Square "D" - Pressure Switch - Type 9013-AMGS - S/N 4038M15G-3-470 14.
Rx Building Spray: Tag No. BS-P-1A - Westinghouse Pump Motor - Model No.
HP250 Fr 5010H - S.P. 68F20805 15.
Core Flood: Tag No. LSA/CFV-19A - Micro Sw Co.- Limit Switch - Model No.
BZE6-2RN - Issue F-48 16.
Rx Building Emergency Cooling: Tag No. AH-E-1A - General Electric Fan Motor l
- Model No. 5K810037Al l
17.
Rx Building Isolation:
Tag No. AH-V-1C - Limitorque - Motor Operator - Model No. SMB 0.N. 3397470A 18.
Rx Protection: Tag No. RC3A-PT1 - Rosemount Pressure Transmitter - Model No.
I 1152 S/N 74861 l
[
19.
Comon Equipment:
Terminal Blocks - States, Model No. NT l
l
ATTACHMENT #2 Page 1 f
DEFICIENCIES AND/0R OBSERVATIONS 1.
Feedwater/Emerg. Feedwater: Tag No. FW-V-16A (SV3 and SY4) - ASCO Solenoid Yalve Model No. LB-8210C94 a.
TDR 282 for Turbine Building shows maximum temperature of 1150; whereas, ASCO states 770F in Catalog 31 and EDS (Impell) calculation 0370-025-004, Rev. 1, shows 1040F; therefore, the status of this component cannot be determined, b.
NoigRasshownintheSCEWsheet. formation in file to support Radiation Exposure qua 1x10 c.
SCEW sheet reference ASCO catalog 30A - Unable to locate this refe-ence in the file er within E.Q. group.
2.
Make-up - Tag No. SV-MUV Ross Solenoid Valve Model No. 2674A4011 7
a.
SCEW sheet shows Ross solenoid Valve 2674A4011 as qualified to 1x10 R; no date on radiation testing / qualification in file to support this valve.
b.
Specific Oak Ridge National Laboratory's test report not referenced (Second page of SCEW sheet states only ORNL, October 1970) for radiation.
3.
Make-UP: Tag. MU-P1A - Westinghouse HP-700 - Frame 688.55 S.O. 68F20835 a.
Westinghouse 700 HP motor uses a "topical" test report digest
[
(WCAP-8754). This is not an actual test report for this piece of equipment.
b.
Westinghouse report WCAP-8754, Rev. 1, references report WCAP-7829 for radiation expose testing. This report is not available in the file.
4 Rx Building Cooling River Water:
Tag No. RR-V-4C - Limitorque Operator (Motor) - Model No. SMB-0 Limitorque Test Reports (600198 plus Addendum 1 and B0058) states that a single test of mid-sized SMB-0 qualified entire line of SMB operators.
No discrepancies were noted with documentation.
5.
Hydrogen Recomb. (NUREG 0737 Equipment): Tag No. LS12V22A-SA --Position Ind.
Switch - Model No. P/N 100967-1 a.
Calculation 1101x5350-77 which is identified as supporting data for Aging states that the component is qualified for 40 years life at 1300F and that Radiatiot; Threshold damage will start at 5x106R (gamma) per EPRI 1558 Fig. C-3.
This calculation does not support the statements in the SCEW sheet which states that the component is qualified for 40 year life at 1300F (Aging). The component will be subject to 2x107 and
{
2750F.
(Radiation and Temperature).
It appears that the calculation l
statement on threshold danage was not factored into the qualified life for Aging.
s
ATTACHMENT 2 Page 2 f
S.
Common Equipment - Elect. Penetration Assy - Model No. F01 a.
This item was not reviewed; The Tech. Functions E.Q. Section informed the audit team that this is an open item in the Safety Evaluation Report (SER) and will be addressed to the NRC.
7.
Main Steam - Tag No. PS-605 - Pressure Switch - Model No. 9N-05-RR a.
The material evaluation sheets show ONRL report dated October 1970. A reference to the actual report should be specified.
(Note: The audit team believe is it ORNL #928 and supplement report 1373.)
b.
Documentation for radiation level qualification not found in file.
8.
Nuclear Service Closed Loop Cooling - Tag No. NS-V Motor Operator -
Model No. SMB-00 a.
Reference #9 on the Limitorque Qualification Sheet CF, dated 7/23/76, is a summary test report for radiation.
It is not actual test data for radiation as required.
9.
Additional Accident Monitoring Equi 3/RCS - Tag No. SP1A-LT2 -
Level Transmitter Bailey Model No.
3YB41X-A a.
The qualification data reference is a B&W letter dated 2/11/80 (McBee to l
Levandoski E.Q. Subcommittee). This letter does not meet the E.Q.
requirements which calls for test report.
In addition, the following discrepancies were noted in the letter:
(1) Model No. BY8841X-A is not listed in the letter.
This may be a typo; there is an item BY84B1X-A listed.
(2) Humidity 100% is written in; unable to determine who made this entry.
(3) Unable to verify 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for operating time; letter does not address.
(SCEW sheet states this item was qualified for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.)
b.
The accident temperature of 2750F as stated in TDR-282 was not factored into calculation 1101X-5350-011 which is referenced as the qualification report for Aging.
10.
Decay Heat Closed Loo) Cooling - Tag No. LSA/DCV-19A - Limit Switch Namco Model No. SL-2-32 a.
Oak Ridge National Laboratory's specific test report not referenced (SCEW sheet states only ORNL, October 1970) for radiation.
l
(
l
~
l
r ATTACHMENT 2 Page 3 f
11.
Decay Heat Tag No. DH-V Motor Onerator - Model No. SMB-3 a.
Same series of component as Item #4; therefore component was not evaluated.
12.
Eng. Safeguards Actuation Sys - Tag No. PT-282 - Pressure Transmitter -
Model No. EllAM a.
Foxboro Test Report T2-1075 is an amplifier test. Nothing is provided in the file to relate the amplifier tested to the transmitter.
b.
The transmitters tested were a different part number and nothing in the file is provided to verify that this report applies to this transmitter.
This review was not completed as E.Q. Section has it on the list of problems to investigate and report to NRC.
(Note: After starting the review, it was pointed out that this component was on the NRC list of items to be reviewed; therefore the review was not completed.)
13.
Eng. Safeguards Actuation Sys. - Tag. No. PS287 - Pressure Switch - AMG5 S/N 4038M15G-3-470 a.
Square "D" generic test reports mentioned in qualification sumaries are I
not included in the file.
b.
The records for this component are contained in sumary test reports.
They are not actual test data as required.
14.
Rx Building Spray - Tag No. BS-P-1A - Pump Motor - Model No. 250HP -
Frame 5010H - S.P. 68F20805 a.
The record for this component is contained in a sumary test report.
Westinghouse sumary test report WCAP8754, REv.1, is not the actual test report as required.
15.
Core Flood - Tag No. LSA/CFV-19A - Limit Switch - Model No. BZE6-2RN -
Issue F-48 a.
Oak Ridge National Laboratory's specific test report not referenced (SCEW sheet states only ORNL, October 1970) for radiation.
l 16.
Rx Building Emergency Cooling - Tag No. AH-E-1A - Fan Motor -
Model No. 5K810037Al o The qualification test report X375 (Joy Manufacturing Co.) does not envelope the elevated temperature for accident conditions.
I
~
ATTACHMENT 2 Page 4 17.
Rx Protection - Tag No RC3A-PT1 - Pressure Transmitter ~Model No. 1152 -
5.N. 74861 a.
Same series of component as Item #4; therefore, component was not evaluated.
18.
Rx Protection: Tag No. RC3A-PT1 - Pressure Transmitter - Model No. 1152 S/N 74861 a.
The Rosemount qualification test report QR-4201-1152 GPT, Rev. A, does not mention the 100% humidity requirement nor the operating life, b.
A 10CFR21 report in the file was issued describing an over pressure condition and reverse pressure condition; both would give an on-scale reading (false reading). Nothing in the file indicated GPUN engineering evaluation of the problem.
19.
Common Equipment:
Terminal Blocks - States, Model No. NT a.
The qualification report, Wyle 44354-1, is for States ZWM terminal blocks. Per EDS memo 0370-025-831, dated 9/22/80, ZWM terminal blocks are flame retardant; Model NT is not. Per the States' data sheet on "ZWM and NT", ZWM applies to flame retardant blocks with self-extinguishing barriers and marker strips. Wyle report only tested the ZWM terminal blocks. Nothing in the file documents showed whether or not this report j
applies to type "NT" terminal blocks, b.
The following references were not in the file:
(1) EDS Nuclear Report No. 02-0370-1058, Rev. 2, dated 6/23/81 (Reference #2 on SCEW sheet.)
(2) Terminal Block LOCA Test for Electrical Penetration Assemblies by R. M. Schuster, 11/6/73.
(Reference #4 on SCEW sheet)
(3) States Co. letter to Yankee Atomic Electric Co., dated 1/27/78 (Reference #5 on SCEW sheet.)
(4) Southern Co. Services letter to EDS, dated 9/18/80.
(Reference #6 on SCEW sheet.)
(5) G.E. letter to Vermont Yankee, dated 2/2/78.
(Reference 7 on SCEW sheet.)
I
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ATTACHMENT 3 Pcga 2 DISCREPANCY LEDGER 1
1 Inconsistencies in data 2
Data or reference not available i
3 Data or reference not specific 4
Letter vice summary test report vice actual 5
Apparent calculation error 6
Documentation problems, typos, etc.
7 Data not related to component 8
Component qualification problem 9
No problem apparent 10 Not evaluated 11 Similarity 12 Aging 13 Temperature 14 Pressure 15 Humidity 16 Radiation 17 Operating time
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,gedLettertofiRC o
Date-subject J. S. Wetmore Cherry llill From:
Locahon T 11-1 Licensing Itanager - C. II. Smyth
&ll Director-Till R. J. Tc 'e To:
/brsg DcOr,I_/3'TCo%
Gh %cice FG %
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PA Les iav 3
Attached is a preliminary / final draft letter to liRC. Please review anu retyrn your corrents/ approval to PWR Licensing - CllD, Parsippany by LA 12, RtM fG WA![ b Original Preparer (s):
Submittal due to fE :
dc,n ll I9 W Please cell o y hr, er h at ext 225T i'. Parsipp.s with concents /apf ; val.
liote s :
hrJ.S.Wetwore!!anager, PilR Lic Attachnent 0300;
January 1984 Office of Nuclear Reactor Regulation Attn:
J. F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Environmental Qualification of Electrical Equipnent On October 5, 1983 representatives of GPUN and NRC met to discuss outstanding items of the NRC SER/TER dated December 10, 1982 on the subject.
By letter dated October, 1983 GPUN committed to provide a resolution of each item and a justification for continued operation (JCO) for those items not completed. provides a tabular listing of the deficiencies by component frer Table 4-1 of the TER (Technical Evaluation Report) for NRC categories I.B.II.A., II.C. and IV. Attachment 11 provides the resolution of each iter.
Based on these resolutions, no additional justifications for continued opera-tion are required.
It is GPUN's position that TMI-l is currently in com-pliance with the Environmental Qualification Rule 10CFR 50.49a as applicable te TM1-1.
Sincerely, H. D. Hukill Vice President - TM!-l cc:
J. Van Vliet R. Conte 0141g-disc 4 4
I
Equipment (ualification Deficiencies / Resolution (Categories I.B. II.A, and II.8) f I.
Specific A. Limitorque Motor Operators GPUN has performed a plant walkdown of each Limitorque motor for o
model and serial number, GPUN has upgraded all in containment Limitorque operators for o
high temperature / radiation including limit switches, brakes, motors, grease reliefs, brackets and lubrication, GPUN central file contains all correspondence and test reports o
required to docuraent qualification, SCEW sheets will be revised to reflect additional infernatior ir.
o the update schedule for submittcl in the fall of 1984.
- 1. TER ltems 1, 3,118-120 [WDG Y-3; DHV-1&2; CAV-13; MUV-2; WDLV-303:.
Limitorque models SMB/Sts-3, SMB-000/SMD-00 are shown to be simiicr to models tested / age analyzed / qualified life in Limitorque Generic Report B0050 Section 4.1.4.
i
- 2. TER Item 2 [AHV-1)
Limitercue ocdel 510-2 is shown to be similar to models tested / age analyzecicualifiec life in Limitoroue Generic Report B0056 Sectt 4.1.4 Cin; moter brake medel 6-71010-6 1s qualified by sinilarit,.
tc mocei 6-03009-50 which was tested as described in test reper:
60019E (F-02232-01).
Both moJc!s are cor.structe:. of similar materials anc rate for approximately tne same torques but differ only in size.
- 3. TER Items 6&7 [CFV-2&3; CAV-1, 2, 3 &4; ICV-2)
Licitorque model SMS-000 is shown to be similar to models tested / age analyzed / qualified life in Limitorque generic re w *,
BOCES.
CFv-212 which are required to function in a LOCA are locatec in the Intermediate Bids. (mile environment for LOCA) anc are qualified for a harsh environment.
These CF valves wi
be therefore deleted from the Master List.
- _ _ _ _, (
- 4. TER Items 10,11,14 & 15 [FWV-5; EFV-2; FWV-92; & EFV-1)
Limitorque models SB-3/SMB-0/SMB-00/Sf18-000 are shown to be similar to models tested / age analyzed / qualified life in Limitorque generic report B0058.
Limitorque has developed a thermal lag analysis which shows that the operator will operator through the Intermediate Bldg. 9MSLB) temperature spike of 325'F (which is equivalent to the 326*F of the Intermediate Duilding profile).
B. ASCO Solenoid Valves There are no ASCO solenoid valves required to be qualified o
inside containment, GPUll central file contains all correspondence and test reports o
required to document qualification, SCEW sheets will be revised to reflect additional information ir, o
the update scheduled for submittal in the fall of 1984.
- 1. TER Item 28 [EFV-30)
As described in GPUN letter dated August 2, 1982 (82-103) GPU!i has removed the EFU latch signal from the EFW control valves. There-fore this solenoid is no longer required be qualified and was deleted from the Master List but the SCEWS were not removed.
e This will be accomplished in the fall 1984 update.
FWV-16B; (SU 1 & 2) MSV-13:i ASCC-selenoids have Deen replaced with qualified ASCO solenoids.
ASCO cualificatier. test reports AQRG7306 anc AQS21678/TR apply, Seal 0-ring replacement is part of the computerized maintenance program.
C. Westinghouse Motors
- 1. TER Itecs 45, 46, 49, 50 & 51 [MUP-4; MUP-1; BSP-1; DHP-1. EFP-2:
- a. Motorettes (stators) - tested included silicon rubber insulated lead wires. Aging analysis on the assembly showed a 40 years life expectancy.
t.. Bearing Analysis - shoned that the bearings could withstanc a LOCA/HELB (ref. GPUh calculation 1101X-5350-000 and GPUN mem: R.
Spragg tc D. Slear dated S/14/81).
. i
- c. Motor Lubrication (Exxon Terisstic 32) -_ is controlled within the preventative maintenance program and is rated by Exxon at a radiation level of 100 rads with a flash point of 410*F.
- d. Lead splices - are controlled within the corrective maintenance program by GPUN procedure 1420-Y-15.
EFP-2 was analyzed in Westinghouse Report dated 1/01 for motor insulation life analysis which envelopes the thermal lag peak for the Intermediate Oldg. of 326*F.
Similarity for the above listed motors is established by Westinghouse report WCAP 8754 Rev. 1 Section 2.
D. Victoreen Radiation Monitors
- 1. TER Item 53 [Rm-A2; A5, A6]
These radiation monitors (RM-A2, 5&S) are indicators of LOCA and ac are located outside containment (subject to a mild environment).
These SCEW sheets will be deleted.
E. Static 0 Ring Pressure Switch s.,[
o'~
1
- 1. TER Item 57 [FW Iso. Press Switch (600-607)]
These switches.will be replaced prior._to restart by a qualified pressure switch.
i No justification for continued operation is required since the plant will not go critical prior to restart arc.
therefere ne nuclear heat will to generated, F. Bailey E/F Converters v
- 1. TER Itec 60 [P.SY-4; MSV-4 (atmospheric dump valves) will be replaced by MSV 2 & B (block & condenser bypass valves) whcih are qualified and is a suitable alternate path to licensed (hot) shutdown.
[Ref. Vol. 0 of 8/21/81 submittal to HSV-2.)
SCEW sheets for MSV-8 will be provided in the fall 1984 submittal.
G. NAMCO Limit Switches
- 1. TER ltem 66 & 67 [MSV-6; MSV-13)
Under LOCA and MSLB sufficient flow is provided to the OTSG's oy a single motor driven EFW pump.
(See GPUN letter dated 3/22/83).
The steam driven EFW pum; is only required for stcticr. olackout f
which does not produce a harsh environment.
Failure of the limit the OTSG's which could be reduced immedia qualified EFW flow and OTSG level instrumentation.
Failure of the limit swith (f1SV-13EFW system wi'1 funct monitor valve position and may resu)lt in lifting reliefs butre because of qualified EFW flow and 0TSG level this will not misle the operator.
These valves will be deleted from the Master Li H. Fisher Limit Switch
- 1. TER Item 71 [I!SV-4)
The valve position indication for the atmospheric dump valves will be deleted from the Master List (see discussion of item I. Foxboro Transmitters
GPUN possesses original purchase orders whien are part of the file which refers back to a plant tag number or vendor letters which are part of the EQ file.
B&W evaluation of Class lE Incontainment Contro tation (77-11207001-00) dated 7/81, which is part of GPUN central file.
The Ell series transmitters were purchased prior to 1974 and were The time duration listec in the SCEWS indicates 86 hours9.953704e-4 days <br />0.0239 hours <br />1.421958e-4 weeks <br />3.2723e-5 months <br /> wnich exceeds the 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> (10 sec.) of the profile (Items 78 & El).
subject to as severe an environment. Item 79 is located in the Aux.
- 2. TER item 93 [RB EC Flow]
The utili'.y report (Wyle 45592-4/model E13 DMK) on Foxboro transmitters documents the qualification of this transmitter.
J. GEMS Limit Switch
- 1. TER ltem 98 [WDL LS-Il6)
The Reactor Building Sump Level instrument has been upgraced ir dotiumented in a revision to the SCEW sheets in fal submittal via Wyle Report No. 45102-1.
I l
switch of item 98 will be deleted.
Consequently, the limit l
l II. Generic A. Kerite Cable
- 1. TER Item 106 GPUN has in central file the ori inal Bill of !!aterials which 0
documents the applicable test report for the Kerite cable.
B. Continental Cable
- 1. TER Item 107 GPUN has in central file a letter from the vendor which establishes similarity between the cable tested and that installed at Till-1.
The lots are traceable through purchase orders which are part of our QA files.
C. Ray Chem Cable Splice
- 1. TER Item 108 GPUN has reviewed the applicable Ray Chem Test Reports and determined that it is applicable to the splices at TMI-l because the material corposition is the same for all Raychem splices.
D. GE Penetration
- 1. TER Item 109 GOUN had resvaluatec the penetrations installed at TM:-l anc have determined that they are all above flood level; and that the hyperion paint is immune te caustic spray, GPUN has als; perf;rre:
an aging analysis on :ne penetrations.
E. GE Terminal Blocks (ED-25)
- 1. TER Item 111 GPUN has determined that these terminal blocks were tested to AM:
110-11004 page 3.
The SCEW sheets will be revised te reflect thu change.
F. Conax connectors
- 1. TER Itec 114 & 115 1
GcUN has reviewed the Conax Conne: tors and determined that the, sre pressure seal modules described in PL-14-BL and IPS 409 and 325.
~.
~6-
{J G. GE Thyrectors
submittal.
A new SCEW sheet will be sent in our fall 1984 a
i 1
l
+
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I Equipment Qualification Deficiencies / Resolution (Category II.C)
I.
Qualified Life A. Limitorque flotor Operators TER Items 5, 17-22, 24 [BS-V-1, 2, 3; DH-V-3, 4, 5, 6, 7; MU-V-12, 14, 16,36,37;NS-V-35)
Qualified life is established in Limitorque Generic Report B0058.
B. ASCO Solenoid Valves TER Item 33, 36, 39, 40 fSV/AHV-1A; SV/CAV-2, 5, 189; SY/ ICV-6; SV/MUV-3,26; SV/UDL-V304, V534, V535]
The qualified life, based upon an Arrhenius Analysis, is shown or, the SCEW sheets.
C. Static 0 Ring Switches TER Item 56 [PS-672 through 675)
The qualified life is established by tne calculations listed on the SCEW sheets. Tne basis for these calculations is an Arrher.ius Analysis.
D. Scuare D Switches TER Items 56 & 59 [PS-283, 284, 286, 28, 269, 290, 480 (745)?
The replacement schedule for sub component parts is a part of the computerized Preventive Maintenance Schedule, E. Namco Snap Locks Switches TER Items 63, 64, 69 [(LSA, LSB) AHV-1A; (LSA, LSB) CAV-2; (LSE, 33; ICV-3; (LSA, LSB), MU-Y-3, 18, 20, 26: (LSA, LSB) WDL-Y304, V53a, V535:
The material evaluation for a 40 year life of Buna N is correct basc:
upon an Anhenius Analysis.
The conflicting temperature data ir. the l
TER does not include an Arrhenius Analysis anc tnerefore cannet De i
evaluated.
l
F. Nicro Switches TER Item 72 [(LSA, LSB) CAV-19, 20,189; (LSA, LSB Same resolution as E above.
II. Replacement Schedule The replacement schedule for all environmentally qualifie Till-1 is included in the computerized Preventive Maintenanc u ament at The replacement schedule is not included on the SCEW sheets aedule.
sheets specify qualified life on sub components or mate The SCEU that life is less than the plant design life of 40 years n
l l
l l
I a
-,n
.g.
Equipment Qualification Deficiencies / Resolution (Category IV)
I.
Generic This documentation was not requested by the Fr:nklin Research Corporatier.
from GPUN in any of their requests for documentation. GPUN has provided all of the documentation requested as documented in GPUN letters dated
}iarch 2, 1982 (E&L: 4Co2/82-052), furch 24,1982 (5211-82-067) and June 25, 1962 '5211-82-155). All documentation is contcined in the GFUN central file.
II. Specific A. Ross Solenoid Valves TERItem42[SV/MUV-lG,20)
See I above.
B. GE Motors TER Item 44 [(A, B, C) liU-P-2, 3)
The TER states that tha,e motors are considered to be qualified.
C. GE Metcrs TER Itet 47 [(A, L C) Ah-E-l;'
See : above.
C. Roseccunt Pressure Transmitters TER Item 76 [(PT1, 2) RC3A, B)
The SCEW sheets will be revised to li t specific (instead of sunna y qualification reports and change the q.elified li'e from 40 to 10 years. Revised sheets are schcduled for a fall of '84 submittal.
E. Barton D/P Transmitters TERItem77[FI-5-77,78,79)
See I chove.
1
{
F. Bailey Level Transmitters TERItems85,88[.(LT1,2,3)RCl;(LT4)SPIA,B)
Report is on file at the NSSS vendor B&W.
G. Bailey Level Transmitters TERItem07[(0$1)DPT1,2;DS3-LT;BS5-LT)
- 1. FRC disagrees with GPUN's analysis that this display instrumenta-
-tion need not be environmentally qualified. FRC did not have the docutentation necessary to make this conclusion.
- 2. See I above.
H. Rosemount Temperature Transmitter TERItems90,91[(TE2,3)RC4A,B: (TEl, 2, 3, 4) RCSA, B)
- 1. Report is on file at the NSSS vendor, D&W.
- 2. The qualified life on the SCEW sheets will be changed from 40 to 10
- years, i
J. Stanwick Terminal Blocks TERltem113[CommonItem; Qualifi:stion is basec upor, a rep rt that is proprietary to the Dui.c Power Cc.
Only summary informatier. is available to GPUN.
Intor-@ffloo Momerendum Nucltear a'e January 27, 1981.
Suciect Freliminary Draft letter e,
e,
., o
.. :n
,c-s-Location TMI Nuclear Station To F.
A.
Sinegar Middletown, PA 3220 8k-003E l
The attached c nn+: te v e r c.
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To Locat e Three Mile Island Attached are "Oc:=cnt Resolution" sheet (s) on the following docu=ect:
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fap H $0 MNuclear mmment Honolution n.w.i wa n. W.O. No. DPcimm;l regnt 4 n.wi... - p.i.. co m m.ni. o,#,..., o.orn.e % EllHW AGid,lkhe, lleWRftlitig, O'NI N9 PmIPue. g p,,,g,i, Commery Opninwol RefecWen G 4 (w A / tad 1 9n f o (*A ~ ,4 & JM a. sul p-en AA m4. ard.. ar n >o ad. Ah ( Jept/ gle/AA offd M A Nilig z v.
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Inter Office Memorandum Date 'a n.:a rv ? ^, 16 i Nuo ear SuDse#t '. ".. *. * ". ~ *.. ' " - - '. ' '. ' ~ ' '..:.n' ' ". ": ' '.' n' '.' v' '. ' C ' r_.'.r..~ ~. :".. 'n" .r. s"..' F.".:. '.".' File: Environr. ental Qualificatier.s 3300,on!. 022 B To t, y, gap Ing txat Three Mile Island p...... p p.,, p... .,a re. e...,. ~.s a s.s ~ ~.,. n. . 'asa...a I ...... s s. ...,..:......n n..a,.. 1. ..... -.ne.# 4,.,...... Fre;ir.ir.*.ry ;- s rt let er to the '::' - SI-Si ..g. ..ew..:... ...n . _......, 3.. g. s. ........s. .o... A
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inter Office Memorandum i (hM'5 >('I6f" Date Muclear S osect (wWrh 0 I
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,a To t.oc a t'on S.ree Mile Island Attached are "Oc= ent ?csolution" sheet (s) en the follo.ing document-h6 C- $Yf b%Ds 4 Y " M M' &!@a /i,'9 If there are an;. ::n erns regarding tnese ec =ents, please conta:: te individual sho T. as ine reviever on the Oc=ent Resciutien sheet: '. / l J y At* a c h:t r
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no i tu los aP f o e t a o D r oN on f N o t A On nit a oc /WP l s e B sl e e n p ro ta t n n i t g c e e n i r j w O o n n Ho o c i t tn s u t ^ pe l e n o cw c n s Ao o C a s ,n s t o ne m =: tn U" m C so I o f o c e ta I D ""I r r a e w e e iv l e e e H cs c no eP u f u r / e e i e s r R P i t n d t e n n_ s o e e e e N u u l 1 t c. f e o 1 D D
Nuclear memorandum I subject Environmental Qualification of oate February 6, 1984 Electrical Equipment E&L: 5196 From: L. W. Hardin9 Location: Cherry Hill Bldg. Plant Engineering Director - To. J. J. Colitz Attached, please find resolutions of coments provided in your meno (3300-84-022) of January 3, 1984. Pleae be advised that three cornents were rejected and were discussed with P. A. Levine and R. O. Barley on 2/6/84, s L. W. Harding Senior Licensing gineer LWH:mt att. cc: C. E. Hartman - Lead Elect. Eng. TM:-l P. A. Levine - Eng. Sr. I it':-l ti. G. Snyder - Prev. tiaint tigr. iti:-l R. J. Toole - Ops & ftaint. Dire:ter - Tit:-i i C. W. Snytt - TM:-l.icensing lianager i I l l l l l a:. : w t,.
1 l [, gJjNuc ear com nent nesolution fle.euess 3/A h .o W0 W g gy.,,,,,,,,, te. I ie. u o ry I%. t e Ic t t..r tn Ure yg},g pse,,g ..A.,j6. e..h _r i. . q, i.. :. : :,,,. i..,.i....
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- i e.. :", flowiewre it.s.e of Cunwnents Originatoe D4ste of Resoluonne - - - - - ~ -Cununens e ~ ~ - - Iseen Ilefeeeen a ,.luen As snal f*entwesnel flen neleng:* Accept Hoject Heeeese for No. 8'assall'eu s Cununent Conmwnt flejecafee. g,, ] t *.v er ir!
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X October 17, 1983 letter P e '..v e r d '.,v e r I..t t er re r. *. -n e
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X xerox pr'Oblem fcff"r n n.1 At 8 reclimen t 1I. l l e" a t 1.4.- t mi+ 's t Io the c var 1 et t.cr to e " e n it i lo eit. i t ie,1. 'Il re co.cr l e t t.o r n 1 :.' it re t e At t ra"It-nen t. 1 3. nv i ite<: re titular l i ' i,,t or t he .le ri c ienc i en by cor i;~n. n t. 1e. Tn lil e is l ..f Ihe Til' tor 'll"* en t er.or i en 1.14 I I. A, II.'*. ni l IV. At t nchment ii girov i t - tto r u.elutinn nr encte i t cn. The gen t,an a t t a. h".1 t.. tfr-
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r. o t.e t i..vi 1.u 1. X t.f e e r e it see t re t u i n r l i! ine ..r ,ler i c i arn i e'. 1 At t ach. 70guig w nt On s i i f i er ' i "e n != 1 i c iencier:/ X men t. ItennIntinn ( c:e t.. re r ic I. It., 1I.A, in,1 f.r e i ! I. li ). Tho. e ivet I""r enty lint: riele 1.14.11. A. Anwwwerpg e.
p yJ] Nuclear commeni nosokition Ite.euest 8/A No W G No. [ _. t sua enna.es I ~' ' 8 I" I " ' '7 I' ' ' ^ ' ' ' ' f' lases Tf4,I,-J _ -fe 4.g.... ' I. A. l.c v i, / fl.... :eiy le r /.l. .f. 8 *.. I i ' " I - ; * '- "I' fleww,wr, Date of Cenews.ceits ...... _ _....Conwnant e - -Oeigirietoe Dese of Mesolutani 9 teen flefeeente Arceget ficioct Reesesefor $1.ow As.tual f*ent nsa.1 flewswelwett. Nie. l'anall'ae s Cepewnesse Cewswnent Mejecelese If l'aessel in Is A*'. '4tu re.t i.I ' l'f fil .rform re
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Note change of wording. Walkdowns I.," I of cra c h f.imi t or que-e..t r t'.. r em * !" 1 Were conducted at various occasions. i.n.
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These walkdowns were those which caused conflicts. Grease reliefs have r:1 im triu uns. ni,c,rri I-I ri t i i e n*: sin-been remved from the discussion. m e n t. I,imitorque >g.o rri t.. r. In e.l li t i nte st r ea. ne reIiein hen v" onfy b<" n r" t ' I '* " * " I l ..in en e sisgel e vis i v e: re n-1 re f " t " n"* ozrvnne r Iinfn nhoen l f I* tv i*' t v.I. There in ins re.g u i rconc u t. tfrit e* r ere:. retlefn bn we f.o I.e en v i r..i re ee n '
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F iTlNuclear comment nesolution
- n.,.. 1. n r 3 ficquase S/A No
~ g g.c,,,,,,, l'r e l_ im i sri ry I'r, e t, woNo ~ 1,. t t. r to U n'. Agni 3,g I. A.~ fr v i.u /r1. e:. ':ny.1e r / l. .I. * *o I i ' ' ! - !" MI* lietwee w ce lhete s.f Cenownesets Osigsssatoe fleets flaferente Conwn nte Date of Resolutsoet No. raps /rnes ,.isaw Actual I,sogw.sent flowswafwegg* Accept Hoject nomeo,e for s 4:vwrunneet Conwnent Rejection i., ni i. ri.. pr. .o re r.u i t r he siii 1.
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Changed to June 1984 1 n y.c f.u t ro ' rior...: :n r i l y 1.e f. r. ec+.t u rf. r.r,. %p1ne ine pre :
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., - ru.. . :n 4 i '. n t $_. in ing it:v n n. H i.. p i i r.- ~r r t :.ch 5 n The rules for EQ do not require safety e. r.- n a s i' n t.i c n i t. rn,i.
- p. t h io grade equiprent. Therefore, equipment x
r.rn. I ir " n n r a (ii..t ) nien t i..m. h. c w. " it v in the Turbine Bldg. are acceptable. i.r.l. .' a n.i n n r.- no t. ...pi. : '. ft: 44 Tii. :.. MSV-4's do not have qualified E/P con- ? vn i v. : re r. ,,n c..na...r o r v:.rnon a n.i verters. The MSV-3's have the same G/P
- c..n.t en no r v.r un n.
i: 111: a n.t c,nnot i.- converters but are located in the Tur-r< l i-.i s p. ni. rt:v n r.n ..r. tie titock a bine Blrig. which is a mild environment. vniv"- t o r c..n. i c n n.., t.y ev en i v. : He have found some qualifled E/P con-rt:v u-r rt:v A :.na n... t h.-
- i. s or t va lv.
r..r ft:v'. A n.. a n. verters which will be placed on order (16 wks delivery). 14 n,.. hi,r-e air.; t c, m e, i v. n i nmn i .niy The steam driven pump is not required
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E:v p.i e i n i e... r..ci i i.1 ior t.e n os case conditions (LOCA, MSLB) only 350 f, t i. F.... i m. t.- r pnwn-... i-ot h in-nom is required to cool the core to ,.m p.. nrevent uncovery (See, PUN letters to r NRC dated 3/22/83 & 12/9/83).See C.Pwu i, nti. Tr,r anyrrrtors tri v. e.. c., re pi er. a i y analysis based on Blue Book for 2535 r .c. 4. .:~n..rn s -mic.,na.,ct..r ni-i min r r r.n-M4t Plant. i,,...
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.l. li' ' I i " '"' fieviewee it.ite eif (:en.wnents Osigisseto, Date of flesolution Onenn ens. Isan Isai m m w e Arresis ilejoct Room foe St ow As.tisael I'sog.sesel Ilewenelwigs. Nes. l'esenH*m e (:seeuweiev et Cownwesent Rejectices Il f *sessilele p. At e. Tl.c.. p i.. em i.t n.-le
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Nuclear Mcmcrcndum Environnental Qualification of oate. February 6, 1984 34,et. Electrical Equipment E&L: 5196 From: L. W. Hardin9 Location. Cherry Hill B1dg. Plant Engineering Director - J. J. Colitz To Attached, please find resolutions of coments provided in your meno (3300-B4-022) of January 3, 1984. Pleae be advised that three coments were rejected and were discussed with P. A. Levine and R. O. Barley on 2/6/84. L. W. Harding Senior Licensing.gineer LWH:nt att. cc: C. E. Hartnar - Lead Elect. Eng. TM:-1 P. A. Levine - Eng. Sr. I Tit:-1 Prev. Maint. Mgr. Tit:-1 M. G. Sn. ster F. J. To:le - Ops & fiaint. Director - T!!!-l
- . W. Snf.r. - Tli -l Li:ensing Manager l
l 1 l l c:. : s t
~ l E d]Nuc ear conunent nesolution f t,u.se 3/Afeo___.__ _ __.__._ _ _ g g,,,,,,,,, !,
- i s i s i. e,. 1 set' l
er 'o H P'. W D No ~_ ,,,,,, _ 7pg_g Q A. I, f ie. fit. G. .: s v.I. i f t. e. e '.. l i ' "I flave*,wwe, D.ite..I Conwwwwits Oeignieto, Date of Heustusans Cewownente feeen flefeeene e Act_eget Rolect Homeesefor No. f* age /f*ae a Sloove Ae:tual f*ent.e sn.1 linmwel'"U* Conweent Crwswnent flojecelon if I,mul,la 1
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!. i ne: I se t r elic r al t ** 'tti't.~t. X October 17, 1983 1 tctter ,o
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(?.,ve r letter re fe revie e A '... ament I X xerox problem I l tier ra rs 1 At i n t timerit II. Tlic,tvierInm nt t4 tJie cover 1 **t.t e r n re rio' i *** t s' i t ic l. nie <-over l et f.er n I n" n' e t " A l ' 'ic t'- mesi t I pr<.y i len re ' e l'ie f *: s' ii*diiw* T t It" .le ri c le ne ic. ley c.... g -..e n t f in '.n t e ! " le _ t ref f lee TVlf r,. r Il l ' crit er...r i en I.11. I 1. A, fI.**. e r, l IV. A t. t. re c t emen t. II pr..v i i t" t ie. r. .it u t i <tn i .if erit la l l envi. Tier = ten ezes e t,9 rarlee.1 f.. t 's - ...v. r ] 1et t. r preiv I.le t ti.- r. .. I +. t i.... I.is t y t fiere i < vio 1 n tiss i rer I i:.1 iser ot' .t. r i ei e ne i"r.. i i At t ve rfi E.pii ge nt, Qu i l i t' i "e t i. vi Ib t i c ivoie le<./ X ment 4"nol ut i<en ( f ?'e t cit..r i": 1.P., ! I. 4, ran I l ' i r. " 1 II.P). Tlie over 1.er ore l y 1 i ;t.: Tit le
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7 J JNuclear comment nosolution [, g ,.,,,...,,,, 3 Itce tuou B/A No lion;innesis I " I I'" i na ry Da n g t. I, t. t er to IW N,. W O.No ~ Ploeit _TM.I k 4, g I. A. l. i n. /fl. <:..;ny.I. r f.l. .I. r.. I i ' of-;'L h.. fle vie w ete llate of Coenert er.*s Osiginator Date of ILrsolu6iosa Cosensitesile liessi .leference Accept Ileject floosoft for Sloow Actual I'solicisant flowentling
- No.
l'auell'as e. Connunnt Comment Rejectioet if l'ossilolo 1 ,u t.. mi. n.i i.i <:1.i rN yerform pinnt w:i l lo low n X Note change of wordino. Walkdowns n P it e I of ersch I.im i t.oregue ine.t. i r f..e m. l. l were conducted at various occasione, i. A. nn.1 nerial number rin.1 i. i'. i ernm en t.r.t ? These walkdowns were those which caused conflicts. Grease reliefs have 4 ii in e.nt in_ been removed from the discussion. .:imu h,r
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meri. f.i m i t.oregiae ope rit ' n" lo nilil i t. I on t pir ea ne r e l i e f r. hu va..n l y t i. e n r p l rice.1 couple vre I v e r :e nal r f c e ene. i . iti n g;re:i::e relse f':. niu n: 1 1 h. e t e l e t...t. There i. no rea pt i t'emosi.
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. gun I i ri e.l. 5 A t. t.. leirw l : 4 t-t:1. l* nii.pi l.1 t o. f t;!.it. x Pry e l'o rn. I. A. ls. l (> ii t. t.. 1.i ne i: ntnut1 I ha v e "t.." i r e:a r t e.1 he t.w..:n re.gu i re.1 a nel Ie. x 199.e hern. !.B.I l I 7 A i t..
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[' L)] Nuclear comment nosolution l'ri s,e - 3 or 5 It guest 9/A f fo _ ____ E. __ _ _ _ _. W O reo _ _ I _. g ioc,,,,,,,,, l'r"I in i sin ry I 'm l Ie't"r 'o illT %,3 _ TMI-1 p, A. l..uiii../It. t;. ';ny ler/.8 .l. olit. " I 14 D' floven we, Date of Caniimenta Originato, Date of flusolusso Conni.ents ft n llelesence Accept fleject fleeson for Show Actual I*ent.osnil I?ewoulina. No. I* anon'as e. Coenmens Comment Rejection 18 l'osselein 8 Att..
- 1. i ne 4:
A"CO.:o l o n, s i e t s ha v. og l'""" Chanced wording to show conoletion by x 1 is,e r e p l a r".1 wi t.h qim l i l'i e.! A :!' '. l etio i el:;. ,]Une 84. I '+i rn. 1. 11 ') A t. t.. I.i ne h a nel *. : Men 1 8 Lit i vu. i ep l:* cemen t. Deleted. x I riay is not. prirt. o f' th" comt.nt rire1 msint-1. 14 e nti nc e prosern m. Th ' r. ir en. rerps i re-ment. t ha t,
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Tfi. ' h 'lN n h o o t.- for INVl/B V ( "< h ) ; lWV16H (::V (&Is ) ; FWV1 f B (;;V l &;') ; ;V/f t:VI ( A; 'l V/ t*M V 1 4 0 s t.rt t.e f.hro ' Ihr A " f ' ::o l en o i si vri l v e r, ra re igua l i f i".1 f'o r is ' ' yenrn. The Com ponen t. f ti '.c r i n 1 : i:vre I uit f. i on "heet: elo n o t. Iint
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' I(i ns, rt n n no l en > i el vri l y, c.m p..n" n t. In A t t.. I.i tie 1 :
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x l' i #*f t.e :1 i ne. ! ', rit. !. I'. l. a 11 A't. I.i ne '- Hrt lirt ion ti't' i t e r If f t-A-i :. f RM/\\-2 is required durinn a LOCA. The x n .,,e l oca t e.1 in t.he i n t " r ene 1 i i t - Intermediate Bldg is a harsh environ-l'i rn. H 1 1,. "IevnfIon " ' '. '. I '~ r rIin.' t ment for a steamlIne break. For the i. n. i t.h i :
- 1. "a t. i nn i-n..I i i 1. t envir""-
accident of interest it is in a mild enyironnent. mnnuuss e e.
1 ~ J ] Nuclear comment nesolution p g "'" I"" 5 ' 8/A Ho W O No ut t.o N i,.. Document l'8 ' ' I i M i ".ry, lirri af Ict.t er rge,,e TMI-1 Q-.. Irv'nc/fl. G. 'Inyil e r /.l. ColiI i'l - to Mf8 P. A.~ i Itoviewes Datn of Cununes 's Originatos Date of flesolution Cosnmente liesn 'lef es esace Arcs pt Heject Reesort for g p, No. Page/Pasa ~ Conunent Comment Rejectiosi Changed to June 1984 in At t. The pre nura nw i t ch.- uill t,
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l 'a r.e i bu 1. ruit n ec"<,nn r i 1 y befor" e. u t.n r !. lie rn. Itep l a c i u r, pre:.nia r" n u i t.. '.": it not n I.M.I. re n t.n r t comm i t. men t. n,pl we nn u l.1 ru i t. tie m.ek i tir new commi I m. it t. : I ir t* . t n r t.. 1i A t t.. lining, rtly ? nrnt 8 in p i n e. of rt:Vs i :. The rules for EQ do not require safety I r: ire : not n nu i t nni e ai ern:i. en t h i., x grade equipment. Therefore,equioment l'n rn. l i c o n n e.1 ( bot. ) nt ni t.. low n bec inn. rt:v in the Turbine Bldg. are acceptable, i.e.l. P an.i n nre not. c. pre i i.,, rt v'. Tnene MSV-4's do not have qualified E/P con- ? vnive : rriy on con.irnnor vnenum nn.i verters. The MSV-3's have the same G/P Con.lannor vacuun i: H I T: rool ca n no t. bo Converters but are located in the Tur-re I i a<! u pon. f t
- V H A'.H n r o Ihe block bine BldQ. which is a mild environment.
vnivon ror con <ienn r byen: v,1 v e: He have found some qualified E/P con-rt:v u - v tt:v PA nn.1 h n re i. h-biork verters which will be olaced on order valven ro r r-t;V s A n n.1 H. (l6 wks delivery). i 11 A v. t..
- 1. i n-4: The nt.am.i r i v..n pomt i-oniy The steam driven Dumo is not required en r..-
t require.1 ror :. t.n t. i on i. h. c k on i i :, not. n x except for Station Blackout (vs loss r i rn. va i i.i o.n f.en-n t.. The ; t ,m .iriven of offsite Power) because under worst i. <:. i. Eiv pump ir,nino r..p i. ~ i ior ion of case conditions (LOCA, MSLB) only 3s0 n,,t.n y r.iun t. r pump: ..r i., ..t le uc gom is required to cool the core to orevent uncovery (See GPUN letters to pu m p.:. NRC dated 3/22/83 & 12/9/83).See C.Pwu i-ne.. Tne i n v re, .,r. nn v.
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ny analysis based on Blue Book for 2535 c,,... n cen rni :rm i e.,n.nic i.., ni.r..i,r Tran_ MWt Plant. ( en...: orn. ). e i r:.
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