ML20128G898
| ML20128G898 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/23/1984 |
| From: | Patch R, Walz V POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20128G886 | List: |
| References | |
| EDP-12, NUDOCS 8507090350 | |
| Download: ML20128G898 (21) | |
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l ATTACHMENT 2 TO JPN-85-55 Enaineerina Desian Procedure 12 Procedure for Establishina cuality Assurance Cateaorv Classification New York Power Authority l
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 3
l P
r NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TIILE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS b/.
k b/
DATE: 8 8Y APPROVED BY:
IECHNICAL~SEHVfCES'SUPI.
ketasl k
DATE: f/.Z3/ff CONCURRED BY:
QUALIlY ASSURANCE SUPI.
APPROVED BY:
f m/ _
DATE:
2J fy R E~S p)E N I MANAGER Page No.: 1 2
3 4
5 6
7 8
9 10 Rev. No.: 1 1
1 1
1 1
1 1
1 1
Page No.: 11 12 13 14 15 16 17 18 19 20 Rev. No.:
1 1
1 1
1 1
1 1
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1 Q) _a _a 3
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Rev. No.
1 1
Onto 8/23/84 Page 1
of 20 t
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS 1.0 PURPOSE 1.1 The purpose of this engineeri*g and design procedure is n
to provide instructions and guidance for establishing the quality assurance category classification of plant structures, systems and equipment.
l 1.2 This procedure shall be used for establishing the quality assurance category classifications for new structures, systems and equipment added by plant modifications, if the classification was not clearly established by the modification process.
1.3 This procedure shall be used for re-establishing the quality assurance classification for existing struc-tures, systems and equipment when it is determined that there is a need to do so or if the quality assurance classification was not previously established.
l 1.4 This procedure provides instructions and guidance fo r establishing the environmental sub-category (harsh or mild environment) fo r safety-related electrical equipment for the purpose of establishing electric l
equipment qualification requirements.
2.0 REFERENCES
2.1 ANSI N45.2-1974, Quality Assurance Requirements for the l
Design of Nuclear Plants 2.2 WACP 10.1.6, Control of Hodifications, Component Changes, and Safety and Environmental Impact Evaluation i
Reports 2.3 JAFNPP Final Safety Analysis Report, Section 12.2
-Classification of Structures and Equipment 2.4 Code of Federal Regulations, 10CFR50, Appendix A
'2. 5 JAF Engineering and Design Procedure EDP-3 Design l
Verification Procedure l
2.6 Authority Quality Assurance Procedure QAP 2.1 -Quality Assurance Program Scope 2.7 JAF Plant Standing Order (PS0) No. 32 Component Quality Assurance Category Requests Rev. No.
1 Date 8/23/84 Page 2
of 20
NEW YORK POWER AUTHORITY JAMES A.
FliZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS 2.8 10CFR50.49 - Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants 2.9 10CFR50, Appendix A General Design Criteria for Nuclear Power Plants.
2.10 10CFR50, Appendix B Quality Assurance Criteria for Nuclear Power Plants and Fuel Processing Plants.
3.0 DEFINITIONS 3.1 Quality Assurance Classification A classification
[
ievel assigned for quality assurance purposes to plant structures, systems, and equipment.
The assigned level is commensurate with the importance of the structure, system, or component in performing its specific design function as it relates to plant operations.
3.2 Quality Assurance Category I The quality assurance
[
classification for plant
- systems, or portions of systems, structures, and equipment whose failure or malfunction could cause a release of radioactivity that would endanger public safety.
This category also includes equipment which is vital to a safe shutdown of the plant and the removal of decay and sensible heat, or equipment which is necessary to mitigate conse-quences to the public of a postulated accident.
l The above definition should be interpreted to mean those structures, systems, and equipment that:
1.
Are necessary to assure the integrity of the reactor coolant pressure boundary.
2.
Are necessary to assure the capability to shutdown the reactor and maintain it in a safe shutdown condition.
3.
Are necessary to assure the capability to prevent or mitigate the consequences of accidents which could result in potential off-site exposures comparable to the guidelines exposures of 10CFR100.
Rev. No.
1 Date 8/23/84 Page 3
of 20 s..... -
1
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS 4.
Contain or may contain radioactive material and whose failure would result in conservatively calculated potential off-site doses which are more than 0.5 rem to the whole body or its equivalent to any part of the body.
For this classification the applicable criteria of 10CFR50, Appendix B should be applied.
3.3 Quality Assurance Category M The quality assurance classification for plant
- systems, or portions of systems, structures, and equipment which do not fall within the definition of QA Category I but do perform a function which may have some importance to safety with I
respect to any design criteria.
l For this classification selected criteria of 10CFR50, l
Appendix B shall be applied.
{
3.4 Quality Assurance Category II - The quality assurance l
classification for plant systems or portions of systems, structures, and equipment which are essential 3
for the reliable generation of electric power (failures would result in the loss of electrical power generation in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or less) but which are not essential for a safe shutdown.
Failure of this equipment could result in loss of power generation but would not endanger public safety., Equipment and systems which contain radioactive materials but whose failure could not release quantities sufficient to prejudice public safety are included in this category.
3.5 Quality Assurance Category III The quality assurance l
classification for plant
- systems, or portions of
- systems, structures, and equipment which are not essential fo r the reliable generation of electrical power and which do not contain radioactive material or whose failure could not result in the release of radioactive material.
Rev. No.
1 Date 8/23/84 Page 4
of 20
NEW YORK POWER AUTHORITY JAMES A.
FliZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS 3.6 Quality Assurance Sub-Category I (EH) - This sub-cate-gory of Q. A., Category I contains safety-related and post-accident monitoring electrical equipment required to remain functional during and following design basis events and which could directly experience harsh environmental conditions postulated to be caused by these events.
These environmental conditions could include temperature, pressure, humidity, radiation, synergisms submergence, spray impingement, and aging affects.
Environmental qualification per 10CFR50.49 (ref. 2.8) applies to this equipment.
3.7 Quality Assurance Sub-Category I (EM)
This sub-cate-gory of Q.A.
Category I contains safety-related and post-accident monitoring electrical equipment required to remain functional during and following design basis events and are located in mild environment locations. A mild environment is an environment that would at no time be significantly more severe than the environment that would occur during normal plant operation, including anticipated operational occurrences.
4.0 RESPONSIBILITIES 4.1 Technical Services Department - Plant engineers and supervisor engineers in this department are responsible for performing classifications or re-classifications of quality assurance categories in accordance with this procedure.
Knowledgeable personnel in other depart-ments may be called on to perform the classification or perform the verification aspect o f this procedure.
4.2 Quality Assurance Department - This department reviews classification evaluations and provides concurrence by signing the " Request for Classification Form" (Enclo-sure 1).
l Rev. No.
1 Date 8/23/84 Page 5
of 20 E
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE F'OR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS 5.0 PROCEDURE 5.1 Perform the quality assurance classification evaluation using the Enclosure 2 form titled: " Quality Assurance Classification Evaluation".
5.2 In performing the evaluai. ton, utilize the following design inputs as applicable.
5.2.1 James A.
FitzPatrick Nuclear Power Plant Final Safety Analysis Report 5.2.2 Code of Federal Regulations, 10CFR50 5.2.3 JAFNPP Controlled Plant Drawings 5.2.4 JAFNPP Operating Procedures and Emergency Operating Procedures 5.2.5 Plant and System Design Bases and Analyses available from the Architect-Engineer and NSSS Vendor 5.2.6 Applicable Regulatory Guide to which the Authority is committed 5.2.7 NUREG-0800 Standard Review Plan Sections 17.1 and 17.2 5.2.8 JAFNPP System Descriptions 5.2.9 Regulatory Guide 1.97, Rev. 2 -Instrumenta-tion for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environmental Conditions During and Following an Accident.
5.3 Establish the design function of the item being evaluated, and evaluate the performance of this function as it relates to the safety-related functions stated on the Enclosure 2 form.
Rev. No.
1 Date 8/23/84 Page 6
of 20 L
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT
' ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS 5.4 Perform an in-depth review of the equipment function to establish quality assurance classification.
When performing this classification, it must be realized that the original plant design classified entire systems with minimal evaluation of the actual function performed by individual components.
This approach is substantiated by the overall system classifications contained in the JAFNPP FSAR, Section 12.2.
5.5 Perform an evaluation to establish the quality assur-ance environmental sub-category for Q.A.
Category I safety-related and post-accident monitoring electrical equipment.
For harsh environment electrical equipment, establish the particular postulated design basis events for which the equipment must remain operational.
Establish the environment sub-category as I (EH) or I (EM).
5.6 Following completion of the Enclosure 2 evaluation form, sign the form including name, title and date.
5.7 Obtain a design verification of the evaluation in accordance with the requirements of reference 2.5 with the following exceptions:
5.7.1 The method of verification in all cases is the " Design Review" method.
5.7.2 A satis factory design verification shall be documented by signing in the space provided on the Enclosure 2 form.
No other forms or signatures are necessary.
5.8 Following completion of the verification, obtain the approval of the Technical Services Superintendent or his designee.
This approval is indicated by signing in the space provided on the Enclosure 2 form.
5.9 The evaluator and the Technical Services Superintendent (or designee) shall state the established category on the Enclosure 1 form and provide the required signa-tures.
5.10 Complete the Enclosure 3 memorandum to the Quality Assurance Superintendent.
Attach a copy of the completed Enclosure 1 and 2 forms and forward to the addressee and indicated distribution.
Rev. No.
1 Date 8/23/84 Page 7
of 20
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w
6 NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS 6.0 ENCLOSURES 6.1 - Request for Component Quality Assurance Category Classification 6.2 - Quality Assurance Classification Evalua-tion 6.3 - Forwarding Memorandum Rev. No.-
1 Date' 8/23/84 Page 8
of 20 m
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 1 NE W YORK POWER AUTHORITY JAMES A.
r!T2 PATRICK NUCLEAR P0wCR PLANT RE00EST FOR COMPONENT QUALITY ASSURANCE CATEGORY CLAS$1r! Call 0N SYSTEM COMPONENT NO:
OESCRIPIION:
PRESENT OA CATEGORY:
REASON FOR REQUEST:
REQUESTED BY:
Sagnature Date FOR ICCHNICAL SERVICES DEPARTMEN1 USE The above request has been reviewed and the Quality Assurance Category dttermined to be Category EVALUATED BY:
Sagnature Date APPROVED BY:
Sagnature Date CONCURRENCE:
QA Superantencent Date PORC REVIEW:
Resadent Manager Meetang Number Date Copy sent to Requestor:
Date Revised List Issued:
Unte Rev. No.
1 Date
-8/23/84 Page 9
of 20 t-
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 2 QUALITY ASSURANCE CLASStrtCalION EVALUATION 1.
! TEM DESCRIPTION (as applicable) 1.1 Structure Name 1.2 System Number:
1.3 System Name:
1.4 Component 1.D. No:
1.5 Component Name:
1.6 Reference Dwg, No ITEM TUNCTION (describe in detail the design function of the item) 111. SATETY-RELATED FUNCT10N EVALUATION (Check the correct response or indicate Not Applicable - NA)
If en ites-meets one or more criteria contained in this section it should be classified as QA Category 1 unless sound reasons to the contrary are stated in Step !!!.30.
l YES NO NA III.1 Does the item function to assure the integrity of the reactor coolent pressure boundary?
111.2 Does this item function to assure the capability to shutdown the reactor and maintain it in a safe shutdown condatlon?
Rev. No.
1 Date 8/23/84 Page 10 of 20 j
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 2 (Continued)
YES NO NA
!!!.3 Does this item function to assure the capability to prevent or mitigate the consequences of accidents which Could result in potential o f f-site radiation exposures comparable to the guideline exposure's of 10CFR1007
!!I.4 Does this item contain or may contain radioactive material whose failure would result in conservatively calculated potential off-site doses which are more than 0.5 rem to the whole body or its equivalent to any part of the body?
111.5 Does tnis item function to prevent the consequences of accidents postulated in the JATNPP FSAR?
!!!.6 Does this item function to mitigate the consequences of accidents postulated in the JAFNPP FSAR?
111.7 Does this item perform the function of missile, pipe whip, flood protection for safety-or related equipment (CDC 4)?
!!!.8 Does this item function to assure that specified neceptable fuel design limits are not exceeded for analyzed normal and abnormal operating conditions (CDC 12)?
!!!.9 Does this item function to control reactor operating parameters (CDC 12)?
!!!.10 Does this item function to provide instrumentation of a monitored variable for control or indication for those variables and systems that affect the following (CDC 13):
1 Fission Process?
2.
Reactor Core Integrity?
Rev. No.
1 Date 8/23/84 Page 11 of 20 i
y NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES IITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CAIEGORY CLASSIFICATIONS ENCLOSURE 2 (Continued) f YES NO NA 3.
Reactor Coolant Boundary?
4 Containment Integrity?
5.
Core Cooling?
III.11 Does this item func* tion as a pressure boundary in any of the following applications:
1 Reactor Coolant Pressure Boundary?
2.
ECCS System Pressure Boundary?
3.
Primary Containment Pressure Boundary?
~
(CDC 14, 30, 31)
!!!.12 Does this item function es part of the primary containment (CDC 16)? _ _ _
111.13 Does this item function as part of the plant's emergency electric power syster (CDt 17)?
!!!.14 Does this item function as part of the Control Room boundary (GDC 19)? _ _ _
l 111.15 Does this item function as part of the protection system designed to initiate automatic shutdown of the reactor (CDC 20)?
III.16 Does this item function es part of a reactivity control system (CDC 26, 27)?
'111.17 Does this item function as or a part of a residual decay heat removal system designed to remove heet from the reactor core such that fuel design limits or pressure boundary design conditions are not exceeded (CDC 34)?
!!!.18 Does this item function es part of an emergency core cooling system (CDC 35)?
Ill.19 Does this item function to provide containment heet removal (CDC 38)?
Rev. No.
1 Date 8/23/84 Page 12 of 20 1
w.
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALIIY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 2 (Continued)
YES NO NA
!!!.20 Does this item function to provide ~ containment atmosphere cleanup (CDC 41)?
111.21 Does this item function to provide cooling water to transfer heat f rom *s a fe t y.
related structures, systems, and components under normal and accident conditions (CDC 44)?
!!!.22 Does this item function to provide reactor boundary isolation (CDC 55)?
111.23 Does this item function to provide primary containment isolation (CDC 55, 56, 57)?
!!!.24 Does this item runction to provide.for the control of releases of radioactive
. materials to the environ-ment (CDC 60)?
!!!.25 Does this item function to provide storage and the prevention of criticalit y of fuel storage and handling systems (CDC 61, 62)
!!!.26 Does this item function to provide monitoring of fuel and waste storage systems to detect conditions that may result in loss of residual heat removal capability or excessive radiation levels (CDC 63)?
!!I.27 Does this item function to monitor the reactor containment atmosphere, spaces containing components for recirculation of LOCA fluids, effluent discharge paths, and the plant environs for radio-activity from normal operations, anticipated operational occurrences, and postulated accidents (CDC 64)?
I!!.28 Could the failure of this item in any way degrade the performance of any other safety system?
Rev. No.
1 Date 8/23/84 Page 13 of 20 L
NEW YORK POWER. AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR-ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 2 (Continued)
If yes, provide explanations Yt$ NO N4 111.29 Is this item a part of an instrumentation system used by the V
Control Room operator to assess plant and environs conditions during and following postulated design basis events?
Use Regulatory Guide 1.97, Rev. 2 for guidance for establishing the appropriate quality assurance cl a s si fic a t i on. For items not included in Reg. Guide 1.97, re-view the instruments design and safety basis as defined in the f5AR.
Provide justification in Ill.30 if not classifying as 04 Category 1.
111.30 If the item under evaluation meets any criterra in this section,'it should normally be classified as QA Category 1.
If there are sound reasons to the contrary (i.e., approved licensing bases, approved plant design criteria, or NRC approval) provide the justification in the space below along with the recommended alternate QA Category recommendation.
Rev. No.
1 Date 8/23/84 Page 14 of 20 2
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 2 (Continued)
YES NO NA IV.
IMPORTANT TO SAFETY FUNCTION CVALUATION (CAI. M)
IV.1 Does this item functio'n to provide fire protection, which minimizes consistent with other safety requirements, the probability and effects o,f fires and explosions (CDC 3)?
NOTE:
The diesel and elect ric fire pumps are 0. A.
Category.I and are ng to be classified under this criteria.
IV.2 Does the item provide some function of possible importance to sa fet y but does $ directly meet the safety-related criteria defined in Section
!!! above?
provide explanation
- If the item under evaluation meets the above criteria, it should be classified as CA Category M.
V.
NON-5ArETY FUNCTION EVALUAi!ON (CA CAT. 11 09 III)
V.1 If the item does not meet QA Category I or M criteria and considering the definitions of QA Category 11 and Ill, state the correct classification for the item under consideration and a justification.
QA Category II/III (Circle One)
V.2 Justifications i
Rev. No.
1 Date 8/23/84 Page 15 of 20 l
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES
.l
/
TITLE:
. PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-'12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 2 (Continued)
VI.
E V AL UAi!ON Of THE CENERIC apPt!CA8IL!iY Of INE CLA551 FICA 110N RE QUE SI Review the generic applicability of the subject classifica-tions request per the following:
YES NO NA VI.1 Are there similar or associated
- ~
~
com-ponents which have been ident i fied during this evaluation "which are presently not classified in the QA Category List?
VI.2 Does the subject evaluation and established qualitv assurance category indicate a need to review existing 04 Category classifications for similar plant components for the purpose of reclassirication?
VI.3 If the response is YES to either VI.1 or VI.2 include these other components which have been adentified in this evaluation or prepare en additional classification request.
List the additional components identified by this review which require classification or re-classification:
Indicate whether these components are included in this evaluation or if an additional classification request has been prepared (Check One) lhis evaluation New classification request VII. Q.A. CATECORY I - ENVIRONMENTAL SUB-CATECORIZATION Vll.1 Complete the following for the equipment and componenta under evaluations Evaluated QA Category a.
(Circle One)
I 11 111 M
Rev. No.
1
-Date 8/23/84 Page 16 of 20 D
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 2 (Continued) b.
Is the equipment or components under evalua.
tion electrical in nature or include electri-cal components (i.e. electro-mechanical, electro-pneumatic).
(Circle One)
YES/NO If the Q.A. Category is 1 and the answer to VII.1.b is YES, pr,oceed to VII.2.
If NO, proceed to Section VI!!.
Yll.2 State location of equipment or components, including building and e l e v a t i o'n.
Building Elevation VII.)
Determine which of the following design basis events for which the subject safety-related equipment items must remain functional in order to perform its intended safety function and safety design basis:
AREAS ArrECTED YES NO 1
Primary Con.
PC and RB tainment (PC)
LOCA (Small cr targe) 2.
Primary Con.
RCIC Steam RB Line Break (HCLB) 4 HPCl Steam RB Line Break (NELB) 5.
RWCU System RB Line Break (HELB) 6.
Main Steam TB Line Break Steam Tunnel V11.4 If the subject Q.A. Category I electrical equipment must perform its intended safety function in a postulated harsh accident environment, establish its environmental sub-category as 1 (EH).
If the subject Q.A. Category I electrical equipment performs its intended safety function in a mild environment, establish its environmental sub-category as I (EM).
I Rev. No.
1
'Date 8/23/84 Page 17 of 20 J
- s
's NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING'AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 2 (Continued)
Circle the evaluated environmental sub-category:
1 (EH)
I (EM)
Discussion:
v 111. -
EVAtuATION/5UMMARY v!!!.1 EV ALUATED QA CATEGORY (Circle One)
I M
Vllt.2 QA CAI. I CNV. SUB-CAIEGORY (Circle One) 1 (EM) 1 (CM)
N/A' v!!!.3
SUMMARY
Or EVALUATION (state briefly the significant evaluation criteria which establishes category) lx.
OEstcN INPUTS UTitIZED 1.
2.
[
).
4 5.
Rev. No.
1 Date 8/23/84 Page 18 of 20 m
NEW YORK POWER AUTHORITY JAMES A.
FIIZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES TITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 2 (Continued) 1 CVALUAi!ON VERtrtCA!!ON AND APPROVAL 1.
Evaluated by:
Tit 1es 4-Date:
2.
Verified by:
(Design Review)
Title:
Date
).
Approved by:
Techntcal Services Supt. lor cesignee)
Dates Rev. No.
1 Date 8/23/84 Page 19 of 20 LJ
a l
NEW YORK. POWER AUTHORITY i
JAMES A.
FITZPATRICK NUCLEAR POWER PLANT ENGINEERING AND DESIGN PORCEDURES fITLE:
PROCEDURE FOR ESTABLISHING QUALITY PROC. NO.: EDP-12 ASSURANCE CATEGORY CLASSIFICATIONS ENCLOSURE 3 t
MEMORANDUM 10: QUALITY ASSURANCE SUPERINTENDENI TROM:
IECHNICAL SERV!CES SUPERINTENDENT SUPERINTENDENT Of POWER V!As SU8]ECI:
00AL!tY ASSURANCE CafEGORY REQUESTS COMPLETED EVALUAll0NS F0s CONEunRENCE References (a) jar Plant Standing Order P50 No. 32 -
Component Quality Assurance Requests 1
The completed quality assurance category evaluations for the in accordance following listed items have been completed with reference (a) and are forwarded for your concurrence:
a.
b.
C.
d.
e.
I.
g.
h.
shall be addressed Questions relating to these evaluationsindividual evaluations.
2.
the to the engineer who prepared SERvlCES SUPERINTENUENT TECHNICAL CC: Responstole Engineer DC Supervisor Document Control Center tav. No.
3
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