ML20008D757
| ML20008D757 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 01/13/1969 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20008D758 | List: |
| References | |
| NUDOCS 8007300629 | |
| Download: ML20008D757 (76) | |
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APPEITDEC 13 m
'9 QUALITY ASSURANCE PROGRAM V
TABLE CF CONTENTS Section Face 1
GBJECTIVES A:!D DEFI:iITICNS 13-1 l
1.1 OBJECTIVES 13-1 l
1.2 DEFINITIONS 13-1 1.2.1 QUALITY CONTROL 1B-1 1.2.2 QUALITY ASSURANCE IB-1 1.3 ORGANIZATION AND ADMINISTRATION 1B-1 1.3.1 PRIOR TO INITIAL FUEL LOADING - CP CO 13-1 1.3.2 3ECH 2L CORPORATION 13 h 1.3.3 3&W QUALE'Y ASSURANCE PROGRAM 1B-5
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1.3.3.1 Introdaction 13-5
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1.3.3.2 Program Elements 1B-5 1.3.k CONSIAIERS POWER COMPANY ORGANIZATION DURING AND AFTER INITIAL FUEL LOADING 1B-lh 1.h IMPLEMDITATION OF CP CO QUALITY ASSURANCE PROGRAM FROM DESIGN THROUGH CONSTRUCTICN 13-17 1.h.1 DESIGN 13-17 1.h.2 PROCUREMENT 1B-17 1.h.3 MANUFACTURING 13-18
'l.h.h CLEARING, SHIPPING AND STORAGE 13-18 1.h.5 CONSTPUCTION OF THE PLANT 1B-18
^1. k.'5.1 Civil Construction Scope of Work 1B-18 1.h.5.2 Mechanical Construction Scepe of Work 1B-19 Q(m
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1.h.5.3 Electrical Construction Scoce of Work 13-19 s
1.5 PREOPERATIONAL TESTING
' 13-20 13-1 Amendment No. k n ww
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APPENDIX 1B i
f LIST OF FIGURES j
Figure No.
Title Pm f
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l l-1 B8N Power Generation Division 1B-7 25 l-2 B8N-NPGD Quality Assurance 1B 8 1-3 Bulk Power Supply Organization Chart 1B-13 1k Consumers Power Company Organization - Design Through Construction 1B-16 4
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4 4'..t; 00J.83 1B-iv Amendment N. 25 l
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APPENDIX 1B
-(D k.j QUALITY ASSURANCE PROGRAM Subject to those effectivity dates shown in Section II below, the Midland Project Quality Assurance Program will comply with the requirements of the following documents:
1.
For Consumers Power Activities:
The Consumers Power Ccmpany Quality Assurance Program Manual (Topical Report No. CPC-1A Revision 5) 2.
For Bechtel (Architect-Engineer, Constructor) Activities; Bechtel Quality Assurance Program for Nuclear Power Plants (Topical) Report No. BQ-TOP-1, Revision lA) 3.
For Babcock and Wilcox (Nuclear Steam Supply System Supplier)
Activities; B&W N.P.G.D. Quality Assurance Program for Nuclear Equipment (Topical Report No. BAW-10096A, Revision 3)
This compliance is subject to the following alternatives,
>/"'N.
Interpretations, and exceptions:
i I
BECHTEL ALTERNATIVES AND INTERPRETATIONS Note:
Unless specifically noted otherwise all organizations, groups, and personnel discussed in thisSection I are Bechtel organizations, groups, and personnel.
The following alternatives and interpretations apply to the implementa-tion of the Bechtel QA Topical Report (BP-TOP-1):
A.
Construction Work Procedures
.The Bechtel Quality Assurance Topical (Section 1.5.4, page 12, paragraph 1) requires that " Construction Managers are responsible for the management and technical direction of assigned projects, and for assuring that construction projects are provided with appropriate personnel, and are following prescribed division practices and procedures for conduct of construction activities.
Chief Construction Engineers are responsible for providing division standard work procedures to the projects".
The Topical (Section 1.5.2, page 11, subparagraph 3) further requires.that the Quality Assurance Manager be responsible for " Approving quality related procedures and manuals prepared by departments and projects within his division for conformance to quality assurance policies".
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7 t(-
00184 1B-1 Amendment No. 36 12/77
In lieu of this require =ent the Bechtel Midland Quality Assurance
_/~~N Pcogram requires that Construction personnel perform their quality
( )
program related functions using either division standard work procedures prepared by Construction Engineering or project work procedures prepared by Project Field Engineerine personnal.
The final decision on which to use rests with the Project Field Engineer.
All quality program related procedures used by Construction personnel are approved by Project Quality Assurance.
Project Field Engineering has already prepared and is in the process of preparing approximately 75% of the required construction work procedures. Many of these work procedures were prepared prior to the existence and issue of procedures issued by the Division Chief Construction Engineer.
B.
Review of Quality Control Instructions The Bechtel Quality Assurance Topical (Section 1.6.1, page 14, subparagraph 13) requires that Project Quality Assurance " Review, prior to use.... Quality Control Instructions..."
In liew of - this requirement the Consumers Power Company Quality Assurance Topical Report requires that all Quality Control Instructions be reviewed and approved by Consumers Power Company Quality Assurance prior to use.
This review implements the commitments for review described in Section 1.6.ltsubparagraph 13 of the Bechtel Quality Assurance Topical.
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The Bechtel Midland Quality Assurance Program also requires that this activity be audited by the Project Quality Assurance Enginrcr.
C.
. Titles _
In the following cases, Midland Project organizations and personnel have titles differing from those in Bechtel Quality Assurance Topical Report but the responsibilities are the same.
Bechtel Quality Assurance Topical Report Midland Prcject
_ Title
- Title, Materials, Fabrication and Quality Materials aad Quality Services Control Services Department Department Field Construction Manager Project Superintendent Project Cons.truction Quality Control Pro. ject Field Quality Control Engineer Engineer Field Contracts Administrator Field Subcontracts Administrator
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Division Chief Engineer Cognizant Chief Engineer x/
m 00185 1B-2 Amendment No. 36 12/77
APPEIDIX 13 V
LIST OF TABLES Table No.
Title Pace 1-1 Frefuelin-Test Prc~re:
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1-2 Engineered Safeguards Test Prcgr3:
13-22 V
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003.96 13-111 Amendment No. k
D.
Supplemental Interpretations of Regulatory Guide 1.37-3/16/73 (ANSI N45.2.1-1973)
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Section 4 (Pre-Installation cleanliness) of ANSI N45.2.1 states " Items should not be delivered to the point of installation site sooner than necessary unless the installed location is considered a better storage area".
In lieu of this requirement items might, in some cases, be delivered to the installation site sooner than necessary at the direction of the Project Field Engineer and will be protected in accordance with Section 5 of ANSI N45.2.1.
E.
Supplemental Alternates and Interpretation of Regulatory Guide 1.38 -3/16/73 (ANSI N45.2.2-1972)
The following alternates and interpretation apply to ANSI N45.2.2:
1)
Section 2.7 Classification of Itens.
The listings in paragraph 2.7.1 through 2.7.4 will be used as a guide in determining the categorizing of items under levels A through D for the project.
Categorization differing from Section 2.7 will be considered acceptable provided that no degradation in commodity quality is assured.
As in the case of electric motors, exterior pumps, and exterior valves, which are designed for outside service and could possibly be stored in areas other than those in which they are designated, l.e. outside service electric motors shown in
.. A)
Level B could possibly b3 placed ln.a. Level C.aren.
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The same would apply to exterior pumps and valves shown in Level C which could possibly be placed in a Level D area.
In all cases however, the classifications shown in ANSI N45.2.2 will be reviewed and considered by field engineering.
2)
Section 2.7.4 Level D Classification.
The last sentence 1st.
paragraph is interpreted to read "These items require protection against the elements, airborne contamination, and physical damage as necessary and commensurate with the ultimate use of the item".
This determination is made by Field Engineering in accordance with Project prepared and Project Quality Assurance approved procesures.
3)
. Section 6.2.2 Cleanliness and Housekeeping Practices in Storage Areas. Detrimental soil is defined as material or items which could degrade the stored material.
F.
Supplemental Alternates to Regulatory Guide 1.39-3/16/73 (ANSI N45.2.3-1973) 1)
Section 2.1 Planning.
The Project will use four cleanliness zones instead of the five zones listed in this paragraph.
These zones will provide th: necessary clennliness.and will g-'g provide'less confusion '.n the field.
The requirements of N
13-3 003cS7 Amendment No. 36 12/77 1
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zones I and II in the standard will be included in Zones A and
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B of the field procedure. The requirements of Zone III of the
/t standard will be covered by including these items into Zone B or upgrading Zone C for :he particular items.
Zone IV will be included in Zone C except the restrictions on tobacco or eating is not required. This zone can be upgraded to include these restrictions for particular items if necessary.
Zone V will be incorporated into Zones C or D as required.
Note:
Zone C provides no restriction except that the areas will be maintained free of detrimental scrap materials and will be swept regularly.
Protective coverings will be utilized in work areas to minimize grease and oil spillage on finished surface.
Zone D areas will be heavy construction areas without cleanliness restrictions and will be upgraded to Zone C when the heavy construction is completed.
Restriction List Zones A
B C
D Clothing changes Yes No No No Clean gloves, shoe covers, Yes Yes No No head covering Filtered air Yes No No No
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m Material precleaning
~Yec No
-No No Material accountability Yes Yes No No "ersonnel accountability Yes Yes No No Na use of tobacco or eating Yes Yes No No 2)
Para 2.2 Procedures and Instructions.
This paragraph requires procedures for safety and fire regulations.
The project will use procedures which describe existing National State and Local codes and regulations to control safety and fire.
NFPA is the national fire code followed at the site.
G.
Alternates and Interpretations of Regulatory Guide 1.54-June 1973 (ANSI N101.4-1972)
The following alternates and interpretations apply to the
. implementation of Regulatory Guide 1.54 and ANSI N101.4.
1)
The painting requirements.for the Midland project are specified in four project oainting specifications, most of which were developed pr.ioz co the issuance of Regulatory Guide 1.54.
ANSI N101.4 was used extensively in the development of these specifications -and compliance to ANSI N45.2 :is Tequired by Consumers Power Company.for equipment procured for the Midland p roj ect.
Althcugh not specifically required in all four speci fications, ANSI-N101.4 and ANSI N101.2 are generally jg referenced and are'used in the evaluation and approval of
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' vendor painting' procedures.
s O()'!9~F1 1B-4 Amendment No. 36 12/77
2)
In instances where non-LOCA quai. fled paint is used on small components with a limited painted surface, such as valve
-/)N operators, instrumentation, small accessory components and
\\s, equipment trim, the FSAR wfll provide the total surf ace area painted with these non-LOCA qua'ified paints to substantiate their limited application and therefore acceptable use.
It is the applicant's position that upon completing the tabulation of the amount of non-LOCA qualified paint used inside the Midland containment, should this amount be below 100 kilograms, the amount would be acceptable.
In the calculation of thfe total weight, only components exposed to the LOCA environment will be considered.
If upon completion of the tabulation of the amount of non-LOCA qualified paint used inside containment, this amount exceeds 100 kilograms, it is the applicant's position that the following will be considered in conjunction with system characteristics (sump screen size and spray nozzle openings) to determine acceptability or necessity of any corrective actions:
The areas of paint exposed to the containment 14CA atmosphere a.
b.
The mode of paint fa. lure (i.e., flaking or solubility) c.
The potential of the paint reactants reaching the containment sump, considering possible surrc nding traps such as insulation, etc H.
Alternate to Regulatorv Guide 1. 58-August 1973 (ANSI N45.2.6-
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1973)
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The Regulatory Guide states that the provisions of ANSI N45.2.6-1973 are " generally applicable.
. during-fabrication prior to receipt of items at the construction site".
The project will not impose ANSI N45.2.6 on suppliers during fabricatica prior to receipt of items at the construction site.
Instead, the following activities are performed to ensure that offsite inspection, examination or testing is performed adequately.
Bechtel procurement documents will require that the supplier's Quality Assurance program provide measures to assure that personnel performing safety-relsted inspections, examinations and tests are qualified to perform these activities.
Such measures include procedures for qualification of-personnel describing the minimum experience, training and proficiency testing required-for qualification.
The measures also include requirements for records documenting qualifications for each of the supplier's inspection, examination, and testing personnel.
Personnel qualifica-tion procedures will be reviewed by Bechtel prior to initiation of inspections, examinations, or tests.
.Also,.Bechtel performs. surveillance inspection at supplier's facilities by using inspectors qualified in accordance with ANSI N45.2.6.
Quality Assurance audits are performed on suppliers and 4
additionally, nondestructive examinations perfor=ed according to the quality requirements of Section III of the ASME Boiler and
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Pressure Vessel Code;are performed by supplier personnel certified N /
to SNT-TC-1A.
55 S 1B-5 Amendment No. 36 s
12/77
1.
Supplemental Alternate to Regulatory Guide 1.64-Revision 1
'p (ANSI N45.2.11-1974)
%..)
Paragraph C-2, o: the Regulatory Guide places restrict 10ad on the use of the supervicor for design verification.
As an alternate the following controls will be exercised.
Design verification may be performed by the originator's supervisor if the supervisor is the only individual in the project team competent to perform the design verification.
In such cases, an additional review will be performed by either the next higher level of supervision or by of f-project personnel.
These personnel are qualified in the area of design review and verification.
I J.
Alternate to Regulatory Guide 1.88-August 1974 (ANSI N45.2.9-1974)
Section 5.6 of ANSI N45.2.9 requires that the per=anent record storage facility have " structure, doors, frames, and hardware class A fire rated with a recommended four hour :ninimum rating."
_ln lieu-of.this the existing Jobsite record storage facility has a two hour fire rating.
K.
Alternates and Interpretations of Regulatory Guide 1.9/-
2_
April 1975 (ANSI N45.2.5-1974)
The following alternates and interpretations applj to ANSI N45.2.5:
m) 1)
-Sections 1.4 Difinition'of '3ampling Point mul 4. 8 In-Process
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Tests on Concrete and Reinforcing Steel.
These sections seem to require the sampling of concrete at the truck discharge or the end of the pump line.
For the Midland project, the concrete receives its final mix at the central batchplant, and is transported by agitator trucks to the final conveying system.
The sampling point for the compressive strength test cylinders is from the discharge of the central batch plant stationary mixer, based on the following:
ANSI N45.2.5 Section 4.8 states that "Sa=ples for inprocess tes!. shall be taken at the sampling point in accordance with ASTM C 172."
ASTM C 172, Section 2, Note 3, reads:
" Sampling should normally be performed as the concrete is delivered from the concrete mixer to the conveying vehicle used to transport the concrete to the forms." ASIM C 172, Paragraph 3.2.1, Sampling from Stationary Mixers Except Paving Mixers, gives explicit instructions for stationary mixer sampling.
Compressive strength test cylinders are cast from representrtive samples taken frem the discharge of the hatch plant. stationary
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mixer in accordance with Paragraph 3, ASTM C 172.
Slu=p, air
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content, unit weight and temperature of the concrete will be h
13-6 QQM)Q Amendment No. 36 12/77 s
recorded when cylinders are being cast.
For purposes of s
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correlation, cylinders will also be cast from a sample taken
., s at the ty3, sport discharge of the same batch from which a sample was taken at the stationary mixer.
After correlation has been established, correlation cylinders are continued on a periodic basis to verify the correlation.
The conveying vehicle is defined as an agitttor truck.
The drums are turned at agitating speeds and not at mixing speed, because the concrete is completely mixed before being loaded as evidenced by the mixer uniformity tests ;f ASTM C 94.
Concrete samples f rom the batch plant mixer allow for better control of preparing samples, as well as less disturbance of cylinders from preparation through initial curing.
The sampling point for final acceptance of air content, slump and temperature is at the truck discharge except for concrete conveyed by pump. Pumped concrete is sampled at the pump line discharge.
The production control for air content, slump and' temperature can be at the batch plant discharge or truck discharge provided that a correlation program is developed as recommended by ACI/304 Paragraph 9.7.
The correlation program compares the test results for the same batch between the batch discharge and truck or pump discharge.
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2)
Section 4.3 Measuring, Mixing and Transporting Equipment requires measuring and mixing of concrete to be in accordance with National Ready Mix Concrete Association - (NRMCA), Concrete Plant Standard and Truck Mixer and Agitator standard.
The NRMCA Plant Standard Section 2.2 requires that the batching recorders, ".
shall register both empty balance and total weight of each. batched material."
The concrete batch plant at the Midland site will not provide a zero printout on our batch plant ticket.
Since our control panel locks out until the scale reads zero, the system meets the intent of NRMCA even though the printer does not provide a numerical indicator.
3)
Section 4.5, Concrete Placement.
Regulatory Guide 1.94 (C-3) requires that ACI-309-!" be used to determine the adequacy of consolidation equipment. ACI 309-72 was incorporated into the construction. specification in 1973, subject to the following alternates:
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Amendmeat No. 36 1B-7 12/77
't a)
Alternate to Equipment Requirements
-The project concrete placement specification was written in 1970, and based on the then current ACI Committee 609 report. The equipment currently in use on the project was purchased in accordance with the ACI Committee 609 4
report, and has been maintained in conformance with it to date.
Field inspection of concrete placements and concrete cores indicate satisfactory concrete consolidation has occurred. We therefore see no sound reason to justify the replacing of the project equipment to meet the recocsenda-tions of ACI 309-72, and discarding equipment that is currently performing in a satisfactory manner.
b)
Alternate to Lift Thickness Requirements ACI 309-72 Section 7.1 s:-
as:
"The conc ete should r
normally be deposited in.ayers 12 to 18 inches (30 to 45 cm) thick (dependint an the length of the vibrator head-and other factora,."
1 Other ACI specifications and recommendations for lift
. thickness are as follows:
-1)
-ACI 301-72 Chapter 8 on " Placing," Section 8.3.1
-states:
" Concrete shall be deposited continuously, or in layers of such thickness that no concrete will
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be deposited on concrete which has hardened sufficiently N.
to cause.the formation of seams or planes of weakness-within the section."
- 11) ACI 301-72 Chapter 14 on " Massive Concrete," Section 14.4.3 states:
" Concrete shall be placed in layers approxi-mately 18 inches thick."
111) ACI 301-72 =Section 8.3 references ACI 304 for detailed
- recommendations for depositing concrete. ACI 304-73 Chapter 6, Section 6.1 states:
"It (concrete-ed.)
.should be placed in horizontal layers not exceeding 2 ft.
(60 cm) in depth, avoiding inclined layers and cold joints."
e The project construction specifications require that concrete be placed in horizontal layers "of not greater ' depth than
- 24. inches so that satisfactory consolidation can be achieved with vibrators." Field inspections of concrete placemerts and concrete. core samples indicate satisfactory consolidation and placement of concrete'has occurred.
By combining the foregoing requirements and other' related f actors (concrete mix consistency and results of field inspection), the use of lifts not' exceeding 24 inchescis.in accordance with ACI specifications.
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4)
Table E required In-Process Tests.
This table requires that the compressive strength of grout be in-process tested daily f(
during production to the requirements of ASI?! C 109.
The following alternates to the testing of grout will be implemented:
a)
Batch Plant Mixed Grout The specificat ons require that each class of concrete i
has a companica grout mixture for use on construction joints, buttering pump lines and such other aoplications as shown on the drawings.
As appropriate to the concrete mix, the grout mix is specified to be the concrete =ix without the addition of coarse aggregate, leaving the cesent, pozzolan, sand (fine aggregate 3/8 inch or less) and admixtures in the same ratio as before and enough water to provide the desired consistency, but not exceeding the maximum water /(ce=ent + pozzolan) ratio established for the concrete mix.
Since this will prcduce a grout at least as strong as its companion concrete (due to the high cement content per cubic yard),_ testing of_all.the materials used in manufacturing grout is done as part of the concrete in-process testing program, and this accomplishes satisfactory quality control of the grout.
b)
Premixed Crout Factory packaged grout which requires addition of water
',()N and.miving in =a-aedaace with *ha ~ ~ ~ ~ ^ - ~ ~ ~ - - ' - instructions
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will be tested in accordance with ASTM C 109 for each lot purchased as a quality control check on the factory's production.
Since the project specifications require proper storage to prevent deterioration, there is no reason to require daily testing.
5)
Section 4.9.1, Qualification of Cadweld Operators.
The standard can.be interpreted to imply that qualifications of splicing crews are required for each position and each bar size.
The Bechtel position is that the qualifications for each position will be for the largest bar to be used.
This is also consistent with the May 15, 1973 staff. memo and CPCo's Regulatory Guide 1.10 position.
6)
Section 5.4, High Strength Bolting a)
The installation and inspection of high strength bolted joints are accomplished by one of three methods.
Two of these methods,
(.i.e.., automatic cutoff impact wrench, and the turn-of-the-nut method), concur with ANSI N45.2.5 requirements.
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r 3\\a' 00,; '-)'"3 1B-9 Amendment No. 36 12/77
The third method, the use of direct tension indicators, is a new method permitted by the Errata of October 22,
(,
-1974 to the "AISC Specification for Structural Bolts Using ASTM A 325 or A 490 Bolts."
The quality control procedures required for the use of direct tension indicators are as follows:
1)
To verify the load indicating qualities of the lvad indicators, at least three load indicators from each bag or box shall be verified in a calibration device similar to thac required for wrench calibration.
If nut face washers are v3ed between the indicators and the nuts, the indicators shall be tested with washers at the rate of three washers frcs each bag or box.
Each verification test shall show not less than the l
specified gap when bolt is tightened to the specified tension.
ii)
Load indicator washers shall be installed in accordance with the manufacturer's instructions.
When a load indicator is required under the nut a special nut face washer shall be fitted between the indicator and the nut.
iii) Bolted joints made with load indicators shall be inspected visually to ensure that all bolts have the I
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load indicators properly installed and to the proper gap. At least 20% of the bolts in each connection but not less than two bolts shall be checked with a feeler. gage to_ determine the bolts are properly tightened.
iv) Direct tension indicators used with bolts that have been tighted to the full extent specified in Section 5 of the AISC specification shall not be reused.
b)
The Midland project permits waiving of the AISC requirements for inspection by torque or power wrench provided special inspection procedures are followed.
L.
Alternates to Implementation of WASH 1283 (Revision 1) and UASH 1309 Where the Bechtel QA Topical Report or the preceding infor=ation discusses versions of Regulatory Guides or ANSI standards which are
-different from those provided in WASH 1283 (Revision ~1) " Guidance un Quality Assurance Requirements During the Design and Procurenent Phase of Nuclear Tower Plants" or WASH 1309 " Guidance on Quality Assurance Requirements During the Construction Phase of Nuclear
();
L 00194 1B-10 Amendment No. 36 12/77
Power Plants," the versions discussed in the Bechtel QA Topical Report or in the preceding infor=ation will be implemented by gO Bechtel.
!C In addition, the following draf t ANSI standards will be implemented in lieu of the standards provided in WASH 1283 or 1309:
Draft Standard Version in WASH Document Version to be Implemented ANSI N45.2.12 Draft 3 Revision 4 Draft 4 Revision 1 ANSI N45.2.13 Draft 2 Revision 4 Draft 3 Revision 3 II.
EFFECTIVITY DATES Subject to the exceptions contained in Section III below, the preceding commitments will be implemented on the following dates for all subsequent safety-related activities relative to the Midland Project:
A.
For Consumers Power Activities; December 2,1976 B.
For Bechtel Activities; May 15, 1977 with the exception of commitments relative to Regulatory Guides 1.30, 1.37, 1.38, 1.39 and 1.94 where the effectivity date will be July 1, 1977.
C.
For Sabcock and Wilcox Activities; August 7,1977.
(
III. EXCEPTIONS The following exceptions relate to specific commitments which will be implemented because-implementation would require unwarranted not modifications of the Midland Project design, procurement, fabrication or construction:
A.
General Exception to Consumers Power, Bechtel and Babcock &
Wilcox Commitments No attempt will be made to change procurement documents which have been issued prior to the effectivity date established for the Consumers Power, Bechtel or Babcock & Wilcox commitments in order to comply with those commitments.
The relevant commitments will be applied to procurement documents which are issued on or after the effectivity date.
B.
Specific Exceptions to Babcock & Wilcox Commitments 1)
Section 2.2.1, paragraph 1 af.the 26W Topical Report reads as follows:
"The degree of QA involvement with any U
00M5 IB-ll Amendment No. 36 12/77
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specific equipment / component is determined by the safety classification syste= defined in the B&W Safety Classifica-
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tion -Specification derived f rom Regulatory Guide 1.26 and IEEE Standard 308-1973."
In addition to the preceding, s
1, the Project Position for Regulatory Guide 1.26 (as described in R. C. Bauman's October 10, 1975 letter to Mr. Roger Boyd and as supplemented by R. C. Bauman's February 5, 1976 letter to Mr. Roger Boyd and as evaluated in S. A. Varga's September.24, 1976 letter to S. H. Howell) is also a basis of the safety classification system.
2)
The following design docu=ents are discussed in the B&W Topical ~ Report:
Topical Design Document Report Section Paragraph System Requirements Specification (S.R.S.)
2.2.2 2
3.2 1
3.2 12 4.0 1
4.0 2
System Descriptions (S.D.)
3.2 1
3.2 7
3.2 12 Balance of Plant Criteria (BOP) 3.2 12 i
_ Contract Info--~*4a -Shectc (CIS) 4.0 1
s_
In addition, B&W procedures which implement the Topica]
Report identify a Plant Parameter List (PPL) and Technical Deviation List (TDL).
The TDL is a tabulation of all the.
technical and performance differences between the B&W Standard ~ Plant and the "As-Sold" contract plant.
For new projects, the. issuance of the TDL establishes the preliminary contract technical baseline and is the basis for preparation of the contract technical documents.
The PPL is used for new contracts to identify major factors of plant design.
None of the above documents have been (or will be) prc aced e
for the non-fuel components supplied for the Midland Proj ect.
For new projects, these documents are used as
_the basis documents for the preparation of Equipment Specifications and Balance of Plant Criteria.
- However, these documents became a requirement of the B&W Design Control-system after Equipment Specifications were issued and procurement activities initiated for the Midland Project.
In addition, Balance of' Plant-Criteria requirements have been satisfied by other means without Tecourse to these documents.
Formal Balance of Plant Criteria documents
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13-12 Amendment No. 36 12/77
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will not be prepared since this criteria has been forwarded
</ 'N to the Architect Engineer in the form of correspondence from B&W to Bechtel and B&W will review Bechtel design documents which contain NSSS interfaces for the adequacy of tnose interfaces.
Therefore, since Equipment Specifica-tions and 3alance of Plant Criteria have been prepared without recourse to the SRS, SD, PPL, CIS and TDL documents, these documents are not needed for the Midland Project.
3)
Section 17 and Appendix A of the Topical Report co=mit B&W to implement the requirements of ANSI N45.2.9-1974.
Section 4.3.1 of ANSI N45.2.9-1974 requires for receipt control of QA Records that the system shall include:
"A Records Checkli.9 designating the required QA Records."
A Records Checklist has not been (and will not be) prepared for the Midland Project.
The majority of B&W generated QA records (i.e., calculations, specifications, procurement documents, etc) have been prepared and filed without recourse to a records. checklist. -However..they are listed on the Documents Historical Listing (DHL).
The DHL is the output of an automated system that identifies and raports the status of contract documents originated by B&W.
It also provides a convenient means of verifying that the necessary records have in fact been generated.
Tne remainder of QA records to be generated by B&W for
,fs the Midland, Project consists pri=arily
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ts to
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-support FSAR activities, Core design and site support activities (i.e., Field Changes, Site Problem Reports, etc.).
The-need for the foregoing records is identified in work authorizations approved by the B&W Project Manager for the Midland Project.
As these documeats are prepared, they will be listed on the DHL.
The Quality Requirements Matrix (QRM) described in Section 4 of the Topical Report will continue to serve as the Records Checklist for vendor generated documents.
The QRM identifies the QA Records required from vendors by
' the B&W procurement documents.
As vendor documents 'are 4
received, they are listed on the DHL described above.
The B&W QA Engineur for the' Midland Project is required by.B&W administrative procedures to verify that the vendor QA Records required by the QRM have been received and properly dispositioned.
In summary. because the majority of B&W generated QA Records have been prepared and over 60% of the required vendor QA Records have been received, a Records Checklist will net.be prepared.
The DHL and QRM provide an adequate c
means of verifying that the required QA Records have been generated.
/T s
.; h 00197 1B-13 Amendment No. 36 12/77
(
APPENDIX 1B QUALITY ASSURANCE PROGRAM b/
1 ONECTIVES AND DEFINITIONS 1.1 OMEC*IVES As part of the overall Consumers Power Company Quality Assurance Program, the Midland nuclear plant Quality Assurance objective is to yield maximum confi-dence tnat the plant is designed and constructed so that it can and will be operated without undue risk to the health and safety of the general public and plant operating personnel. Of equal importance as an objective of our Midland Quality Assurance procedure is the efficient and reliable performance of the plant.
Close scrutiny of the design and procurement phases of a plant can, at times, identify problem areas before they interfere with the schedule, -thus assisting in a timely plant availability.
The Quality Assurance Program vill start with the design. phase and proceed throughout the construction and op-erating phases of the plant life.
1.2 DEFINITIONS 1.2.1 QUALTIT CONTROL
' Quality Control is the detailed and systematic inspection, testing, and docu-mentation program to ensure that the material, process, component, system, or s
i facility is in accordance with predetermined quality requirements.
Quality Centrol is further used to determine that the systems and components are built V
according to design.
It is the first line of control and, as such, is the re-sponsibility of the organization performing the actual work, such as:
The Engineer-Architect in the design; the Vendor in shop construction; the Con-structor in the installation and erection; and the Owner during operation.
1.2.2 QUALITY ASSURANCE Quality Assurance is an independent audit to establish the effectiveness of the Quality Control programs throughout the design, construction and operating phases of plant life. Quality Assurance is the responsibility of vendors, subvendors, contractors and subcontractors, with the overall or final respon-sibility by the Owner.
13 ORGANIZA'I' ION AND AIhmmATION
'l.3 1 PRIOR 'IO INITIAL FUEL LOADING - CP CO All phases of design and construction prior to initial fuel loading are the responsibility of.the Senior V1.ce President.in charge of Generating Plant Engineering and Generating Plant Construction. Repening to this Senior Vice President is a Manager of Generating Plant Engineering who has responsibility of the design, procurement, manufacturing and shipping phases of the Project.
p The Manager assigns a member of his technical staff'to be Project Engineer for t
this particular project.Who assumes the following responsibilities:
y 1.
Coordinates communication with CP Co pertaining to this project.
00198 13-1
' Amendment No. 4 3 /96169 L
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Coordinates technical review of design bases, drawings and
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specifications by CP Co Engineering, Operating, and Con-struction Departments.
3 Prepares or coordinates preparation of reports such as the PSAR, FSAR (including a.mendments) and permit applications.
h.
Keeps Management apprised of the status of the project.
5 Provides assistance in preparing and implementing the Bechtel QA program.
6.
Leads presentations and discussions with licensing bodies.
7 Ascertains that preoperational test procedures are prepared c
and reviewed by qualified technical people.
8.
Assures that test results of the preoperational tests are re-viewed by qualified technical persons and assures himself that any necessary corrective measures are taken.
The direction and coordination of the QA program from design through construc-
. tion is the responsibility of.a Quality Assurance Engineer who reports to the Manager of Generating Plant Engineering. His duties include the following:
1.
Plans and administers the Owner's QA program.
V 2.
Determines the adequacy of, and effects corrective measures to, the
-QA program of.the Engineer-Architect and with the aid of the Engineer-Architect determines the adequacy of QA and/or QC programs of Con-tractors and Vendors.
3 Determines that proper documentation is maintained throughout design, procurement, fabrication, cleaning and shipping of systems or components.
h.
Reports.confor=ance to or deviations from the QA program to the Senior Vice President, Manager of Generating Plant Engineering, Manager of Generating Plant Construction and the Project Engineer.
5 Takes corrective measures to all deviations from the QA program and documents the corrective measures and final results.
6.
Performs or directs inspection trips to Vendors shops during
. fabrication, testing, and preparation for shipment. Inis is ac-complishad with the assistance of engine rs from the Civil, Mechanical, Nuclear, and Electrical Engineering groups and specialists from other departments. These trips are sometimes scheduled in advance and sometimes unannounced,' depending upon the proven adequacy of that particular vendor's QA and/or QC program and his implementation thereof.
v' The Quality Assurance Engineer's qualifications will include the following:
00198 13-2 Amendment No. 4 Allsdal&A
1.
Knowledge of applicable codes, such as:
ASME Boiler Code; Piping g,j Codes; In-Service Inspection Codes; and State and Local Codes.
2.
Knowledge of nondestructive tests, such as:
Dye Penetrant; Mag-netic Particle; Ultrasonics; and Radiography.
3 Knowledge of the SAR for this project.
h.
Knowledge of various manufacturing techniques.
5 Fin 111arity with the functions of the various systems and com-ponents and, in particular, the effect of these systems and components on the. safe and reliable operation of the plant.
6.
Experience in performance testing and analysis of the'various co=ponents and systems.
The Manager of. Generating Plant Ceusi.dction is responsible -for plant construc-tion and preoperational testing.
Reporting to him is a Field Superintendent who is respcnsible for the overall construction of the plant.
Bechtel will be the Plant Constructor and vill have responsibility for field QC.
CP Co's Field QA Engineer, under the functional direction of the Generating Plant Department's QA Engineer, will perform proper surveillance of Bechtel's QC-QA program to determine the program's effectiveness. The Field QA Engineer's duties include:
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'l.
~ Determines that Bechtel's field QC-QA program is being properly implemented.
V
.2.
Reports.confor=ance to or deviationc from the QA program to the Field Superintendent and to the Generating Plant Engineering Department 's QA. Engineer.
3 Determines that necessary corrective actions to deviations from the QA program are accomplished.
h.
Ascertains that proper documentation of QC and QA field construction phase is accomplished.
The Field Quality Assurance Engineer vill have the help of other engineers of
- the Engineering, Construction, and Operating Departments who are specialirts in
'their fields. The Field QA Engineer's qualifications include:
1.
Knowledge of destructive and nondestructive tests performed during the construction of generating plant.
2.
Knowledge of docu=entation required for.this project.
3 Knowledge of any special environmental requirements for certain construction functions.
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4.
Knowledge of special protection for systems and components during kJs '
sto-age either before or after installation.
V 00200 13-3.
Amendment No. 4 (NlMMe
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5 Kncvledge of any special previsica for equip =ent that is specified in the SAP..
6.
Knowledge of design specificaticns.
1s 2,
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w The respensibility for design, precurenent of equipment cther than the NS3 and turbine generators. and ccnstructicn of the plant has been assigned tc the Eechtel Corpcration.
33chtel vill perfor= the Quality Assurance effert for all phases cf plant engineering, shcp and field fabrication, and cen-st ructicn.
The 3echtel Project Engineer and his Design Engineering Super-visors and the 3echtel Quality Assurance Engineer have the prime responsibility for imple=ent ing the QA progra=.
Management assistance and surveillance of engineering are provided by the ecgnizant Assistant Manager of Engineering, and technical assistance and review are provided by Chief Engineers and their technical staffs. The Project Engineering ten: prepares the Q list (list of critical ite=s), deter =ines detailed quality requirements and cen=unicates these to procure =ent and construction, reviews critical fabricaticn and in-spection procedures and shop inspection repcrts, and, through the 3echtel Quality Assurance Engineer, provides surveillance of field engineering and inspection.
The Sechtel Quality Assurance Engineer is a =e=ber of the Eechtel Project En-7" gineering tea: and reports to the 3echtel Project _F.nginaer. _He _is stationad s
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at the jobsite after field verk starts and is responsible for surveillance cf s))'
engineering and Sechtel Quality Centrol activities in the field.
The QAE dces not perfor= inspection but serves as a representative of the 3echtel Project Engineer in the field providing guidance en requirements related to the QA progrs= and surveillance of inspection reporting and documentation.
He has authority to stop work and assure correction of any significant deviatien in quality of construction caterials and work =anship.
Sechtel Quality Con-trol in the field is performed by engineers who report to the 3echtel Project Superintendent.
Bechtel shop inspections are perforced by representatives of Bechtel Purchasing and the inspection reports are sent to the 3echtel Project Engineer.
These inspections are both scheduled and unscheduled and are for the purpose of deter =ining that the equip =ent is built according to the plans and specifica-tions.
The inspector has the assistance of the prcject team te help deter =ine any corrective =easures that cust be taken.
The shop inspecticns start with
. inspection of the raw caterials and conclude with shipment of the equip =ent and receipt of all necessary docu=entation.
Shop inspections will include all NS3 suppliers ' shops in addition to Bechtel-supplied equipcent.
Sechtel field QC and QA personnel are responsible for the receiving, erecting, cleaning, docu=entation and protecticn of the equip =ent at the site.
Where
=aterial or nondestructive testing is specified or required to be perforced during construction, Bechtel =ay e= ploy the services of a qualified independent inspection laboratory.
'M Details of Bechtel's Quality Assurance pregran are documented in a Nuclear Quality Assurance Manual of the Power and Industrial Divisien.
Bechtel's shop inspection progra is documented in its Shop Inspection Manual. Field inspec-tion procedures are documented in Bechtel's Field Inspection Manual.
13-4 00 31
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Crganicaticc; planning; design
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M*4 has established a basis for classifying equip =ent in accordance with the i=portance of its nuclear safety-related functicn. The classification basis is given in Table 1 (at rear of this section).
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The ele =ents of-the M*4 QA'pregrs= 'ure applied in~ art urlance ~vith'the equip-V
=ent classificatien by the Nuclear Quality Progra: Requirements Specificatien.
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r practical, to all equip =ent =anufactured and purchased by M'4 for tha Midland project. Prcject schedule requirements dictated initiation cf detailed design verk, =aterials precure=ent, and. fabrication of =ajor MW-=anufactured ec=Do-nents in June 1968. This verk has been done under the existing industry cedes, I standards, and MW Quality Assurance and Quality Centrcl precedures. These r.. C a.. A.r..a. s - n. a. t +. %..
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yf 1 3 3 2.1 Organicatien Power Generatien Divisien (Figare 1-1)
The PGD designs, =anufactures, procures, erects, and services nuclear and cen-ventional stea generating syste=s and equip =ent and heavy-pressure vessel a u.4 ~, a a.*.,.'c
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-s also designs and manufactures reacter vessels, stea: generaters, and pres-suricers for the Navy, the USAEO, and ec=ercial nuclear pcver plants; reacter ceres are also manufactured for ce==ercial nuclear power plants.
Nuclear Power Generation Depa-t=ent (Figare 1-1) 2.e 1DGD has been designated as the MW corporate seg=ent with *.he everall
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respcasibility for executien of ec=ercial nuclear utility syste=s and fuel contract s. This includes contract ad-inistration, design, licensing, precure-
=ent, site activities, and Quality Assurance.
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fabricating operations:
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such as reactor pressure vessels and reactor ecolant piping.
The Lynchburg Cc=ercial Nuclear Fuel Plant which fabricates fuel assemblies, centrol red asse=blies, and ether ecre ec=penents.
- ?G:: vill use ether PGD fabricating facilities to obtain ether reae cr ecolant i
syste= cc=penents, such as stea: generaters, reacter pressure vessel internals, I pressuricers, and refueling equipment, which have been designed by N?GL.
The 3'14 Erection Cc=pany vill provide field installation censulting se-vices including installation criteria for Midland Plant Units 1 and 2.
M*4-NPGD Quality Assurance Organication (Firure 1-2)
MW's Quality Assurance progra= for ec=ercial nuclear utility syste=s and fuel is administered by MW-MPGD Quality Assurance organization. The Manager of
-C m lity Assurance is directly responsible to the Vice President of 5 this capacity, he is respcnsible for the development and i=ple=enta-af a coordinated cc=prehensive Quality Assurance progra=. The Manager Las the authority and corporate organizational freedc= to identify quality proble=s; to initiate, recc==end, and/cr provide solutions; and to require 1=plementation of adequate solutions.
n
-(V) quality Assuranca Representatives y
The QA Representatives report directly to the QA Manager. They have clearly defined responsibilities which include, but are not limited to, review of pro-curement docu=ent packages including equipment Quality Assurance provisiens; review and rating of equipment suppliers and their Quality Centrol procedures, facilities, personnel,.and processes; and developcent and review of internal NPGD procedures, standards, and specifications.
Field Representatives The Field Representatives report to a Supervisor who in turn reports to the NPGD Quality Assurance Manager. Their responsibilities include assisting Quality Assurance Representatives in the preparation of product surveillance
' plans and the imple=entation thereof, review and approval of quality doc =en-tation for the product, and assisting QnHty Assurance Representatives in auditing and qualifying new suppliers.
1 3 3 2.2 Qualit'y Assurance Progra=
a.
Objectives - CA Prcrra:
The objectives of the MW QA progra= are to (1) establish quality require =ents; (2) doc =ent and ce=unicate the established quality require =ents; -(3) provide or select =anufactu-ing facilities that
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assure achieve =ent of the quality require =ents; (h) =enitor the
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=anufacturing as appropriate to insure that quality processes are being used; and (5) provide doc =entation to de=enstrate that the n/
established quality level has been achieved.
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B&W-t4PGD QU ALI TY ASSUR AtlCE Manager Q/A Q/A Representative B&W Manufactured Equipment Q/A Representative B&W Purchased Equipment -
O Mechanical V
Q/A Representative B&W Purchased Equipment -
Electrical Q/A Representative Fuel 4/A Field Representatives l
v 00P.05 Figure 1-2
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b.
Quality Levels
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E&W's quality program, which is consistent with CP Co QA require-i
=ents, functions on two levels:
Quality Centrol and Qualit,y Assurance.
B&W defines these terms as follevs:
Quality Centrol is the first level and the = cst detailed function of a quality program.
The activities are directed toward measuring quantatively the quality of the verk product of any cpera*ien. Activities during the various design phases of a project include a checx of design calculations, drawings, or speci-fications.
Quality Centrol in =anu'acturing includes systematic inspection, testing, and docu=entation to estab.ish that the product confer =s to specifica-tion require =ents.
Quality Centrol can be perfor ed by persennel in the same organization that are responsible for the work function.
i Quality Assurance is a planned, syste=atic audit and control of the quality progra= to insure tha:. adequate quality progra= elements are being.1=plemented.
Quality Assurance activities are performed by personnel who are independent of the Quality Centrol and verk functicn.
c.
Planning B&W imple=ents its QA program through standards and written pro-cedures. E=phasis is placed en the establishment of an audit pro-gra= and. documentation requirements consistent with the nuclear
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safety-related functions by establishing essentiality levels for equip =ent.
V d.
Procure =ent Equipment which has: nuclear safety-related functions and is supplied by B&W for Midland Plant Units 1 and 2 is procured in conformance with a Nuclear Quality Progra= Requirements Specification which is part of the procure =ent document package.
The requirements of the specification are applied to equipment in accordance with the equip-
=ent's importance to nuclear safety. The program of classified and correlative quality requirements are applied to both purchased equip-ment and that being =anufactured within B&W's facilities. The Nuclear Quality Program Requirements Specification defines criteria for the ad=inistration and documentation of supplier quality progra=s and contains appropriate provisions for material control, process centrol, nondestructive testing, maintenance of records, packaging, and shipping requirements.
Suppliers include outside organizations and all E&W-NPGD =anufac-
.turing. facilities, as well as other PGD =anufacturing facilities furnishing equipment to 3PGD.
For equipment manufactured by B&W, 3&W-RPGD' Nuclear Systems Engi-
,m
'neering p epares functional specifications. 'B&W-TPGD Cc=ponent' d
)
Engineering prepares equipment specifications, perfor=s =echanical Od -
design and code-required stress analysis, and establishes the
=aterial requirements.
,v, 00306 13-9 A=endment No. 8 MLlSllXQ
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For equipment purchased by B&W, B&W-NPGD Nuclear Systems Engi-
%,/
neering prepares equipment specifications.
Suppliers prepare detailed designs.
B&W-NPGD QA organization audits and evaluates supplisrs according to the Quality Centrol program require =ents as appropriate to equip-cent classification. For selected equipment, a supplier certifica-tion audit is performed in accordance with written procedures prior to placement of a purchase order, or prior to release to manufacture.
e.
Erection For the Midland Plant Units 1 and 2, B&W furnishes advice and con-sultation, including erection criteria, for erectica of the equiptent it supplies.
f.
Plant Test Program B&W prepares test specifications for the plant test progra=s to be conducted on equipment and syste=s within the B&W scope of supply.
B&W supplies advice and consultation during the test program and reviews the test results.
B&W procedures and standards are used in the preparation,. approval, and modification of test specifications.
O 13323 Design Control V
The B&W QA program incorporates provisions to assure that limits imposed by the
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" design ' ases" and applicable regulatory require =ents are correctly translated b
-into specifications, drawings, procedures, and instructions. Designs and draw-ings prepared by the equiprent supplier are reviewed by B&W-NPGD for confornance
- to specifications and by CP Co (or its agents) for compatibility with interface require =ents.
Where design standards do not exist or where they are modified, design reviews are conducted by personnel who did not perform the original design work.
NPGD Nuclear Systems Engineering is responsible for all project design activites within the B&W scope of supply.
NPGD standards covering calculational cethods, property data, drawings, flov diagrams, and specifications are used wherever possible.
Checks are invoked on these design activites as set forth below in accordance with written procedures:
a.
Analytical Work Analytical work is checked for input, results, and application by an independent reviewer in. Nuclear Systems Engineering who is a person other than the engineer responsible for the or.iginal calmlation.
He vill also check the calculational method if a standard is not used. The reviewer checks for important results in application and certifies his check.
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b.
Standard Drawings
. x _-
Standard mechanical, process, instrumentation, and electrical drawings s_j are used whenever possible.
When it becomes necessary to revise a 00307 1B-10 A=end=ent No. 8 e
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drawing to accommodate project needs, there is a reviev and certifi-
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cation =ade by the cognizant engineering section supervisor for correctness and consistency with standard B&W practices and inter-facing equipment require =ents.
Specificatiens and revisions to specifications for specific types of equip =ent are revieved and approved by the sa=e individuals as identified above for the same equipnent drawing reviews and approvals, c.
Standard Specifications The application of standard specifications to specific projects is used whenever possible.
Their applicability is checked by the engi-neer assigned and certified by his group and section managers.
~
When it becomes necessary to revise a specification to acec==odate project needs, there is a review and certification =ade by the cog-nizant engineering section supervisor.for correctness and consistency with standard B&W practices and interfacing equipment requirements.
Specifications and revisiens to specifications for specific types of equipment are reviewed and approved by the sa:e individuals as identified above for the same equipment drawing reviews and approvals.
Equip =ent lipecifications falling under the jurisdiction of ASME and
. /'"N ANSI ccdes are signed by re61stered professional engineers.as required.
'b d.
pSAR and FSAR Text Material PSAR and FSAR text eterial is prepared and reviewed in a two-step process. First, thu engineer assigned responsibility for coordinating
-the preparation and scheduling of SAR sections for which B&W has responsibility will be responsible for assuring that an independent check has been =ade and certified by a qualified engineer for tech-nical accuracy and calculational =odel adequacy of the =aterial presented.
The second portion of the design review will be con-ducted by the Licensing Supervisor responsible for the licensing on the contract who signs and dates the title page of each SAR section so reviewed. His review covers co=pliance with AEC require-ments for content, report organization, and fulfillnent of other licensing co==it=ents.
Revisions are covered by the above procedure.
The B&W-NPGD QA organization provides an independent audit and evaluation of engineering documents, including specifications,. instructions, procedures, and drawings to confirm that the design review progra= ls. implemented.
1332.4 Procurement Docu=er.t control The procure =ent documents inclr.de technical specifications identifying an essentiality level for the equip =ent based on its l=portance to nuclear safety.
A.
The Nuclear Quality Program Require =ents Specification reflects these essen-(},)
tiality levels and is a part of procure =ent documents submitted to suppliers for procurement of equipment for the project.
V 00208 1E-11 Amend =ent No. 8 RA429B
(
For equipment to be furnished by cutside suppliers, Nuclear Syste=s Engineering
\\=/
follows written procedures in preparing requisitions for supplier quotation requests, requests for place =ent of purchase orders, supplier drawing approval notifications, and releases to =anufactw*e.
The procedures provide for the re-view and approval of requisitions by other personnel assigned to project work.
For equip =ent to be supplied by BLW =anufacturing facilities, Nuclear Syste=s Engineering follcus written procedures in preparing interdepart=ent engineering and manufacturing instructiens for quotation requests, releases fer detailing, releases fer material procure =ent, and manufacturing releases. These procedures provide for review and approval of the instructions by cther personnel assigned to project work.
13325 Instructions, procedures and Drawings B&W-NPGD utilizes its evn facilities and those of other PGD departments in the execution of its nuclear steam syste=s and fuel contracts.. Departmental in-structions and procedures covering Administrative, Engineering, Procure =ent, BiW Manufacturing, Qua'lity Assurance, and Field Installation activities are contained.in the _folleving B&W =anuals located at appropriate locations in the ec=pany. The =anuals include previsiens for additiens and revisions.
Ad=inistrative (Prepared by Nuclear Power Generation Department)
N NPGD Procedures Manual g,j Engineering (Prepared by Nuclear Pever Generation Department)
PWR NSS Manual Procure =ent (Prepared-by Purchasing Department)
Purchasing Manual - Power Generation Division B&W Manufacturing (*)
Quality Control Manual for Nuclear C-nents Fabricated in Accordance (prepared by Barberten Nuclear With ASME Boiler & Pressure Vesse' a
Equipment Department) l Cc==ercial Nuclear Fuel Plant QA Policy thnual (Prepared by Nuclear Power Generation Department)
QunHty Assurance (Prepared by Nuclear Power Generation Department)
I NPGD Procedures Manual B&W QA bhnual for Nuclear Steam Systems and Fuel I
/
Field Installation (Prepared by B&W Erection Cc=pany)
,\\
s3~
~
Field Specifications for NSS Components v
00?.09
. 12 Amend ent No. 8 L
sipha
1 B&W-NPGD supplements the above documents by specific written instructions and
,%./
procedures as necessary for contract requirements.
1 B&W suppliers are required to have appropriate written instructions and proce-4 dures, and drawings covering work processes in accordance with the NPGD Nuclear Quality Prcgram Pequirements Specification.
1
(*)
Examples are given below regarding preparation and use of these =anuals:
Quality Control Manual for Nuclear Cc=tonents Fabricated in Accordance Witn ASME Boller !c Pressure Vessel Ccde This manual describes the Quality Control provisions and procedures in effect in the Power Generation Division of The Babcock & Wilcox Cc=pany to be applied to nuclear contracts built in accordance with the ASME Boiler and Pressure Vessel Code.
The manual does not include all de-tailed Quality Ccntrol specifications and procedures, but contains sufficient references to verify the existence of an adequate Quality Control system.
This manual applies to the B&W canufacturing facilities that are involved in the fabrication of pressure boundary components being fabricated in accordance with Secticn III of the ASME Boiler and Pressure Vessel Code.
This manual is prepared, maintained, and distributed by the. Quality Assurance Engineering Section of Quality Assurance which is a staff function of the Power Generation Division.
g,j 1
l CNFP Quality-Accurance Policy Manual
.This manual sets forth :the general responsibilities and policies of the Quality Control Section of the ILW Cc==ercial Nuclear Fuel Plant.
i The basic Quality Assurance system for the CNFP is outlined in this manual, and includes administration of the CNFP Quality Control program, and requirements for objective evidence that the level of quality speci-l fled in procurement documents and fabrication processes has indeed been achieved.
4 This manual is prepared, maintained, and distributed by the CNFP Quality Control Section of the Cc=nercial Nuclear Fuel Plant.
1 3 3 2.6 Document Control Written procedures are invoked within B&W to control the preparation, approval, and distribution of specifications,. drawings,. instructions, and revisions thereto.
These procedures assure that current approved versions of standard specifica-tions, drawings, and instructions are used by the B&W-NPGD work force.
Engi-neering Development (see Figure 1-1) is responsible for preparing, releasing, and updating these internal procedures.
I
\\: J i
V 00210 1B-12a Amendment No. 8 2 /9/70
,O Engineering Development prepares these standard procedures through the NPGD
%,y standards development program.
This program includes a Standardization Cc=-
ittee which is responsible for the approval of NPGD standards relating to engineering and administrative matters. The Cc==ittee includes personnel frc
Contract, Purchasing, Engineering Development, Planning and Cc==ercial, Propo-sitica, Cc==ercial Nuclear Puel, and Quality Assurance.
This Cctmittee reviews standard equip =ent and material specifications prepared by engineering sections who have assigned responsibilities in the area of verk performed.
Pepresentative topics of the NPGD Procedures Manual, mentiened in Paragraph 1 3 3 2 5, are listed below. Docu=ent Centrol is necessary for the prcper functioning of Design Control (13 3 2 3) and Procure =ent Docu=ent Control (1 3 3 2.h).
i
)
Design Control l
Processing, Use, and Maintenance of NPGD Standard Drawings Specification Nu= bering Syste=
Drawing Approval and Release (*)
Release and Distribution of Specifications 1-Jnstructions =for sthe PreIeration_of, Change J.uthorization For__s 4
' s s' Specification Change Procedure Preparation, Review and Approval of SAR(*)
Procurement Document Control Purchasing Ter=s and Cenditions Interdepartment Engineering and Manufacturing Inst 2uctions
(+)
Examples are given below of the scope and purpose of these procedures:
l B&W-NPGD Procedure - Drawing Approval and Release I
This standard procedure cove s the review and apreoval of all drawings originating within Nuclear Systems Engineering oefore they are released for procurement under a contract. Provisions are made for approval by the group supervisor and section =anager.
The Project Manage =ent section of HPGD releases and coordinates all proj-ect drawings with the Utility (or its agent) which assures routing all drawings through one source; thus, only the Project Manager has the re-sponsibility for releasing design drawings for Midland Plant Units 1 and 2.
,O
!.h s_-
OO?. U.
e 1B-12b Amend =ent No. 8
m
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BW-NPGD Procedure - Preparation, Review, and Approval of SAR V
This standard procedure describes the responsibility for preparing and reviewing portions of safety analysis reports prepared by P W-NPGD for the custc=er's use in submitting a Part 50 license application to the AEC.
This procedure establishes requirements for the inclusion of design bases and applicable regulatory requirements in safaty analysis reports.
Fur-ther, this procedure covers a formal review and approval of changes to the safety analysis reports for cenpatibility with equipment design and pro-curecent activities.
13327 Control of Purchased Material, Equiptent.
.3 Services The BW Quality Assurance program requires the evaluation of potential suppliers of critical equipment to ascertain their quality capabilities.
This review is based on the type of supplies and services.being considered for placement with the supplier and is conducted in accordance with written BW-NPGD evaluation procedures. Suppliers are subject to the requirements of the Nuclear Quality Program Requirements Specification as set forth in Table 2.
Require =ents con-tained in this specification pertain to the supplier's quality program including inspection and tests necessary to substantiate product confor=ance to procure-ment requirements. A vritten report is prepared of~this preaward evaluation.
.After. placement,of_punchase. order (or, issuance _of,interdepartment. engineering fku/
and canufacturing instructions), supplier conformance to BW-NPGD procurement documents (including the Nuclear Quality Program Require =ents Specification) is detemined by a BW-NPGD in-process audit program including follow-up sur-veillance. "The procurement documents define the appropriate quality documen-tation to be supplied to, and reviewed by, BW for completeness.
These BW-NPGD controls are covered by written internal procedures.
1 3 3 2.8 Identification and Control of Materials, Parts, and Components Suppliers of equipment to BW-NPGD are required to have written =sterial con-trol procedures as set forth in the BW-NPGD Nuclear Quality Prog-am Require-ments Specification. This specification is included in BW-NPGD procurement documents and establishes requirements for identification and contrcl of ma-terials, parts, and components. The supplier's procedures.for co=pliance with this quality requirement are reviewed by BW-NPGD Quality Assurance prior to release to manufacture.
13329 Control of Special. Processes Suppliers of critical equipment which involves the use of special processes in the course of manufacturing are required by the provisions of the Nuclear Quality Program Requirements Specificatien to have written detailed procedures covering the application of these processes to the component. 14 hen required by BW-NPGD procurement documents, the suppliel must submit special processes
.sd' and procedures to BW-NPGD for review and approval prior to release' for manufacture.
s /-
00?.i2 1B-12c Amend =ent No. 8 slaAsta
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1 3 3 2.10 Inspection
%/
Suppliers are required to have written Quality Control procedures covering this activity as specified in the Nuclear Quality Program Fequire=ents Specification.
This specification requires that Level 1 co=ponents be fabricated under a con-trolled manufacturing and inspection program.
The quality progra= require =ents for Level 1 cc=ponents are given in Table 1 (at rear of this section).
The specification requires t nat Level 2 components be fabricated under a con-trolled inspection program. The quality program require =ents for Level 2 components are given in Table 2 (at rear of this section).
The B&W-NPGD Quality Assurance function has the responsibility for performing prepurchase order award supplier evaluations, in-process syste= auditing, and product surveillance at supplier's facilities.
In the execution of this func-tion, they may observe significant tests and inspections =ade during the course of manufacturing and prior to the release for shipment. When it is a require-ment of B&W-NPGD Nuclear Systems Engineering or Quality Assurance, mandator'/
hold points will be de'signated in the procure =ent documents. Ccgnicant engi-neering and Quality Assurance personnel =ay participate in observing functional equip =ent tests.
1 3 3 2.11 Test control B&W-NPGD procurement documents establish supplier test and test control require-m
=ents.
Test results are documented and evaluated by the supplier and B&W-NPGD g,j on the basis of specified acceptance criteria as included in the B&W-NPGD pro-curement docu=ents.
Suppliers are required by provisions of the Nuclear Quality Program Requirements Specification to have test control procedures which ec= ply with the requirements of this procure =ent document.
B&W-NPGD reviews and a_ rroves these procedures prior -to the supplier entering this phase of the
=anufacturing cycle.
1332.12 calibration of Measure =ent and Test Equipment In accordance with Nuclear Quality Pregram Requirements Specification, suppliers are required to =aintain a system of control, augnented by written procedures, which assures that critical tools, =easuring instru=ents, and test equip =ent are maintained and calibrated to assure that =easured parameters are being obtained with accuracies consistent with the product require =ents.
The suppliers must be able to identify the instruments which are under the controlled calibration and test program, as well as including the procedures and periods of time at which calibrations must take place. Standards of calibration are required-to be traceable to National Bureau of Standards values.
The use of secondary or reference standards are acceptable provided traceability to the National Standards can be de=onstrated.
1 1
1 3 3 2.13 Handling, Storage, Shipping, and Preservation m
B&W-NPGD establishes requirements for shipping, handling, installation, and storage of B&W-supplied equip =ent.
These requirements are =ade available to the applicant to pernit his planning for achieving these require =ents.
When s_4 necessary, the instructions advise when sp2cial protective environments are necessary.
I 1B-12d Amend =ent No. 8 2 /9/70
n V
Suppliers of equip:ent to B&W-NPGD are required to have written procedures
(,/
covering handling, storage, shipping, and preservation as dictated by product means.
B&W-NPGD reviews and approves the procedures prior to release of equipment for ship =ent.
1 3 3 2.1h Inspection, Test, and operating Status Suppliers are required to establish and maintain written procedures ecvering inspection status control syste=s and supporting documentation to provide pcsi-tive means to identify status. The capability of a supplier to =eet thir quality requirement is a responsibility Of B&W-NPGD QA, and is determined by preavard and pericdie in-procees audits.
1 3 3 2.15 Nonconforming Material, Parts, or Cc=ponents In accordance with the Nuclear Quality Program Requirements Specification, suppliers are required to have written procedures approved by B&W-NPGD and governing the identificaticn, centrol, and disposition of =aterial, parts, and cc=ponents that do not =eet specification requirements.
Repair of non-confor=ing =aterials, parts, or cc=ponents shall be in accordance with docu-mented procedures available to B&W-UPGD upon request. As applicable, B&W-NPGD procurement documents identify certain ec=penents for which the supplier sub-mits his written repair procedures to B&W-NPGD for approval prior to release for manufacture.
1 3;3 2.16 corrective Action U
The B&W-NPGD quality program includes require =ents that suppliers establish and= maintain *vritten procedures covering-an effective
- corrective' action' system which reports to the supplier's crganization all conditions which could have an adverse effect on final product quality.
By =eans of an" internal audit progra=, die supplier's quality organization is responsible for reporting and assuring : hat follow-up corrective action by the responsible work functions l.
is i=ple=ented.
B&W-NPGD QA perfor=s an in-process audit to determine supplier effectiveness of his corrective actica progra=.
f 1 3 3 2.17 Quality Assurance secords Suppliers are required to =aintain Tecord systems documenting the resul+,s of tests, inspections, special processes, deviations, and material certifications.
. Procure =ent. documents for each ce=ponent define the specific records which =ust be =aintained and supplied to B&W-NPGD during the period of supplier perfer=ance as supporting docu=entation to demonstrate product confor=ance to specification
-requirements.
The B&W-NPGD Project Manager =aintains his contract QA Docu-
=entation. files - per established record-keeping procedures contained in the "NPGD Procedures Manual. " Disposition and retention of QA Documentation files are in accordance with the Midland project require =ents.
1 3 3 2.18 Audits A
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surveillance by =eans of in-process audits of supplier =anufacturing progrars The B&W-NPGD Quality Assurance progra= requires preaward audits and postavard to assure adherence to written quality program procedures previcusly approved g,j by'B&W-NPGD. The B&W-NPGD Quality Assurance organization rerfor=s these audits 00PM 13-12e Amendment No. 8 E
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k Table 1 s
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Quality Assurance Essentiality Level Classification Basis Essentiality Level 1 Ccmponents Failure could directly cause the postulated design base accident.
Nonredundant components required for the mitigaticn of the consequences of the postulated design base accident.
Essentiality Level 2 Components Failure could result in the release of amounts of Tadioactivity which-exceed the plant boundary limits as specified.in 10 CFR 20.
All engineered safeguards and reactor protective system components mot classified Essentiality Ievel 1.
Essentiality Level 3 Components
,.es
(
All components not classified Essentiality Level 1 or 2.
Failure of this class of components may result in release of radioactivity but not in excess of the plant _ boundary. limits _as specified.in.10. CFR,20.
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1B-12g 00216 Amendment no. 8 2/9/70
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Table 2 V
Quality Progra= Requirements For Ecuittent Essentia2.ity Levels 1.
The folleving establishes the =inicus specific quality progran requiremento as specified in 3%7 Huclear Quality Program Requirement: Specification:
Eculptent Essentiality Level Section Quality Program Requirements 1
2 1.0 Scope X
X
- 2. 0 Organization X
30 Quality Assurance Program X
4.0 Procurement Document and Scurce X
X Control 5 0-Instructions, Procedures and X
X Drawings
>^
6.0 Document Control X
X V
T.0 Control of Purchased Material, X
X Equipment and Services
'8.0
. Identification and Centrol of X
Materials, Parts and Components 90
- Centrol of Special Processes X
X 10.0 Inspection X
X 11.0 Test and Inspection Control X
12.0 Calibration of Measure =ent and X
X-Test Equip =ent 13 0 2 reservation, Packaging, Handling, X
X Storage and Shipping 14.0 Inspection, Test and Operating X
X Status iO 15 0 Nonconforming Material, Parts or X_
X g
A Ccaponents V
16.0
.Correctiire Action X
OOP. i Lene.=ent no. a 13-12h 2/9/70
t V
Table 2 (Contd)
Quality pmgram Requiraments For Equirrent Essentiality Levels (Ccntd)
Equirrent Eccentiality Level Section Ouality P*cgram Requirement:
1 2
17.0 Quality Assurance Records X
X 18.0 Audits X
2.
The quality progran requirements for Essentiality Level 3 are variable depenrHng on.the particular.use and service.cf..the. individual.cc=ponents involved, rather than using generic quality program requirements as is the case of Levels 'l and 2-Therefore, the quality program requirements for. level 3. components are covered in the applicable equip =ent specifica-tion rather than by invoking a generic quality program specification. In general, the quality program requirements for this category, in addition to those contained in the applicable codes and standards, are intended to ensure that the ec=penent meets-the specification requirements. When nececcary, the procurc=cnt documents shall rcquire that a thorou;;h per-L formance test program be conducted in accordance with vritten precedures V
and that documentation of the test results be available.
For cases where the cc=ponent being procured las been previously tested, a written de-ceription of the test program as well as a documented description of the test results vould-. suffice..In essence, the quality program require =ents for this' level ec=ponent are the best cor:=creial practice.
t r'
k v
00?i.8 i;,memen yc, 3 13-121 2/9/70
(~ f BULA POWER SUPb ORGANIZATION CHART
\\
SENIOR VICE PRES ELECTRIC OPERATION DIRECTOR OF DIRECTOR OF COAL SUPPLY NUCLEAR FUEL SUPPLY VICE PRES POWER RESOURCES.
PLAN NING &, OPER ATION MANAGER BULK POWER SUPPLY ELECTRIC PRODUCTION ELECTRIC Q
SUPT. CONVENTIONAL ELECTRIC PRODUCTION O
EQUlPMENT SUPT. NUCLEAR
?)
- M MET.
SE NIOR SUP.
MECH. INSP-NUCLEAR PLANT E NGIN E ER ENGINEER (WELDING)
FUEL MA JAGEMENT
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s p y.
SUPE RIN TE NDE NT PHYSICIS T u
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GEN. MECH.
1 N
l g A4 AINT. SUPV.
ulDLAND 4
OPER ATIO N S 1.,
E NGINE E R
)i 7
NUCLEAR SE NIO R FUELS ENGINEER ENG! JEER
T
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< Q l.3.4 CONSUMERS POWER CCMPANY ORGANIZATION DURE!G A'ID AFTER INITIAL FUEL LCADING b./
The Bulk Power Supply Department is responsible for all nuclear plant opera-tion and naintenance. This includes such activities as fuel design, license changes, review of plant operation, equip =ent and system changes and general supervision.
Electric Production Superintendent - Nuclear The Electric Production Superintendent - Nuclear has the respcnsibility for all nuclear activities within the Bulk Pcuer Supply Department.
The following personnel reports to the Electric Production Superintendent except that the Director of Nuclear Fuel Supply reports to the Senior Vice President in charge of Electric Operations:
Nuclear _ Fuel Management Superintendent The Nuclear Fuel Mana'gement Superintendent is responsible for the technical direction of the operation of Consu=ers Power Cc=pany's nuclear reactors and the management of the Company's nuclear fuel resources. This includes per-for=ance of the necessary reactor core calculations to provide for safe, re-liable and econo =ic nuclear plant operation and the supervision of the nuclear fuel quality assurance programs.
k Senior Reactor Engineer v
The Senior Reactor Engineer is responsible for physics design, review of plant operations (reactor core), physics support for licensing and for the develop =ent of methods, codes and verification pertaining to core physics.
Nuclear Fuels Engineer The Nuclear Fuels Engineer is responsible for the preparation of the specifi-cations for fuel fabrication and =echanical and thermal-hydraulic design and for conducting of the nuclear fuel Quality Assurance progra=. The Nuclear Ruels Engineer provides support for licensing and the development of =ethods, codes and verification of ther=al-hydraulic para =eters.
Health Physicist The Health Physicist is responsible for all nuclear plant operations pertain-ing to radiation protection, radioactive release and environmental sa=pling.
The Health Physicist provides support for licensing and is the liaison be-tween CP Co and the State, LocQ and Federal Government.
Nuclear Overations Engineer (Midland)
The Nuclear Operations Engineer for Midland v4H provide support to the Elec-O tric Production Superintendent concerning the Midland plant operation, license hj changes, license reporting require =ents and will act as the CP Co liaison to manufacturers and State and Federal Govern =ent agencies.
v 00P.20 13-1h A=endment No. k abwe
i i
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The Nuclear Operations Engineers for Midland will ccordinate all Midland
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plant operations and maintenance with other electric production functions.
plant Superintendent The "idland Plant Superintendent is responsible for the cperation cf Midland plant. He vill be responsible thrcugh the plant staff for acceptance-testing all plant equipment, initial fuel leading and power testing. The Plant Superintendent is also respcasible for maintaining plant Operating cenditiens that are in ec=pliance with the operating license issued by the Atc=le Energy Cc==issicn to CP Co.
Through his responsibility for plant operaticn flows the responsibility for quality assurance measures taken in the course of equipment acceptance as well as maintenance and repair, Director of Nuclear Puel Supply The Idrector of Nuclear Fuel Supply is aesponsible for the specifications, acquisition and delivery of nuclear fuel including fabricatien and re-processing.
Electric Producticn Superintendent The Electric Production Superintendent is responsible for all conventienal plant activities. These activities include scheduled maintenance programs,
,(
'1
.all water chemistry, welding of all =etals associated with stea generating
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equipment, =etallurgical assistance and general plant operations.
%/
The Electric Production Superintendents (Nuclear and Conventional) report to the Mana6er of Bulk Power who is responsible for all operations of the Bulk Power Department.
The Bulk Pcver Supply Department is responsible for all in-plant electric?.1 equipment which includes maintenance and performance.
The General Supervisor of electric equipment is responsible for this function and all reports to the Manager of Bulk Power Supply Department.
v 0021 1B-15 Amendment No. 4 euhufe
( D (O
(6 CONSUMERS POWER CO. ORGANIZAT ON -DESIGN THROUGH CONSTRUCTION SENIOR VICE PRES E N G. & CO N ST.
I I
I DANAGEh MANAGER GEN. PL4NT ENG.
G E N. PL A NT CON ST.
I i
1 I
MECH.
CIVIL NUCLEAR PROJECT QA FIELD ENG.
ENG.
ENG.
ENG.
ENG.
SUPT I
l L
-_q I
I i
FIELD QA FIELD ENG.
E N G'S.
- J ccN i
a R
8
- - - - DENOTES FUNCTIONAL RESPONSI DILITY RE h
- _ = _
4 1.h IMPLH4ENTATION CF CP CO CUALITY ASSURANCE PROGF14! FRCM i
b/
DESIGN THRCUGH CCNSTRUCTION i
CP Co has assigned the basic portion of its Quality Assurance program to Bechtel. Bechtel vill perform, therefore, the independent audit of Quality Control programs during the following design and construction periods:
4 a.
- Design, b.
Procurement.
i c.
Manufacturing.
d.
Cleaning, shipping and storage.
e.
Construction.
CP Co vill perform audits of the Bechtel Quality Assurance program. The Bechtel program will consist of essentially the following:
1.h.1 DESIGN During the designing of the plant, an audit vill be performed by technically qualified people other than the design group assigned to this particular proj-
,A ect. This audit will-consist of reviews such as the following:
k 1.
Functional analysis of system: and components.
9 2.
Compatibility of-the systems and compone.ts.
3 Proper use'of materials.
4.
Code conformance.
5 Maintenance and repair accessibility.
6.
In-service inspection accessibility.
l.h.2 I)ROCURH4ENT Material and equipment specifications and purchase orders vill be reviewed to determine that:
1.
The component or system when installed will conform to that specified in design and function according to the functional specification for-that particular component or system.
2.
Quality Control vill be properly perfor=ed by the vendor, subvendors, contractor or subcontractors.
hj 3
Provisions are included for Quality Assurance inspections and audits W
bytheOwnerand/orOwner'sagent. These inspections will include v.
subvendor's or subcontractor's shops.
N Amendment No. 4 13-17 cul% M CD
)
/
h.
Deviations frc= naterial specifications or dimensienal tolercnces g,j vill be allowed only upon approval by the naterial purchaser.
5 The ec penent or syste= vhen installed vill be in accordance with applicable codes or statutes.
6.
Quality of verkranchip is well defined.
7 Held points for witness inspecting er testing are delineated.
3.
All special fabricating, cleaning, packaging, special handling, ncndestructive testing, performance testing and shipping pro-cedures are delineated.
9 A listing of all required docu=ents and their disbursements is included in the specification and purchase order, l.h :3 MAWFACTURING The Quality Assuranca performed during manufacturing vill establish that the component or system will be as specified in the material or equipment speci-fications and purchase orders. This vill be acecaplished by shop inspection and audit visits perfor=ed by the 3echtel QA group with surveillance visits by CP Co personnel.
l.h.h CLEARING, SHIPPING rid STORAGE
\\*#
Quality Assurance vill verify that instructions have been followed by the per-sons responsible for cleaning, shipping, receiving, and storage of material with emphasis on all special precautions that are peculiar to specific ite=s.
All dnmnge to any item and the repair or disposal of that item vill be documented.
1.k.5 CONSTRUCTION CF THE PIM C Quality Assurance vill be performed in the Civil, Mechanical and Electrical Construction secpes of work. The following typifies the areas of interest in each of the engineering scopes:
1.h.5 1 Civil Construction Scope of Work a.
Buildings, dikes and groundwork be in acct-dance with the design specifications.
b.
Concrete slump, concrete strength, CADWELD splice and other tests be performed.
c.
Cleanliness of ecnerete batch plants and reinforcing steel be
=aintained.
~
d.
The concrete mixture be of the proper type and co= position and the method of handling, conveying and placing be according to estab-s2-lished standards.
v
]
b 1B-18 Amendment No. E o /26 /6a
I
!(m)
w /
e.
Reinforcing bars be properly placed and secured.
V f.
The contain=cnt tendens be properly installed and tensioned, g.
Cc=pleted work be properly protected.
h.
Aathorization be given and doc =ented for field deviatiens frc=
design.
.1.h.5 2 Mechanical Construction Scope of We d a.
Cc=ponents be installed in their functional and physical locatiens deter =ined by the design specifications and drawings.
b.
Procedures for velding be qualified and the actual welding per-formed by qualified persennel.
ec. _ Heat treating _be pedmed whenmequired.
d.
Necessary destructive and nendestructive testing be perforced.
e.
E:rriron= ental centrol be established where necessary to perfer critical operaticns.
. f-w f.
Align =ent of pt ps, fans and other equipent be within given
(
-tolerances.
V gi Hydrestatic and other tests required by codes or regulatory bodies be perfor=ed and vitnessed when required.
h.
Authorization be given.and docu=ented for field changes.
1.
Cc=pleted verk be properly protected.
.). Field docu=entation where required be acec=plished.
1.}453 Electrical Construction scope of ve d a.
Proper size vire and type of insulation be used en each circuit as per applicable codes and specificaticns.
'b.
Circuit continuity, resistance, and other nondestructive tests be s
perforted.
c.
Rotation of =otors be proper.
M
'd. %' iring, iinstrumentation and controls be installed per applicable codes, specifications, and the safety analysis report.
,,q e.
Authorization be given and documented for field deviaticus frc=
,( Jj design.
Q
(
. g,.
. s, r
nUO,on5-
,w 13-19
.A=endment No. 4 s
9/26/69
Y f.
Co=pleted work be properly protected.
%./
g.
Field documentation, where required, be accomplished.
15 PREOPERATIONAL TESTING A co=prehensive field testing program for the Midland Units 1 and 2 vill be conducted to insure that equipment and systems perfor= in accordance with design criteria. The CP Co Generating Plant Engineering Department vill be responsible for the written procedures for the various tests.
Each test pro-cedure vill be written by either CP Co, B&W or Bechtel and reviewed for adequacy by the other appropriate party or parties.
The CP Co Generating Plant Construction Department vill be responsible for the i
administration of the perfor=ance of the tests including collection of the data.
CP Co Project Engineer -vill be responsible for -initiating the review -and eval-uation of the test results by CP Co, Bechtel and B&W.
The test progrc= for each unit will begin about nine months before the iespec-tive reactor fueling. Upon completion of the installation, the individual components and systems vill ~be tested and evaluated. The testing program vill be perfomed according to detailed predeter=ined testing techniques and pro-cedures. Field analysis and more detailed office analysis of test results vill i, j'
-be'made-to,rerify-that' systems and components are perfoming satisfa~ctorily or M
to reco= mend.necessary corrective action.
In general, the types of tests vill be classified as hydrostatic, functional, electrical, and operational.
Operational tests vill involve actual operation of the system and equipnent under design conditions or simulated design conditions. Functional tests vill verify that the system or equipment is catable of perfoming the function for which it is designed. The prefueling test program is su m rized in Table 1-1.
Engineered safeguards' of each nuclear unit will be tested as part of the pre-fueling test program defined and sumrized in Table 1-2.
The objective of each functional test is to determine that major components are properly activated by safeguards signals and to measure performance for j
comparison with component specifications and the system require =ents.
The
^
. objective of the operational tests is to de=onstrate the perforrance of sys-tems in each of their operating codes.
Q) v 00226 13-20 Amendment no. 3
f k
Table 1-1 j
Y Prefueling Test Progrs=
l Func-Elec-Opera-Hydro ticnal trical tional 1.
Reacter Building and Penetrations Leak Rate Test.
X 2.
Electrical Systems X
X l
3 Control Rod Drives X
X i
4.
Co=ponent Cooling System X
X X
5 Decay Heat Re= oval Syste=
X X
X X
6.
Pressurizer Quench Tank X
X 7
X Relief Valves (Bench Test)
I '
([,
8.
Chemical Addition Gystem X
X X
X V
9 Sampling System (Reactor Coolant)
X X
X X
10.
Makeup and Purification System X
X X
X
- 11. Reactor Coolant Pu=ps X
X X
, 12 Nuclear Instrumentation Cable Tests X
4-
- 13. Nuclear Instru=entation and Protection Syste=s X
X
_1k.
Integrated Control Syste=
X X
X-15.. Reactor and Auxiliary.Syste=s Nonnuclear Instru=entation X
X X
- 16. Reactor Coolant System X
.17. -Reactor Conlant System Hot Functional Testing X
X X
- 18. Core Flooding System X
X X
- O
.A J-ty
.O 003?.7 13-21
'A=end=ent No. k.
nhfdde
P
'\\
\\
Table 1-1 (Contd)
V Func-Elec-Opera-Hydro tional trical tional 19 Reactor Building Fuel Handling System X
X X
- 20. Fuel Handling System for Auxiliary X
X
'X Euilding
- 21. Area Radiation Monitoring Systems X
X 22.
In-Core Monitoring System X
X X
23 waste Disposal System X
X X
Th. ' Fuel Pool ' Cooling ' System X
X X
25 Shield Cooling System X
X X
26.
Emergency Power Systems Tests X
X X
27 Initial' Fuel Loading X
' O) d'v~a Table 1-2 V
Engineered Safeguards Test Program 4
l.., High-Pressure Injoction Functional test for initiation and perfor=ance of valve operators a.
and pumps.
b.
Operational test for initiation, delivery of high-pressure injection flov, and system control in each redundant safeguards operating mode.
I 2.
Low-Pressure Injection Functional test for initiation and perfor=ance of valve operators, a.
pumps, and heat exchangers.. Heat exchanger testing will cover the specified rarge of-flows and temperatures.
b.
Operational test of initiation, delivery of low-pressure injection af. low,.and system. control in each redundant safeguards code and the on-line test mode.
3 Service water Systems O
O)
-d Functional test for initiation and performance of valve operators, a.
pumps, and heat exchangers.
D b.
Operational te.st for initiation and perfor=ance..of each cooling loop.
00228 13-22 Amend =ent No. 4
A) i; Table 1-2 (Contd)
V 4.
Core Flooding Tanks Functional test for remote operation of stop valves, opening of check valves, and test of nitrogen cover-gas pressure control.
5 Reactor Building Air Recirculation Functional test for initiation of valve operators, pumps, and fans.
Cooling water flow in each cooler to be verified.
6.
Reactor Building Spray System a.
Functional test for initiation and performance of valve operators and pumps.
b.
Operational test for initiation of spray pumps. Establish propor-tional rate of apray water delivery to spray headers (with return through-test line). Demonstrate flow through spray heads using air or smoke.
Demonstrate operation with pump suction taken from bor-ated water storage tank.
,m)
~7
.. Reactor-Building Isolation
./
/
Functional test for closure of all valves on prescribed reactor building
%=/
penetrations. Test to include operation of valves normally open only for specified short-term functions such as in the purge system and the emergency sump drain lines.
Building leak rate at design pressure to be established.
8.
Intecrated Engineered Safecuards Test Functional test to demonstrate _ sequencing of active components in high-pressure injection, low-pressure injection, service water cooling, reactor building air coolers, reactor building sprays, and reactor build-ing air recirculation and cooling in response to actual cr simulated signals.
9 Energency Power and Diesel Leading Test Verify capability of nuclear service buses, power sources, including diesels to. start and support safeguards loads.
Detailed system test requirements will be prepared for all-engineered safety systems when the system designs are finalized and the specific system components are identified, and proper records vill be maintained for all tests.
O
%J v
00MS 1B Amendment No. 4 i
1
.m
O Table 1-2 (Contd)
QW Determination of acceptable performance by each system shall be:
a.
Ccmparison of performance demonstrated in the individual tests to the design requirements.
b.
Proper functioning in the Integrated Safeguards Test.
1.6 OPERATIONS 1.6.1 LunAL FUEL LCADING CP Co will have the prime responsibility for the initial fuel loading of the Midland units. All systems required for fuel loading vill have successfully Inssed all preoperational tests.and vfl 1 have been accepted by CP Co's Bulk Power Supply Department before fuel loading vill commence.
The written fuel loading and systems checkout procedures vill be reviewed and approved by both BFJT and CP Co before fuel loading starts. The 1'tiel loading vill be supervised by CP Co plant staff personnel who will have obtained cold senior operator's licenses for the Midland units. The fuel loading vill be performed by the normal plant operating personnel who will have been trained h(]/
in nuclear plant operations, but who.might~not_ hold..RO licenses at.this stage of plant start-up.
O 1.6.2
' INITIAL OPERATION Initial operation vill include all testing from zero power level to rated power of the primary system. This includes all plant auxiliary systems and turbine generator system.
The written procedures for the complete power test program vill be prepared by CP Co plant staff personnel. These procedures will be reviewed by CP Co's Engineering Department, the General Electric Ccmpany (turbine generator manu-facturer), 3&W (nuclear steam system) and other pertinent equipment suppliers.
The initial operations vill be performed by the normal plant operating personnel.
1.6 3 OPERATIONS All plant operations will be conducted in accordance with operating procedures yreviously approved by the Nuclear Operations staff of the Sulk Power Supply Department. These operating procedures will contain instructions for all modes of opmtion, :such as nor=al operation, nemergeney operation and. site emergency operation.
These procedures will be reviewed quarterly by the plant operating staff. A (N
procedure change may be recommended and approved by the plant staff providing
)
the change does not involve plant safety. All changes that could possibly in-volve plant safety vill be reviewed and approved by the Nuclear Operations g
- staff of the Bulk Power Supply Department under the supervision of the Electric
- Production Superintendent - Nuclear before placing into effect.
13-2h 00230 Amend =ent No. 4 e
J'
/
.,\\
r\\
/.
'~'
Those systems that are important to plant safety will be tested periodically N,f and a performance record will be also maintained. Any significant change frcm previous test or a change in operating performance will be reviewed by the Plant Review Cc==ittee and evaluated.
The Plant Review Ccamittee is ecmposed of technical supervisors assigned to the plant and respcasible for all phases of plant operation.
These personnel will meet the minimum qualificaticns of Section h of the Propcsed Standards for Selection and Training of Personnel for 2;uclear Pcwer Plants proposed by the A:iS-3 Committee, Draft :lc 9, dated July 3, 1069, or any subsequent approved revisien.
The ec= position and responsibilities of this ectmittee shall be as outlined in the Technical Specificaticns for Mid-land Plant.
Those items of significance will be also reviewed by the Nuclear Operations staff of the Bulk Pcwer Supply Department.
1.6.4 FIANT MCDIFICATIO:!S All modifications to equipment or systems which are important to plant safety will be reviewed by the Plant Review Cc==ittee and the Nuclear Operations staff of the Eulk Power Supply Department.
The normal procedure will require that the Plant Review Cc==1ttee review the subject change and make a recc==endation to the Nuclear Operatiens staff. The Nuclear Operations staff will review the recc== ended change and reply with a written recc==endation.
n A
%/
J
,m s
007.',33.
v 13-25 A=endment ?io. h
O CONSUMERS POWER CCMPANY
"\\j Midland Plant QA Program Plan INTRODUCTION The organization, administration and assign =ent of respcnsibility for Consumers Power Ccmpany's (CP Co) Quality Assurance Program is described in Appendix 13 of the Midland Plant PSAR. Ecv this program will be implemented is stated be-low and is referred to as CP Co's Midland Plant Quality Assurance Program Plan (QA Plan). Revisions to this plan are subject to review and approval by CP Co Manage =ent.
The objectives, definitions and organizaticn of CP Co's Quality Assurance Pro-gram are identified below:
OBJia;nVJ_lS i
As part of the overall CP Co Quality Assurance Program, the Midland nuclear plant Quality Assurance objective is to yield =aximum confidence that the plant is designed and constructed.so that it can and will be operated without undue risk to the health and safety of the general public and plant operating personnel.
Of equal i=portance as an objective of our Midland Quality Assurance procedure is the efficient and reliable performance of the plant. Close scrutiny of the de-r3 sign.and procurement phases of a plant can, at times, identify problem areas
(#l before they interfere with the schedule, thus assisting in a timely plant avail-ability.
The Quality Assurance Program will start with the design phase and proceed throughout the construction and operating phases of the plant life.
DEFINITIONS QUALITY C0h'IROL Quality Control is the detailed and syste=atic inspection, testing, and docu-mentation program to insure that the caterial, process, component, system, er facility is in accordance'with Tredetemined quality requirsnents. Quality Centrol is further used to detemine that the syste=s and components are built according to design. It is the first line of control and, as such, is the re-spensibility c' the organization perfor=ing the actual work, such as: the Enginecr-Architect in the design; the Vendor in shop construction; the Con-structor in the installation and erection; and the Owner during operation.
QUALITY ASSURANCE Quality Assurance is an independent audit to establish the effectiveness of the Quality Control programs throughout the design, construction and operating phases of plant life. Quality Assurance is the responsibility of vendors, sub-vendors, contractors and subcontractors, with the overall or final responsi-bility by the Owner.
O 00332 V
1
OQ ORGANIZATION All phases of design and construction prior to initial fuel loading are the responsibility of the Senior Vice President in charge of Generating Plant Engineering and Generating Plant Construction.
Reporting to this Senior Vice President is a Manager of Generating Plant Engineering who has responsibility of the design, procurement, =anufacturing and shipping phases of the Project.
The Manager assigns a me=ber of his technical staff to be Project Engineer for this particular project.
The direction and coordination of the QA progra: frca design through construc-
-tion is -the responsibility of a Quality Assurance Engineer who reports to the Manager of Generating Plant Engineering.
The Manager of Generating Plant Construction is responsible for plant con-struction and preoperational testing.. Reporting to him is a Field Superin-tendent who is responsible for the overall construction of the plant.
Bechtel vill be the Plant Constructor and vill have respcnsibility for field QC.
CP Co's Field QA Engineer, under the functional direction of the Generating Plant Department's QA Engineer, will perfo m proper surveillance of Bechtel's QC-QA program to detemine the program's effectiveness.
The Field Quality Assurance Engineer vill have the help of other engineers of the Engineering, Construction, and Operating Departments who are specialists in their fields.
I,D V
,3 N
]
00233 2
1
O O
O CONSUMERS POWER CO. ORGANIZATION -DESIGN THROUGH CONSTRUCTION 1
5 SENIOR VICE PRES EN G, & CONST.
I i
l 1
MANAGER MANAGER GEd. PLANT ENG:
GE N. PL A NT CONST.
I I
I I
I I
i W
MECH.
Ci v li.
NUCLEAR PROJECT QA FIELD ENG.
E N G.
ENG.
ENG.
ENG.
SUPI L-q I
i e
FIELD QA FIELD O
E N G*S.
ENG.
.)
9 l
. t. A o
- -- - DENOTES FUNCTIONAL HESPONSI DILITY
rm SCOPE The CP Co's Quality Assurance Progra= enec=gsses all phases of the project including the design, procure =ent, shipping construction, preoperational testing, fuel leading, operation, refueling and naintenance. Overall re-spensibility for the quality Assurance Progra= rasts with CP Cc.
The de-velop=ent, imple=entation, coordination and documentation of the QA Prcgra=
frc= design through censtruction are the respcasibility of the CP Co QAE.
The respctsibility for design, pree"-a~" of equip =ent cther than the USS and turbine generaters and construction of the plant has been assigned to the Eechtel Corporation.
Dehtel vill perfo= the QA and QC for 71 ant engineering, shop fabricatien (including NSS, except for fuel), field fabrication and construction.
Bechtel's program for fulfilling their Quality Assurance activities is described in the attached document, "Bechtel Corporation - Pcver and Indus-trial Division - Quality Assurance Plan for Midland - Units 1 and 2."
Further detail procedures and 3echtel policies are described in 3echtel's
" Nuclear Quality Assurance Manual - Power and Industrial Division."
Bechtel's Trogra= ds i=plemented by the Bechtel Quality Assurance Engineer as described in these documents.
The Babcock and Wilecx Cc= pny has a Quality Assurance Progra= for the
[]
. nuclear steam system. The acope of the 3&W Progra= includes the design,
(/
fabrication, shi; tent and shop testing of the cc=penents they furnish. The program is ad=inistered by a separate Quality Assurance crganization and its imple=entation is described in Appendix 13 of the PSAR.
I=plementation of CP Co's QA Program is described belev. The first four sec-
-tions of the QA Plan cover design,-procure =ent, construction and preoperational testing of items designated on the Q-List. A =ajor subdivision's Q-List is included in the attached Bechtel QA Plan and is representative of these struc-tures, syste=s and cc=ponents which will be subjected 'o the QA Progra=.
Engineering and Quality Assurance functions are descri. sed under each project phase.
Table 1 st-a-izes responsibilities for engineering, quality Centrol and Quality Assurance during the design, procure =ent, construction and preopera-tional phases of the Midland project. Overall responsibility for the Quality Assurance Progra= rests with CP Co.
,rh-t
)
pg 00?35 a
p
^X
,(A'V)
{
s
\\ -
Sheebz of 6 Table 1 Midland Plant Functional Responsibilities (Refer to last sheet for definitions and footnotes.)
A E
F G
~
~B C-D
~
~
~
Design Engg Desigii Engg
~
Functional &
Structure or Inher-Construc-Preoperational Structure, System or Equip Criteria System Layout face Procurement tion Tests Component Orig QC QA Orig QC QA Review Orig g QA QC QA Orig _ QC QA Prestressed & Rein-forced Concrete B
B
?,
B B
B B
V V, B B
B
B B
B B
B B
V, B B
B B
'B B
B B
V V, B B
B u
CP CP CP CP Structural Steel B
B B
B B
B B
V V, B B
B (V)2 (y)2 g
Q Emergency Reservoir B
B B
B B
B B
V V, B B
B
&' Pipeline CP CP CP CP Ventilation Chimney B
B B
B B
B B
V V, B B
~ Reactor Coolant &
B&W V
(V-B&W)3 B
Pressure Control (B)1 B
B CP (B-B&W)'
g System - B&W Items CP CP CP ct.
g Nu Reactor Coolant &
B B
B B
B B
B B
V, B B
$P Pressure Control (B&W)b CP (B&W)5 CP CP CP (B-B&W) d c)
System - B Items
f(
ff'\\
f "d
Sheebv'of6 Table 1 (Contd)
A B-C D
E F
G Design.Engg Desi s Engg
~
Functional &
Structure or Inter-Construc-Preoperational Structure, System or Equip Criteria System Iayout face Procurement tion Tests Component Orig QC QA Orig QC QA Beview Orig g QA QC QA Orig QC QA aMakeup & Purifica-B&W B&W B&W B
B B
B B&W (V-B&W)3 B
CP (B-B&W)
- Makeup & Purifica-B B-B B
B B
B B
V V, B B
( B-B&W),'
tion System -
CP CP CP CP B Items Decay Heat Removal B&W B&W B&W B
B B
B B&W Y
(V-B&W)3 B
B CP CP CP System - B&W Items (B)1 (B&W)E B&W B
( B-B&W)
Decay Heat Bemoval B
B
$1 B
B B
B B
V, B B
( B-B&W)j' O
System - B Itetits CP CP CP CP O
$k Core Flooding Syo-B&W B&W B&W B
B B
B B&W (V-B&W)3 B
B CP CP CP tem - B&W Items (B)1 (B&W)5 B&W B
CP (B-B&W)b CP CP CP Core Flooding Syo-B B
B B
B B
B B
Y V, B B
( B-B&W)y' tem - B Items CP CP CP CP g
Reactor Building B
B B
B B
B B
V V, B B
( B),'
g Spray Syatem CP CP CP CP l}'
- S, Component Cooling o
B B
B B
B B
B V
V, B B
( B);'
,g
- N
- a:
I U
- Gaseous Radwaste B
B B
B B
B B
V V, B B
System CP CP CP CP (B)I' e, em
f3 p
j"~\\
N)
She -j of 6 Table 1 (Contd)
A B
C D
E F
G
~
Design Engg Design Engg
~
~
~
~
Functional &
Structure or Inter-Construc-Preoperational Structure, System or Equip Criteria System Layout
, face Procurement tion Tests Component Orig QC QA Orig '
QC QA Review Orig g QA QC QA Orig QC QA Containment Isola-B B
h B
B B
B.
V V, B B
B CP CP CP tion' System CP Ci>
( B)
Main Steam System B&W B&W B&W B
B B
B B&W V
(V-B&W)3 B
B CP CP CP (Thru First Isola-(B)1 (B&W)5 B&W B
CP (B-B&W) tion' Valve) -
CP-CP CP B&W Items Main Steam System B
B h
B 5
B B
B V
V, B B
B CP CP CP (B-B&W)b (Thru First Isola-Ci' CP CP CP tion Valve) -
.m#
B Items feed-WaterSystem B&W B&W B&W B
B B
B B&W V
(B-B&W)3 B
B CP CP CP g (Thru First Isola-(B)1 (B&W)5 B&W B
CP (B-B&W) g tion Valve) -
Feed-Water System B
B h
B B
b B
B V
V, B B
B CP CP CP (Thru First Isola-CP CP CP CP (B-B&W) tion Valve) -
B Items-
B B
B B
B B
V V, B B
{
( B) m S. #Firefighting Sysbem B
B B
B B
'B B
V V, B B
~d a3 Diesel Oil System B
B B
B B
B B
V V, B B
i l
AFFENDIX 13 V
TA3LE OF CC:ITE:ITS (Centd)
Section Fage 1.6 CPEPATIC:IS 13-2h 1.6.1 I:iITIAL Fi1EL LCADI:iG 13-2h i
l.6.2 INITIAL OPERATIC:I 13-2h 1.6.3 OP::3ATIONS 12-2h 1.6.k PLANT MODIFICATIONS 1B-25
\\
,(-
V
(
v 00239 13-11
- - - - - -... - - -. - -. - - - - - - - - - - -Amendment :To. k
. /~N.
O fN
'V Sheet !+ of 6 Table 1 (Contd)
A B
C D
~
~
~
E F
G Desi[gn Engg
.DesigIi Engg
~
Functional &
Structure or Inter-Construe-Preoperational Structure, System or Equip Criteria System layout face Prociarement tion
' Tests Component Orig _ QC QA Orig QC QA Review Orig QC QA QC QA Orig QC QA
- Reactor Building B
B B
B B
B B
V V, B B
B CP CP CP Ventilation System CP CP CP (V)2 (V)2
( B);'
- Auxiliary Building B
B B
B B
B V, B B
B CP CP CP Ventilation System CP CP CP (V)2 (y)2 (B)
- Radiation Monitobing B
B B
B B
B B
V, B B
' Emergency Diesei B
B B
B B
B B
V V, B B
B CP CP CP Generators CP CP CP CP
( B) '
- Reactor Building B
B B
B B
B B
V.
V, B B
C* Auxiliary Building B
B 5
B N
B B
V V, B Il B
Fuel IIandling Edulp-B&W B&W B&W B
B B
B B&W V
(V-B&W)3 B
B CP CP CP (B-B&W)b ment - B&W Items (B)1 (B&W)3 B&W B
- Fuel liandling Equip-B B
b B
E B
B B
V V, B B
( B),'
J ment - B Itemd CP CP CP CP N
kg Switchgear Engi-B B
b B
B B
B V
V, B 11 B
RP neering Safeguards CP CP CP CP bco Station Pwr Trarisf B
B B
B B
B B
V V, B B
She of !-
Table 1(Contd) 1 A
-B C
~
~
D E
F G
~
Design Engg Desidi Engg Functional &-
Structure or Inter-Construc-Preoperational t
l Structure, System or Equip Criteria System Iayout face Procurement tion Tests Combonent Orig QC QA Orig QC QA Review Orig g QA QC QA Orig QC QA
-V, b Load Centers Engg B
B
'B-B.
b B
B V
B B
Motor Control Center B
B B
B B
B B
V V, B B
( B-B&W)b Engg Safeguards CP CP CP CP Switchboard & Elec-B B
B B
B B
B B
k V, B B
B CP CP CP trical Panels CP CP CP CP
( B) '
Raceways Associated B
B B
B b
B B
V, b B
B With Engineering CP CP CP CP wA Safeguards Cable Associated B
B B
B b
B B
I V, B B
B With Engineering CP CP CP CP Q
' Sareguards f
G Instrument Cable.
B B
B B
B B
B V
V, B B
B
[
(Assoc With CP CP CP CP Engg Safeguards) 600 V Control dable B
B B
B B
B B
V V, B B
B Switchboard Wire CP CP CP CP S'
(Assoc With Engg h
Safeguards) a S
125 V Station B
B B
B h
B B
I V, h B
B CP CP CP hy Batteries CP CP CP CP
( B-B&W) y-o cn Battery Chargers B
B B
li B
B B
i V, B B
( B-IRW)
i
.s Sheet-o of 6 Table 1 (Contd)
A
~B C
D G
~
Design Engg Desid En68
~
~E F
~
~
Functional &
Structure c;r Inter-Construc-Preoperational Structure, Systein or Equip Criteria System Layout face Procurement tion Tests Component Orig QC QA Orig QC QA Review Orig QC, QA QC QA Orig QC QA A-c Inverters B
B B
B B
B B
Y V, b B
D-c Buses B
B
.B B
B B
B Y
V, B B
B CP UP CP CP 125 V D-c Dictilbu-B B
B B
B B
E V
V, B B
( B-B&W)
tion Panels CP CP CP CP Containment Elec-B B
-B B
B B
B V
V, B B
B p
trical Equipment CP CP CP CP OON 4
1CO Yi a
R 8"
~
Y O CD
(3 O
MIILAND FIANT FUNCTIONAL RESPONSI3ILITIES. DEFINITIONS AND FOOTNOTES DEFINITIONS ORIG = Originator QC
= Quality Control QA
= Quality Assurance B
= Bechtel Corporation 3&'4 = Babcock & Wilcox Co CP
= Consumers Power Cc=pany V
= Vendor Column A - Structure, Syste= or Cotronent Includes those structures, syste=s and co=ponents on the "Q" list as defined in Anendment No. o.
Where noted by an asterisk, only that portion falling under Class I Seismic Criteria is included.
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Column B - Design Engineering - Functional and Ecuir=ent Criteria Includes those criteria and require =ents which form the basis for the detailed plant design, fabrication and construction. Design criteria =ay be defined in studies, reports, letters, =e=oranda or in the SAR.
Colu=n C - Design Engineerinz - Structure or Syste Layout
. Includes. design drawings such as 2&ID diagrs=s and general equipment or structural layouts.
Column D - Interface Reviews Bechtel is responsible for conducting interface coordination l
and is necessary for the satisfactory and orderly completion of the l
project.
Colu=n E - Procurement
~The =a ntfacture or asse=bly and shipment of structures, sys-tems or components.
Munn F - Construction
,)
The construction and/or erection of components, structures i
or systems at the plant site.
5f Amendment No. 8 2/9/70
(mV)
MIDLAND PLARP FUNCTIONAL RESPONSIBILITIES. DEFINITIONS AND FOOTNOTES (Contd)
EEFINITIONS (Contd)
Column G - Preoperational Tests Those tests conducted after construction and prior to fuel leading to assure integrity of the structure, system or co=ponent.
FOOTNOTES General - The above table represents the broad scope of functional responsibilities and there may be exceptions in detail that may require revisions as the project progresses.
+ - Only that portion of system falling under Class I Seismic Criteria.
1 - (B) denotes CP Co may request Bechtel's assistance in performing surveillance of B&W.
2 - (V) denotes vendor or subcontractor.
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3 - (V-B&W)3 ' denotes' vendor or B&W.
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k - (B-B&W) or (B) denotes with assistance from Bechtel and B&W or Bechtel.
5-- (B&W) denotes B&W furnishes to Bechtel equipment draw-ings required for system.
6 - (B&W) denotes B&W furnishes to Bechtel information such as support requirements.
DESIGN FHASE IESIGN - CP CO -- GENERAL The applicant,~CP Co, is responsible for the overall preparation, editing and presentation of the-SAR and, as such, is directly respcnsible for design cri-teria reflected by the SAR. Bechtel and B&W assist in preparing draft caterial for their responsible areas.
CP Co's mechanical, electrical, civil and nuclear engineers and specialists vill review design criteria, specifications and plant general arrangement, P&ID, single line and sche =atic drawings prepared by Bechtel or B&W.
Distribution of documents for review will be according to -established procedures
,(O which will furnish the QAE with assurance of review by appropriate engineers.
Ov' The QAE will review documents for QC and/or QA require =ents.
00'M Sg Amendment No. 8 2/9/70
[
DESIGN - Q-LIST v
The Q-List consists of critical structures, syste=s and components which re-quire additional design control measures. This list is updated frem time to time and is reviewed and approved by CP Co engineering personnel and QAE in the same canner as other documents.
DESIGN - BECFTEL Bechtel is responsible for the development of plant design criteria necessary for the preparation of component, system and structural specifications and drawings required to construct the Midland Plant.
Bechtel is responsible for preparing specifications and drawings for components they are purchasing and all structures. They are responsible for resolving interface engineering problems with B&W or other vendors.
Be.chtel-prepared purchase specifications shall provide technical information required for 'defininguterial melection, -handling and -identification, size, operating characteristics, functional requirements, code, inspection and docu-mentation requirements. Drawings shall provide infor=atien necessary for the construction, placement or assembly of structures, syste=s and components.
Bechtel shall provide Quality Control and Quality Assurance of their engineering during the Design Phase and shall provide CP Co QAE vith documentation verifying compliance with codes, SAR, and other governing regulations.
(Q -!
DESIGN - B&W
-B&W is responsible for the design.and engineering of the NSS equipment.they are furnishing.
BF-W shall prepare specifications, drawings and other criteria necessary for the. manufacture and operation of their equipnent. B&W-purchase specifications shall ~ provide technical infor=ation required for defining ma-terial selection, handling and identification, size, operating characteristics, functional requirements, code, inspection and documentation requirements.
B&W shall provide Quality Control and Quality Assurance of their engineering during the Design Phase of this project and will provide CP Co with sufficient documentation -to assure compliance with applicable codes and procurement documents.
DESIGN - THANGES Design changes =ay be accomplished through addenda to specifications or re-visions to drawings and will require review equivalent to that provided for the original design. Design changes which Tepresent significant deviations from plant features-involving reviewing nuclear safety aspects presented in the SAR must ~be approved 'by EP Co Senior Tice Tresident in charge of ' Generating Plant Engineering and Generating Plant Construc', ion or his designated representative.
p 00245 6
O DESIGN - CP CO QAE V
The CP Co QAE will perfor= audits or reviews to assure that specifications, design criteria and drawings have been prepared, reviewed and approved by qualified Bechtel or B&W personnel. The CP Co QAE will assure that specif1-cations, design criteria and drawings have been reviewed by appropriate CP Co engineers and/or specialists and vill review same for QA and QC requirements.
The CP Co QAE vill maintain a separate file of the SAR, general project speci-fications and design criteria but may use the project detailed specifications, purchase orders and drawing files for reference.
Documentation for reviews by CP Co personnel vill be naintained by the CP Co QAE.
The CP Co QAE vill randomly audit Q-List cocponent records at B&W and Bechtel to insure independent engineering review of calculations and analysis of critical design data.
DESIGN - CP CO QA FILE DCCUMENTS Documents -to be Tetained in the WCo QA file or are otherwise available after the Design Phase include:
A.
Final specifications.
B.
Verification that Q-List component specifications have been prepared, reviewed and approved by competent personnel.
C.
Verification that the design of Q-List structures systems and components is in confermance with applicable codes, SAR and procurement documents.
D.
Verification that-Q-Lict component specifications have had CP Co reviews.
E.. A copy of the SAR with amendments.
F.
A copy of the B&W and Bechtel QA Program Plans.
G.
CP Co audit reports.
H.
Final drawings.
I.
Verification that the Q-List has been reviewed.by CP Co engineering. personnel.
~J. Procedures used by CP Co for distribution and approval of design documents.
1 PROCURDENT PHASE TROCURDE1T -'UENEPAL Components --for the NSS are either manufactured by B&W or are purchased by them.
All other Q-List cceponents will be purchased by Bechtel.
PROCURDENT - B&W O
V B&W c:ay confer with CP Co regarding their purchase of NSS components but B&W retains the prerogative to select vendors.
00.246 7
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PROCURD4ENT - BECHTEL HOME OFFICE
%)
Bechtel purchases are subject to review and approval by CP Co. Vendors of Q-List items are required to provide a description of their QC/QA programs.
Established procedures will be followed to distribute bid evaluations and purchase recommendations for review by management and engineers.
PROCURC4ENT - BECHTEL CONSTRUCTION The scope of procurement made by Bechtel Construction from the jobsite is jointly established by the Project Engineering and Construction groups and subject to Consumers approval. Critical phases of field procurement activities that may affect job quality are identified and are reviewed by engineering.
Procurement of materials by Bechtel Construction at the plant site vill be allowed only after approval by Bechtel Engineering.
PROCURDfENT - INSPECTION (11ECHTEL PURCHASES)
Bechtel vill make inspection assignments using qualified inspectors. These inspectors vill perform shop inspections in accordance with Bechtel's Shop Inspection Manual. They will. audit vendors' records and obtain all necessary documentation as prescribed in the governing specification and codes. Hold points or witness points may be established in the vendors' QC plan. When this is'done, the inspector shall confirm that he.has witnessed the designated operations or tests.
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When equipment is ready to ship, the inspector shall prepare a " Certified Shop Inspection Report" which shall list documents required and all documents forwarded vith earlier reports or his final report and which chall attect that requirements of the specification and other governing codes have been met.
A copy of Bechtel Inspection Reports shall be sent directly to CP Co QAE.
Additional copies of inspection reports will be transmitted to CP Co's Project Engineer for distribution and review by project personnel.
The Bechtel shop inspectors vill contact CP Co QAE or designated alternates whenever specified hold or witness points are pending or a significant QA problem occurs and normal procedural channels vould require excessive time.
PROCURD!ENT - INSPECTION (B&W NSS)
B&W Quality Assurance personnel vill inspect equipment during manufacture and audit records to determine compliance with procurement documents.
Bechtel inspection of B&W-supplied components will be conducted as described
.below.
Bechtel vill make inspection assignments using qualified inspectors. These inspectors will perfom shop inspections in accordance with Bechtel's Shop
. Inspection Manual. They vill audit appropriate manufacturer's records
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j and obtain all necessary documentation as prescribed in the-governing
%)
8 00.247
O specification and codes. Witness points =ay be established by B&W in the =anu-V facturer's QC plan.
If these points are witnessed, the inspector shall confir=
that he has witnessed the designated operations or tests.
A copy of Bechtel Inspection Reports shall be sent directly to CP Co CAE and B&W Project Manager. Additienal copies of inspection reports will be transmitted to CP Co's Project Engineer for distribution and review by project personnel.
The Bechtel shop inspectors will be instructed to contact CD Co 's CAE cr desig-nated alternates whenever specified witness points are pending or whenever a significant QA problem occurs.
PROCUREEE - CP CO QAE The procurement phase of this project will involve active participaticn of CP Co personnel into inspections, auditing and witnessing tests at nanufacturer's shops. The services of mechanical, electrical, civil and nuclear engineers, as well as speMalists, such as velders, radiographers, chemists and netallur-gists, may be used in nking these shop ' inspections and audits.
Inspections are not scheduled but the following guides will be used:
1.
Any component vill be subject for inspection.
2.
The decision to. inspect or audit a manufacturer vill be influenced by past performance, the component.and inspection reports.
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3 Each Bechtel inspector assigned to the Midland project will be subject to review.
h.
Requests to inspect or audit may be made by Engineering, Construction or Operations.
5 Industry reports regarding ccmponents, =anufacturers or procedures where such affect our QA program will be given appropriate review and action.
Inspection or audit of tanufacturers vill be performed by CP Co QAE or others.
Prior to visiting a vendor, the QAE inspector or auditor vill review the QA file and establish any 1special inspection or audit requirements to supplement regular procedures.
Reports vill be prepared subsequent to an inspection or audit for distribution in accordance with procedures for reviews by such CP Co persennel as the Senior Vice President in charge of Generating Plant Design and Generating Plant Ccn-struction, the Manager of Generating Plant En6 neering, the Manager of Generating 1
Plant Ccnstruction, the Project Engineer, the Operations Superintendent -
Nuclear, the Plant Superintendent and the CP Co Field QAE. The con: cents re-sulting from these reviews will be forwarded to the CP Co QAE for appropriate action.
Ov OOP.48 9
O PROCURE!EIT - CP CO QA FILE DOCU?CiTS b
The QA file vill contain or otherwise have available the following procurement docu=ents at the conclusion of the QA progra=:
1.
Verification by a respcnsible Bechtel engineer that a structure, syste= or component has been designed and procured in accordance with governing documents.
2.
Bechtel inspection reports.
3 CP Co inspection and audit reports.
h.
Purchase orders (technical infor=atien only).
5 Except for radiographs, documentation as defined in B&'d and Bechtel specifications such as:
a.
Material certifications, physical and chemical reports.
b.
Ncndestructive testing certifications.
c.
Major repair details and approvals for such repairs.
d.
Variance reports.
CONSTRUCTICN lp)
CCNSTRUCTION - GENERAL Construction QC and QA. responsibilities. rest with Bechtellut CP Co vill actively participate in field Quality Assurance.
Bechtel engineering vill have a field
. representative,le, their QAE.
"P Co personnel at the site vill include a Con-struction Field Superintendent with Field Engineers and a Field QA Engineer.
CONSTRUCTION - BECHTEL QC Construction responsibility coc=ences with the site acceptance of syste=s, ec=-
ponents or =aterials as delivered and vill terminate when the syste=s, ec=ponents or =aterials are completely installed and erected, cleaned and designated ready for preoperational testing by Bechtel.
Details of Bechtel's field inspection petgm and procedures are described in Bechtel's Field Inspection Manual.
CONSTRUCTION - BECHTEL QA The Bechtel QAE is stationed at the Jobsite after field work starts.
He is a Tield Tepresentative of 'the Project Engineering Team and is wsponsible for sur-veillance of engineering and Bechtel QC activities in the field. He has author-ity to stop work and assure correction of any deviation in quality of construc-tien mater % h and v d - nship. S'he.Bechtel QAE.shall ver:ify that each component, f')
syste= or structure has been installed or erected in accordance with governing V
documents.
00N 9 10
G CONSTRUCTION - CP CO FIELD QAE
.]
The CP Co Field QAE functionally reports to the Generating Plant Engineering Department 's QAE. The Field QAE is responsible for:
1.
Deter =ining that Bechtel's Field QC and QA Progra=s are properly imple-mented and are effective.
2.
Reporting confor:ance to er deviations frc= the Bechtel's QC or QA Progra=s.
3 Deter =ining that proper corrective actions have been applied to deviatiens.
4.
Ascertaining that proper QC and QA docu=entation of Bechtel field con-struction is accomplished.
The CP Co Field QAE will perfom his duties through persistent surveillance at the site.
' Specific Euidelines'for acecmplishment of'CP~Co 71 eld QA are provided in written procedures. Audits will be performed independent frem the nor=al surveillance, inspection, and test progra=s.
Schedules and checklists vill be utilized in assuring adequate. planning for proper audit, visibility of.fabricatien, erection and quality detemining tasks.
Audits vill be made at regulartr irregular intervals, or ty request. They vill
,m be initiated by the CP Co Field QA Engineer and may be perfomed by himself, CP Co construction field engineers, specialists, inspection labs or consultants.
Inspection laboratories or consultants =ay be called upon by the CP Co Field QAE
+o make detailed examinations at intervals or when a particular circumstance may ke their services desirable. They will work closely with the CP Co Field QA
.cagineer.or CP Co. construction. field engineers. A report documenting all as-pects of each visit will be made.
The CP Co Field QAE will assure that equipment at the site is properly protected whether it is in storage or in place.
CP Co field personnel are instructed to report to CP Co Field QAE unsatisfactory equip:ent protection when observed dur-ing routine surveillance of the site.
.The CP Co. Field QAE will.have _ access to a file of Bechtel Shop Inspection Reports.
He vill review these reports and observe potential probles areas.
Problem areas noted en Bechtel field inspection reports are filed for follev-up and later check and verification that proper corrective measures have been per-formed.
When discrepancies or deviations are found during audits or site survel11ance, the CP Co Tield QAE will inform the 3echtel QC and QA Engineers and the CP Co QAE. He vill also file the deviation or discrepancy for follow-up.
At the appropriate follow-up time, the CP Co Field QAE will recheck deviations pg or discrepancies.
If corrective action was perfomed, records are so noted and (j
closed.
If corrective action was not perfor=ed, the CP Co Field QAE will notify the CP Co's Field Superintendent, Manager of Ccustruction and QAE for further resolution.
QQNQ 11
D[b The CP Co Field QAE will audit Bechtel QC for=s and records. He vill witness a portion of nondestructive tests (NM) and may occasionally request additional NW be performed himself. Pe or his assistants vill review field radiographs (RT) 100 percent.
He -ay call upon specialists to review some of the RT and audit field radiographs.
The CP Co Field QAE =ay call upon CP Co's General Laboratory personnel to review field radiographers ' qualificatiens and conduct of operations.
The Field QAE vill perfor or supervise audits including the following:
quality checks on concrete, tendons, piping, equiptent, site storage, radiographic tech-niques, el2ctrical, veld rod control and other items on the Q-List. These au-dits vill be performed in accordance with written procedures.
CONSTRUCTION - B&W B&W will provide erection criteria for equi;nent it supplies and one or more erection consultants to assist CP Co and Bechtel in the interpretation of B&W requirements during the construction.per.iod.
i The B&W site representative shall advise Bechtel and CP Co of any field condi-tions or actions observed which_do not meet B&W requirements.
CONSTRUCTION - CP CO QAE F
The CP Co QAE or his representative vill on an unscheduled and announced or unannounced. basis perform surveillance inspections and audits at the site.
j Audits vill cover both Bechtel and CP Co QA records and will be conducted in the same manner as shop audits.
CONSTRUCTION-- CP CO Fma-QA FILE DOCU!aTG At.the:cenclusion of the: construction phase of this project, the CP Co Field QA files will contain or have access to the following documents:
1.
Final approved specifications and drawings.
2.
A copy of the SAR.
3 A copy of Bechtel's QA Manual and Bechtel's Field Inspection Manual.
4.
Q-List.
5 Bechtel Shop Inspection Reports.
6.
Bechtel certification attesting that syste=s, components or =aterials have been installed, cleaned, erected and are re edy for preoperational testing.
7 Field audit reports.
8.
Record of nondestructive tests.
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(N PREOPERATIONAL TESTING PREOP - GENERAL The preoperational test program is defined as the preparation of test proce-dures, the running of the tests, and the review of test results en equipment and syste=s after they have been installed in the plant. The test program assures that systems are installed as designed and that all systems will funtwion prior to initial fuel loading.
PREPARATION OF PREOPERATIONE TESTS The responsibility for assuring that the preoperational test procedures are prepared and that they are adequate with respect to thoroughness of testing is by the CP Co Engineering Department. The procedures will be prepared by CP Co, Bechtel, and B&W with CP Co assuring that adequate review is given by the two parties to the procedures prepared by the third party.
RUNNING '0F l'Itsut'sttATIONAL"fESTS The responsibility for running the preoperational tests will be with the CP Co Construction Department. They will be responsible for seeing that, in addition to the Construction Dept,-Bechtel, B&W, and CP Co Engineering and Operations review.all test results for adequacy.
PREOF - CORRECTIVE. ACTION 73
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The corrective actions that are required as a result of deficieucies found during preoperational testing shall be conducted in accordance with governing
. procedures _and.shall_be fully. documented.
OTHER PHASES OF QA PIAN As the f.mplementation plans for the remaining phases of the CP Co's Quality Assurance Plan are completed, they will be appended hereto.
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00252 13 I-
O
SUMMARY
OF PROCEDURES AND RESPONSIBILITIES i
INIRCDUCTIOP The organization, admini
- tion and assign =ent of respcnsibility for Ccnsumers Power Ccmpany's JP Co) Quality Assurance Program is described in Appendix 1B of the Midland Plant PSAR.
How the program vill be imple-mented is stated in Amendment o of the Midland Plant PSAR and is re-ferred to as CP Co's Midland Plant Quality Assurance Program Plan (QA Plan).
' Table 1 of the QA Plan su=marizes responsibilities for engineering, Quality Control and Quality Assurance during the design, procurement,
'contruction and preoperational phases of the Midland project.
One of the objectives of this supplement is to clarify the functional respon-sibilities shown in Table 1 of the QA Plan.
The attached copy of j Table.1(Revised 2/2/70)accomplishesthisobjective. The QA Plan also refers to procedures which v.111 be followed in. implementing the QA Pro-gram. 'The other objective of this supplement is to provide in abstract form a description of the procedures which are being assembled for Consumers Pov;r Company's Midland Plant Quality Assurance Manual (QA Manual). '
.QA MANUAL Y
c Consumers Power Company.is in the process of assembling and formalizing
('
a QA Manual.for use by personnel concerned with the Midland Plant QA Program. The Manual vill document the policies, procedures and instruc-tions necessary fo'r fulfilling the QA Program objectives.
The tihle, purpose, scope and headings given in the following abstracts
.are those tentatively being.uced_in the QA. Manual. The procedure number listed for reference vill be replaced by another numbering system.
PROCEDURE NO. 1 - QUALITY ASSURANCE MANUAL 7
Purpose:
This document establishes criteria for preparing and imple-menting QA Program Procedures.
_ Scope:
This procedure shall apply to the design, procurement, construc-tion and preoperational phase of the QA Program.
Mitjor b'eadings: Administration of manual and procedures, manual assign-ment,, preparation and review, revisions and review, procedure designations, impleentation, definitions and abbre'.*istions.
4 g
_Not'e: She...following def,inition.for. quality assurance.shall. apply:
Quality Assurance is-a planned' systematic audit and control of the Quality Program to insure that adequate quality program elements are being imple-mented. Quality Assurance activities are performed by personnel who are Ci independent' of the Quality Control and work function.
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00253 14 Amendment No. 8 2/9/70 s
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p PROCEDUP2 NO. 2 - ORGANIZATION (Design to Preop)
U Purtose: This procedure establishes the organization and defines the respon ibilities of personnel assigned to the project.
Scope: This procedure shall apply to the design, procure =ent, ccnstruc-tion and preoperational phases.
Major Headings:
Organization and Administration (with bicek diagra=s),
responsibility assign =ents, docu=ent distributing and reviewing responsi-bilities, QA Progra= evaluation.
PRCCEDUF2 NO. 3 - DOCUME'iT CONTROL (Design to Preop)
Purpose:
This procedure establishes criteria for obtaining, distributing, reviewing and filing docu=ents prepared by CP Co., the Engineer-Architect, the NSS supplier and other vendors.
Score: This procedure shall apply to design, Trocure=ent, construction and preoperational phase documents such as:
specifications, requisitions, purchase orders, drawings, inspection and audit r'eports, vendor test re-ports, preoperational and hot functional tests reports, radiographs, mill test reports and other IEff reports and data.
Major Headings: General, file nu= bering system, docu=entation require-
=ents, what CP Co vill obtain fro = vendors, records retained by =anufac-s T
1,urers, =icrofi1=ing, original docu=ents, retention, project file, QA file, Field QA file, procurement, distribution, review responsibilities and document subheadings.
PROCEDURE NO. h - QAE AUDITS AND/OR INSPE~fIONS - GENEPAL
Purpose:
This procedure establishes methods for perfor=ing audits and/or inspections to assure co=pliance with the SAR, codes, specifications and the 10 CFR 50 Quality Assurance criteria.
Scope: This procedure shn M apply (a) to QAE audits of the Engineer-Architect, the NSS supplier, vendors, CP Co project engineering, and the site; and (b) to QAE inspections of equip =ent during procurement and at the site.
Major Headings:
General:
This document is intended to be a basic audit and inspection procedure allowing for develop =ent of special purpose procedures.
Audits: Tentative subheadings are:
Types, Basic Criteria, Preaudit Preparation, document require =ents, Frequency of Audits and, 'Bcchtel, TWd,
-Vendor, Project Engineering (CP Co), and site audits.
.Squ1Tcent.Inspectio=s:
Te=tativeJsubheadings are: Basic Criteria,
.A Preinspection Preparation, Frequency and BW,' Vendor and site inspections.
U 15 A=end=ent No. 8 2/9/70
p Performance Tests:
Covers vitnessing perfor=ance tests in vendors shops.
Retorts:
References procedure for preparing and distributing reports.
Deviations and Corrective Actions:
References procedures for issuing deviation notices and submitting corrective actions.
PROCEDURE ?!O. 5 - FIZID CAE AUDITS AND/OR INSPECTICUS - GENEP.AL Purnose:
This procedure establishec =ethods for perfor=ing site audits and/or inspections to insure co=pliance with the SAR, ecdes, specifications and the 10 CFR Quality Assurance criteria.
Scope: This procedure shall apply to audits and inspections by the Field QAE at the plant site during the construction and precperational phases of the project.
Major Headings:
General:
This document is intended to be a basic audit and inspection procedure allowing for development of special purpose procedures for ite=s such as concrete, tendons, radiography and welding.
Audits: Tentative subheadings are: Basic Criteria, Types, Document Requirements, Frequency of Audits, and Preaudit Preparation.
/ N V
Inscections : Tentative subheadings are: Types (Covers Receiving, Storage, and In Place), Basic Inspection Criteria, Preparation and Frequency.
Tests:. Test are to be covered by a separate procedure.
Reports:
References procedure for preparing and distributing reports.
Deviations and Corrective Action:
References procedures for issuing deviation notices and submitting corrective actions.
PROCEDURE NO. 6 - DEVIATIONS AND CutMEnVE ACTION (Design to Preop)
Purpose:
This procedure establishes =ethods for reporting deviations and corrective actions.
Scope:.This procedure shall apply to the design, procure =ent, construc-tion and preoperational phases of the project.
Major Headings:
General, Field QAE action, QAE action, follow-up, corrective action, and QA p gram evaluation.
PROCEDURE NC 7 - REPORTS
Purpose:
This procedure establishes the basic requirements for reporting audits-and inspections.
Major Headings:
For=at, distribution.
00.,,.5~~d 16 A=end=ent No. 8
'2/9/70
CONSUMERS POWER CCMPANY
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IdDLAUD PLANT UNITS 1 & 2 NUCLEAR QUALITY ASSURANCE Q-List The purpose of this list is to specify those items within the scope of the Nuclear Quality Assurance Progrc.m.
Items listed require special consideration daring design, canufacture, and construction as outlined in the Nuclear Quality Assurance Manual.
This is a list of all seismic Class I structures, systems, and equip::ent as defined in Appendix 5-A of the PSAR.
(The attached issue of the Q-List defines cajor subdivisions. A detail list with further subdivisions is issued to all parties carrying out the QA Program cnd kept up to date as the Troject progresses.)
The Q-List is divided into three major sections:
1.
Civil Structural 2.
Mechanical 3
Electrical C1'7IL STEUCTURAL SECTION Civil structural items within the scope of the Nuclear quality Assurance Program are as follows:
Reactor building.
Portions of the auxiliary building housing the engineered safeguards systems, control room and radioactive materials.
Enclosures for service water pumps.
Diesel generator foundation, building, and fuel storage tanks.
Supports,for Class I system components.
Emergency reservoir and pipeline.
1-Number Description Spec No Remarks 1.1 Prestressed & Reinforced Concrete 1.2 Liner Plate 13.
Fuel Racks l.h Structural Steel 3 15 Emergency Reservoir & Pipeline 1.6 Ventilation Chimney gZg A-1
,