ML20040E787

Forwards Formal Response to Eg&G Comments on Revision 2 to CENPD-255,revised Section 3.11 to CESSAR-F & Revision 3 to Class IE Qualification of Class IE Electrical Equipment.

ML20040E787
Person / Time
Site:	05000470
Issue date:	01/29/1982
From:	Sherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML20040E788	List: ML20040E787 ML20040E789
References
LD-82-008, LD-82-8, NUDOCS 8202050365
Download: ML20040E787 (100)

Text

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C-E Power Systems Tel. 203/688-1911 Combustion Engineering, Inc. Telex. 99297 1000 Prospect Hill Road Windsor, Connecticut 06J95 POWER SYSTEMS s

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" F P" 41992

• IO Dcaket No.: STN-50-470F - January 29, 1982

d US{ilj72$7 j LD-82-008 wA u /f l& $

Mr. Darrell G. Eisenhut Director for Licensing Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i

Subject:

Response to EG&G and Staff Comments on Topical Report No. CENPD-255

Dear Mr. Eisenhut:

Revision 2 to Topical Report CENPD-255, Qualification of Class 1E Electrical Equipment, was submitted on August 5, 1981 for staff review. Comments were provided by EG&G Idaho, Inc. , your consultant, and were discussed in our meet-ings with the staff in Bethesda. Our draft responses to these comments have been provided over the past several weeks. Our formal responses, a revised section 311 to CESSAR-F and a copy of Revision 3 to Topical Report CENPD-255 are enclosed. Bound copies of the topical report, a CESSAR-F SAR amendment, and the sample environmental test report requested by the staff will be provided shortly.

If we can be of any additional assistance, please feel free to contact either myself or Mr. G. A. Davis of my staff at (203)688-1911, Extension 2803 Very truly yours, COMBUSTION ENGINEERING, INC.

ZM

. E. mherer Director Nuclear Licensing AES:ctk Attachments cc: C. I. Grimes h0 Ss\

8202050365 820129 PDR ADOCK 05000470 A PDR

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ATTACHMENT 1 FORMAL RESPONSES TO EG&G COMMENTS P.nGES 1 thru 74 NOTE: EG&G comments were provided in a series of informal transmittals.

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, EG&G COMMENTS /C-E RESPONSE Comnent

1.2 BACKGROUND

INFORMATION Add chemical spray to list of considerations.

Response The term " Chemical Spray" will be incorporated as requested.

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Comment

2.0 REFERENCES

Why are just the two reference listed here, and the rest relegated to Appendix E?

Response All references indicated in Section 2.0 represent those references with which CENPD-255 is in full compliance.

All references indicated in Appendix E are utilized as appropriate on an equipment specific basis.

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Coment Section 3.2 Scope of Supply and Interface Requirements How are appropriate interface requirements provided to the responsible party?

Response .Please see the revised wording of Section 3.2.

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Coment Section 3.3.1 Aging The listed information should include '

1. Normal operating vibration (see IEEE 323-1974,6.3.5)

2. Synergistic effect investigation (see NUREG 0588, Rev. 1,

4. (3)).

Response Please see the revised wording in Section 3.3.1.

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Coment Section 3.4 . Environmental Conditions and Effects Last Sentence j "The inethods used to establish the environmental parameters

' for qualification are discussed in Section 5.2.2". This is a mis-statement all Section 5.2.2 does is state that a

, review will take place to evaluate the methodology used.

i l Response The last sentence in Section 3.4 has been deleted.

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1 Comment Section 3.4.1 Temperature

" Figure B-7 defines the qualification test profile for in-containment

" Harsh environment" equipment. This profile is based upon saturation temperatures corresponding to the containment pressure profile. A saturation temperature of 290 F is calculated based upon a 60 psig maximum containment pressure. Per Reference 2.1, a 15*F and 6 psig margin is added thatfresults in a 305'F and 66 psig steam / air qualifi-cation test condition."

This method of calculating qualification temperature is not allowed by IEEE 323-1974 or NUREG 0588. A qualification temperature profile based on the saturation temperature corresponding to maximum contain-ment pressure is not an adequate profile. CESSAR FSAR, Figure 3.llA-1 A reveals a peak temperature of 350'F for a period of 12 minutes into a DBE with an 8-hour expected temperature of 300"F. The FSAR curves must be enveloped with margin. NUREG 0588 and IEEE 323-1974 require bounding envelopes with margin, and in this case it is not done.

It is also noted that CESSAR FSAR, Figure 3.llA-1A (LOCA Temperature) is identical to Figure 3.11A-3 (MSLB Temperature). Is this correct?

Response

3.4.1 Temperature Please see the revised section 3.4.1.1 of CENPD-255 for the description of harsh environment' testing.

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Comment Section 3.4.1.1 Harsh Environment (Temperature)

Paragraph 4 - Explanation of the statement that HELB is not within the scope of this report is required. (e.g. , HELB will be determined in many respects by non-NSSS systems. For this reason, all equipment not susceptible to LOCA are considered

as mild environment equipment in this report. The plant specific SAR will have to evaluate all mild equipment herein for HELB effects.)

Response: Our response to your comment, "4.6.1 LOCATION" as addressed in our reply of Nov. 10, 1981 is an applicable response to this comment.

The methods and procedures used to define such environmental conditions are not within the scope of this report. These methods and procedures are an integral part of and are included in the equipment and system level design process and associated design documentation.

The following new wording was incorporated in 255 Par. 4.6.1 If it is detennined that a particular piece of equipment is located in an area that exposes it to a defined (e.g. HELB, flooding or re-circulation fluids) environmental condition, then these conditions will be incorporated into the qualification program.

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Section 3.4.2 Radiation 3.4.2.1 Harsh and Non-harsn Environment 4

" Equipment which is exposed to radiaticn above 10 Rads will be irradiated to its anticipated Total Integrated Dose (TID) prior to type testing unless det' ermined by analysis that radiation does not effect its ability to perform its required function."

NUREG 0588, 2.l(2), requires that analysis be supported by partial type test data. Even equipment that is irradiated to less than 104Rads cannot be qualified by analysis only.

See staff resolution to Coninent 37, NUREG 0588, Rev.1.

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" Equipment which will be exposed to radiation levels 10 Rads or below will be analyzed to determine whether low level radiation could impact its ability to perform its required function."

Response Please see the additional wording in 'Section 3.4.2.1.

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l Comment Section 3.4.3 Vibration In addition to the items listed here, NUREG 0588 4 (2) and IEEE 323-1974 6.3.5 require vibration to be considered and included in the aging program.

Response

The following wording was added to Section 3.4.3:

Where significant levels of continuous vibration are expected to exist during service, the effects of such vibrations, either exter-nally _or self-induced will be anhlyzed via surveillance, preventive maintenance, analysis, partial type testing, or any combination of the above.

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i Comment Section 3.4.4 Pressure

" Equipment will be environmentally tested to these conditions prior to operation and perfonnance requirements demonstrated during u... fter the test."

This is a confusing statenent. It implies that separate testing of actual installed equipment will be the only pressure qualification testing done. This, of course, is not adequate per NUREG 0588,2.3(1) and IEEE 323-1974, Section 6.3.2.

Response The phrase " Prior to Operation" has been deleted.

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Commen t Section 3.4.5 Humidity i

This section &lso confuses actual installed equipment with equipment undergoing type testing. See the above comment. l The last sentence contradicts the first.

While sequential testing of humidity can be justified, it is difficult or impossible for most items.

The phrase " Prior to Operation" has been deleted. l

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Cpment

'Section 3.4.7 Dust While this section is very adequate, consideration should be given to NRC Staff Resolution to Comment #65, NUREG 0588, Rev. 1, during future revisions of CENPD-2SS.

Response A comparison review of Section 3.4.7 and the NRC Staff Resolution to Comment #65 indicate that CENPD-255 is in full conpliance with 0588.

No change to CENPD-255 wordinc. is required.

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SECTION 4.0 EQUIPMENT REQUIRING QUALIFICATION Comment This section should include a description of the review process and the source documents used in the determination of which equipment require qualification. With this information, a customer can go through the same process for his specific plant in order to guarantee inclusion of all applicable equipment. (Section 3.2 suggests that there are components in NSSS systems which will not be C-E supplied and are, therefore, not in this section).

e R_esponse The purpose of CENPD-255 is to describe in general the methods and procedures for qualifying Class IE electrical equipment. The methods and procedures used in the determination of which equipment requires qual-ification are part of and included in the equipment and system level design process and are not within the scope of CENPD-255. No change to CENPD-255 wording is required.

Comment The abstract of this document (CENPD-255) and Section 1.1 suggest that the scope (Section 3.07) and the methods (Section 5.0?) may be referenced, but that the rest of the document is not designed for reference. If this is true, Section 4.0 should simply describe the procedures for searching source documents to determine component inclusion and then give the general discussion that is presently included.

Response

The purpose of the abstract and Section 1.1 is to reference the entire CENPD-4 255 document. No further changes to the wording in CENPD-255 are necessary.

Corrrnent i If this section is to be referenced, all items that are in NSSS designed systems (even those which are not tc .se supplied by C-E) which will require environmental qualification should be listed. If these systems have undergone modification or evolution separate lists will be required for different generations or every plant. Source documents should be referenced to make the lists traceable.

At the conclusion of the above listing, several components could then be used for examples and detailed qualification plans could be developed. - The present fonnat for discussion of equipment is so general and " typical" that it defies '

l use in plant specific applications.

Response

Sec. 4.0 3rd and 4th Par.

1 The equipment scope of CENPD-255 is clearly defined in the abstract and in Section 1.1 stating that the methods and procedures presented herein apply only to C-E supplied Class IE electrical equipment. The plant specific equipment

, listing is found in the applicants S.A.R. It is planned to present a plant

! specific equipment listing at the E.Q. Audit.

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The qualification plans of Appendix "C" & "D" have been replaced with a set of j plans having more detail as requested.

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Comments Section 4.0 General It should be noted that the list of N.S.S.S. equipment requiring qualification is found in the CESSAR FSAR Section 3.11.

If the methods and procedures that are used in compiling this list is beyond the scope of 255 a note to that effect should be

included.

Response

The methods and procedures for establishing the class 1E equipment list as found in CESSAR FSAR Par. 3.11 is beyond the scope of CENPD-255.

No further wording will be added to CENPD-255.

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Comments Section 4.0 Comment It was agreed at the 10-20-81 meeting that a general statement of criteria for inclusion in that list would be added to this section. The general criteria that was mentioned is listed bel ow.

Response The following paragraph has been addea to Section 4.0;

. Equipment requiring aualification is that equipment and systems that are essential to emergency reactor shutdown, c ontainment and isolation, reactor core cooling, and containnent and reactor l

heat removal, or are otherwise essential in preventing significant release of radioactive material to the environment.

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1 ll Comment 4.2 Isolators Three of the four isolators discussed are stated for- use in '

"some" applications and no specific uses are given. This suggests the possibility that_ there might be uses or isolators that might not be presently covered and that might miss out on plant qualification programs.

Response The word " sane" has been deleted from CENPD-255 Sections 4.2.1 and 4.2.3 and 4.2.4.

Comment 4.2.3 Process Signals The statement " Isolation...may be accomplished by using devices that have no feedback effects on the input signals" suggests one of the following.

The other three listed isolators allow feedback from non-Class lE circuits.

Some process signals may be subject to feedback from non-Class 1E circuits.

In cases where interface with non-Class lE circuits could have adverse effects, the failure modes must be identified to show justification for this situation.

Response Class lE isolators used to provide isolation between lE and Non lE equipment are designed and qualified to ensure that faults in the Non IE equipment do not degrade the safety function of the Class lE equipment. No revision to CENPD-255 required.

4.2.3.1 Comment How many abnormal conditions of 8 HR. duration can be expected during the life of the equipment?

Response In general, equipment of this nature is designed to survive abnormal environmental conditions .f.or 1% of its total expected life. The number of 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, abnormal environmental condition excursions expected during the life of the equipment will need to be defined by a specific utility.

Coment 4.2.4 Digital Isolation Device Assembly "The absence of these signals would not result in the failure of any Class lE equipment to perfom its intended safety function". Does this include post-accident monitoring?

Response The digital isolation device assembly is not used with post-accident monitoring systems. No revision to CENPD-255 required.

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Comment-4.3 Nuclear Service Valves and Auxiliary Equipment Paragraph two provides a list of equipment that "will be addressed in the applicant's plant specific SAP,". Does I this mean that these items are BOP or that they simply didn't want to include them here?

Response This equipment is in the balance-of-plant scope of supply and is not in the scope of CENPD-255. No revision to CENPD-255 is required.

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Comment 4.3.1 Electric Valve Motor Operators for Nuclear Service Valves Does the loss of the heater in Figure 4-7 affect the operation i of the MOVs? Can the heater fail in a manner that would disable the valve?

2 Response The heater shown in' Figure 4-7-has:been deleted. The ' va10e-heaters are not connected or used when the valve is in operation.

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s Comnent' 4.6.1 Location "Most equipment located outside of containment would only be subjected to a seismic event." What about HELB, flooding, and LOCA (recirc) effects?

Response Proposed new wording added to Sec. 4.6.1.

If it is determined that a particular piece of equipment is located in an area that exposes it to a defined environmental condition (e.g. HELB, flooding, or radiation due to recirculation fluids), then these conditions will be incorporated into the qualification program.

The methods and procedures used to define such environmental conditionsare not within the scope of this report. These methods and procedures are an integral part of and included in the equipment and system level design process and associated design documentation. No change to CENPD-255 wording is required.

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Comment 4.6.5 Equipment Categorization i There is no block on Table 5-2 for category.

Response The equipment category will be defined in the note block of Table 5-2. No change to CENPD-255 required.

Comment 5.0 NUREG 0588 does not allow operating experience, analysis, or ongoing qualification without partial type testing in support of edch qualification method. While this is clarified further in the section, a statement to that effect should be included here.

Response This concern is addressed in Section 5.1.

Coimient 5.1.2 TYPE TEST METHODS (Last paragraph)

"For long term testing (more than 1 hr.) monitoring at discrete intervals is performed with justification provided."

This contradicts Section 5.1.4 g, h and also the intent of NUREG 0588 2.2(9). See also staff resolution to comments on NUREG 0588 2.2(9). The intent is to allow periodic checking of function when testing proceeds "round the clock".

, Response The following wording has been added to Section 5.1.2:

For long term testing greater than one day, monitoring at discreet intervals is performed with justification provided.

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Coninen t Radiation

"(Excess margin will be equal to or greater than the uncertainty in measured dose)".

I Does this mean Applied Margin = 10% + uncertainty It should be so stated.

Response The following wording added to Section 5.1.3.

4 Applied margin = 10 percent of accident dose plus uncertainty of measuring. device, if significant.

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Comment 5.1.3 MARGIN TEMPERATURE See review of Section 3.4.1.1 for discussion of Figure B-7.

Response

The following wording has been added to Section 5.1.3:

As stated in Section 3.4.1.1, Figures B7A and B7B define the environ-mental test profiles for in-containment equipment. The combined MSLB/

LOCA profile of Figure B-7A has a 15 f temperature and 6 psig pressure margin added which is illustrated with a dotted line.

The saturation profile of B-7B has saturation temperature and corre-sponding pressure values of 290 F and 60 psig (round off incorporated) and is based upon the.following typical pre-LOCA in-containment environmental conditions:

i A. Temperature: 120 F ,

B. Relative Humidity: 50%

C. Pressure (total, steam + air): 14.7 psia A 15"F temperature and corresponding 15 psig saturation pressure margin were added to the saturation temperature and pressure values resulting in the environmental test profile illustrated by the dotted line in Figure B-7B.

For equipment located outside containment a 15 F temperature margin was also added to the appropriate environmental test profile, as illustrated in Figures B-8 through B-ll.

Pressure: +10 percent of gauge but not more than 10 psi. Exception for saturation profile, (15 psig niargin). See previous discussion on temperature margin.

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i Comment TIME

GENERAL COMMENT

C.E. is attempting to generalize a method for time margins of

' less than one hour. NUREG.0588 3. (4) specifically requires a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> minimum margin. Staff resolution to industry comments on this section says, in part:

"There may be some designs where less restrictive margins may be

justified and found acceptable on a case-by-case basis."

Response Please see the re-worded Time and Unusual Time paragraphs of Section 5.1.3.

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.l Comment SPECIFIC COMMENTS Page 5-5, 2nd paragraph "In addition to the above two trips the following trips are to be qualified to operate for the entire envelope defined by the curve of Figure 5-1: Low Pressurizer Pressure Trip, Low Steam Generator Level Trip, and Low Steam Generator AP (Low Reactor Coolant Flow) Trip."

No mention is made of how these parameter's times to trip are calculated, and how those times relate to the curve of Figure 5-1. Sound practice would indicate that their trip times are under those postulated in Figure 5-1, but it is not so stated.

A suspicion remains that the opposite might be true, and the assump-tion has been made that, for example, the Low Pr3ssurizer Pressure Trip is not needed beyond the times shown in Figure 5-1 because either the High Containnent Pressure trip or the Low Stdam Generator Pressure trip will have already actuated.

Response The Low Pressurizer Pressure Trip, the Low Steam Generator Level Trip and the Low Steam Generator AP (Low Flow) Trip are not required past the times shown in the Figure because either the High Containment Pressure Trip or the Low Steam Generator Pressure Trip will have actuated. For certain conditions the former three trips will take a very long time to actuate, while a reactor trip will already have taken place. The Low Steam Generator Pressure Trip for break areas above 3 ft2 and High Containment Pressure Trip for break areas below 3 ft2 form a practical bounding time to trip for all five trip functions.

The " UNUSUAL TIME" response of our November 25th transmittal will be inserted on page 5-5. This response states (in part) that unusual time margins of less than one hour will be included in the test envelope where it is determined that the addition of a one hour time margin to the required operability time would result in an

! overtest that is damaging to the equipment.

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Comment Page 5-6, 1st paragraph.

" Guidance provided to the operators will reflect the extent of qualification of equipment to help ensure that they 3re not mislead by false indications."

This reviewer doubts that this is an adequate response to the "not mislead an operator" requirement. In the example stated, an operator is asked to ignore Low Steam Generator Pressu're, High Containment Pressure, Low Pressurizer Pressure, Low Steam Generator Level and Low Steam Generator AP approximately 10 minutes after a D.B.E.

Response The Core Protection Calculator-Low DNBR Trip and the High Linear Power Trip will be the only trips qualified to the limited time interval described in this paragraph. The Low Steam Generator Pressure, High Containment Pressure, Low Pressurizer Pressure, low Steam Generator Level and Low Steam Generator AP Trips will be qualified for the entire envelope defined by the curve of Figure 5-1.

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Comment j 5.1.4 d Add a statement including radiation or a reference to 5.3.1 where this is amplified.

Response The following wording has been added to Section 5.1.4d:

Section 5.3.1 provides additional discussion regarding the 1

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Commen t 5.1.4. f Add " including mechanical and self induced vibration as required".

Response The following wording has been added to Section 5.1.4.f:

Where it is determined that s.igniff. cant levels of external 1

or internally induced vibration exist, qualification will be demonstrated based upon the methodology presented in Section 3.4.3.

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Comment Page 5-10 following h. ,

A note here on submergence testing should be required. See NUREG05882.2(5).

Response The following. wording has > been added to ~ Section 5.1.4.h':

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' Submergence testing,if applicable,will be perfonned following I

seismic testing per the methodology of Section 3.4.8.

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Comment Page 5-10 4th Paragraph Typo - Seution 4.6.4 should read 4.6.5.

Response Corrected.

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Comment Page 5-11 i) Performance testing .nd/or monitoring of operability status during (5) and (7) will be performed to the extent pract' ..

During (7), safety functions.must be monitored.

See IEEE 323, 1974 6.3.2(7) and NUREG 05882.2(9).

Respon'se It is understood that performance testing and/or monitoring of operability status during seismic and DBA testing are required if the equipment is required to perform its safety function during those events.

The reason the phrase "to the extent practicable" is l

included in note "i" was that only limited monitoring may be achievable because of the limited seismic test duration.

No change to CENPD-255 required.

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' Comment Page_5-11 last paragraph This addressment of Class lE motors shoulo use IEEE Std. 334-1974 as its basis. IEEE Std. 334-1974 recognized in NUREG 0588 as an acceptable daughter standard demonstrating compl'iance with IEEE Std. 323-1974. In addition, IEEE Std. 334 is endorsed by Regulatory Guide 1.40. It also is noted that IEEE Std. 334-1974 uses IEEE Std. 117-1974, IEEE Std. 275-1966 and IEEE Std. 112A-1964 as references.

Response IEEE 334-1974 has been added to this paragraph.

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Comment 5.1.6 Environmental Test Profiles See review of Section 3.4.1.1 for discussion of Figure B-7.

Response

The following wording has been added to Section 5.1.6:

5.1.6 Environmental Test Profiles Typical test profiles for equipment which is required to perform a Class IE function during or after a design basis accident and which is located in the Containment Building are shown in Figure B-7A and B-78. These profiles provide for margin requirments and include additional peak transients as required by IEEE Std. 323-1974, Section 6.3.1.5 and Appendix A. These profiles provide for establishing the design basis event peak transient environmental conditions, reducing to normal environmental conditions, then repeating the peak transient environmental conditions for the period of time over which the equip-ment is needed to perform its Class IE function. Equipment will be exercised or monitored for its Class IE function.

Typical test profiles for equipment located in non-harsh environments are provided in Appendix B, Tables B-8 through B-ll. These orofiles were developed based on normal and abnormal environnental conditions.

Equipment will be tested to the simultaneous temperature and humidity conditions for at least eight hours at the low and high temperature levels and at high humidity at normal temperatures.

] Figure B-7A .

TYPICAL CONTAINMENT BUILDING ENVIRONMENTAL TEST PROFILE FOR CATEGORY "A-1" AND "A-2" ENVIRONMENTAL CONDITIONS ,

8 ' ' ' *

(5PSIG 66 PSIG f~~ DESIGN BASIS EVENT IRANSIENT N

T\ ADDITIONAL PEAK TRANSIENT  ;

N i \

im PSIG l 60 PSIG PRESSURE

\ -

60

\

\\

g

= Ci 0 REhul A T UNC IOP R U IN \

SUPfRIIEATED s SUPERHEATED . \ .

g SIEAhVAIR STEAMIAIR 2

\ SLOPE 0 N \ -

40 g h 400 0

385 F \ UNSPECIFIED r

g3 F 8 hknv"A}l .\ c

= <-m N N0'r 'N \ W * ~ ~365 7 F -

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$= N \ 35d'F \ 315 F TEMPERATURE .

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(TEMP.

STA8ilIZE AT NORMAL I STABILIZE AT NORMAL - \ ENVIRONMENT ,

120

) LNVIRONMENT INITIATE CHEMICAL

- 10 100 (PRESSURE) SPRAY .

PRES $URD

~

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0 100 1000 10000 10 2 10 2 4 10 .,

SEC SEC TIME, MINUTES

.- - QUALIFICATION IIVEL .

gigo

? ---- TEST LEVEL ,

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• R Figure D-7B TYPICAL CONTAINMENT BUILDING ENVIRONMENTAL TEST PROFILE FOR CATEGORY "A-1","A-2" AND "V 1" ENVIRONMENTAL CONDITIONS 4

b TR 4 i DESIGN BASIS EVENT TRANSIENT S ENT >

75 PSIG

-k ______ [_75__PSIG _ _stg. Saturation Pressure for 305 F amf35,t,t!!g;e PRESSURE N g 60 PSIG l \ PRESSURE G0 PSIG \ ~

, TEST TIME LIMITED BY SAFETY- , g

\ (STEAM / AIR RELATED FUNCTIONAL REQUIREMENT T e

400 \ MIXTURE) _

40g

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g- 300 -

g

\

\ [

TEMPERATU E (STEAM / AIR MIXTURE) 30h r I

\ s

\

\

2900F  %

g200 290 F N 20 u, N\ 9 4 STABILIZE AT NORMAL QUALIFICATION

$ TEMPERATURE ENVIRONMENT LEVEL g 4 --_ TEST LEVEL 100 - . STABILIZE AT -

10 NORMAL

/, ENVIRONMENT INITIATE CHEMICAL SPRAY I I i -

I I l i 2 10 102 10 102 103 104 TIME, MINUTES TIME, MINUTES

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Coment:

5.1.6 Environmental Test Profiles Para. 2, Figures 8-8 through 11 (not Table )

i Response: The word " Tables" will be deleted and the word " Figures" will inserted in the second paragraph of section 5.1.6 for consistentcy with the figures shown on Pages B25-B28 of Appendix C.

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I ' Comment l 5.1.7 Acceptance Criteria The first paragraph starts " Testing, and/or analysis...". This should be changed to read " Testing or testing and analysis..."

NUREG 0588 2.4 does not allow qualification by analysis without partial type testing to sJpport that analysis.

Response This change has been made.

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Comment Page 5-18 last paragraph Type - Section 9.2.1 should read Section 4.2.1.

Response This change has been nade on Page 5-20.

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Comment:

5.2.2 Environmental Conditions Calculations i

Paragraph 2 should discuss all components in areas which co61d be influenced by ECCS fluids. Some components that are not part of the ECCS system might be affected.

Repsonse: The following wording has been added to paragraph 5.2.2:

Environmental Conditions Calculations To ensure compliance with the requirements of Appendix A,B, and D of Reference 2.2 of CENPD-255, a review will be performed that evaluates the actual methods and codes used to calculate the environmental para-meters for design basis events. Environmental condition verification is generally a joint activity between the customer, A/E and C-E.

Per the requirements of Section 1.4 (11) of Reference 2.2, components of the ECCS located outside containment will be qualified to withstand the radiation equivalent to that' penetrating the containment and the circulating fluids passing through individual ECCS components. Equipment not associated with the ECCS but located in the same area will be addressed on a plant specific basis to meet the Radiation Qualification Requirements.

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Comments 5.3.3 Surveillance / Preventative Maintenance The last paragraph should include a statement that the data and evaluation from the S/PM program should become part of the central file either by inclusion in the equipnent files or by reference.

Response: The last paragraph has been revised to reflect the above comment as shown in the. paragraph below:

Data maintenance, storage in the central file and evaluation activities such as the surveillance / preventative maintenance program will be the responsibility of the utility.

It is not the scope CENPD-255 to define the methods, procedures or material to be incorporated in the Utilities Central File System. However, support will be provided to establish a Complete Central File.

Coment 6.1.4 Qualification Test Procedure Section 6.1 references IEEE 323-1974 Section 8.0, which discusses documentation. Section-6.3.1.1 of IEEE 323 should be included as a reference for this Qualification Test Procedure section.

Response Section 6.3.1.1 of IEEE 323 has been included as reference l in Section 6.1.

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Conrnents 6.1.5 Qualification Test Report The Qualification Test Report should also include test setu'p and test procedure (Reference 2.1, Section 8.3(4)(c) and (4)(d)).

It is almost essential for the persons actually preparing the Plans, Procedures and Reports in this section (6.0) to somehow be'kept aware of the source documents (Reference 2.1 and 2.2) that support this section. This basic plan is very well thought out and should work well as long as the people involved are aware of the long-term documentation requirements and the importance of the "auditable" form requirement.

Response The test setup and test procedure information are generally included in either the Qualification Plan or Qualification Procedure doctsnents. Discussion of the test setup or testing procedures, other than verifying actual implementation of the planned approach, is normally not incorporated within the final test report, unless deviation from the planned approach is required.

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Comments 7.0 QUALITY ASSURANCE and 8.0 ADMINISTRATIVE PROCEDURES One of these sections should include a discussion of turnover of information, from C-E to the customer, concerning maintenance of environmentally qualified equipment. This would involve, but is not limited to, the following:

1. Storage requirements prior to installation.

2. Handling and QA during installation.

3. Special installation requirements.

4. Baseline data required for on-going surveillance

5. Maintenance required to maintain the qualified status of the equipment.

Response

1. Storage requirements prior to installation:

The revised wording has been added to ageing Section 5.3.1.

2. Handling and QA during installation of equipment are defined and accomplished by the utility and/or the architect engineer and are beyond the scope of CEMPD-255.

3. Special installations (if any) are equipment specific and are addressed in installation drawings, equipment specifications and technical manuals and are beyond the scope of CENPD-255.

4. Baseline data (as defined in the aging analysis) for on-going sur-veillance of equipment is equipment specific and will be defined in l the appropriate equipment qualification documentation and is beyond the f

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5. The manner and frequency of maintenance for qualified equipment is equipment specific and will be defined in the appropriate equipment specifications and specific qualification documentation.

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Coment APPENDIX A TYPICAL CLASS IE ELECTRICAL EQUIPMENT AND DATA LISTING This appendix should include all equipment that is listed in Section 4.0 and is shown in Figures 4-1 through 4-11. There should also be a direct correspondence between the component or module names used on this appendix and those given in Section 4.0. Frequently, the name given in the appendix cannot be found in Section 4.0. Examples of problems follow.

1. Section 4.1.4 on the CEA Position Indication system does not mention disconnects. Figure 4-4 shows a refueling disconnect panel. Table A-1 lists a CEA P.I. connector.

2. Section 4.1.2 on the NI system mentions signal processing drawers.

Table A-1 lists an NI Signal Processor. Figure 4-2 shows Log Power and Linear Power Safety Channels.

3. The SSCCS, SSAS, and SSM are on Table A-1, but cannot be found in Section 4.0 or on Figures 4-1 to 4-11.

4. The isolators from Sections 4.2.1 and 4.2.3 are not on Table A-1.

5. The penetrations, cable, and junction boxes of Section 4.1.1 through 4.1.4 are not on Table A-1.

6. Due to problems with nomenclature (for examples see 1 and 2 above) it is difficult to locate items in 4.1.5 through 4.1.9 on Table l A-1.

There also seems to be discrepancies with the Environmental Condition and Environmental Equipment Categories.

Both the NI Detector and Cable and the NI Pre-amp are in Condition Category (CC) "A2" (in containment, subject to MSLB) but the Detector and Cable are Equipment Category (EC) "1" (harsh, must function) and l the pre-amp is EC "4" (non-harsh). The same thing occurs for the CEA P.I. Cable (A2, 1) and the connector (A2, 4).

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Comment APPENDIX A The SPLA and pressure switch are both CC 'C' but the SPLA is EC 'l'  ;

(harsh) and the Pressure Switch is EC '4' (non-harsh).

.Due to the lack of correlation and the above inaccuracies, it is hard to see this appendix as a guide or as a senple. A smaller '

' exact sample would be more effective.

j Response Appendix A, typical Class IE electrical equipment and data listing was revised to correct the inaccurancies and provide correlation between Appendix A, Section 4 and Figures 4-1 through 4-11.

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Appendix "A"

• Appendix A Comment A-1 Purpose It is assumed by the reviewer that those components shown on figures 4-1 thru 4-11 and not noted in table A-1 are B.0.P.

A note to that effect should be added here.

Response

Principal components of systems as shown on Figures 4-1 thru 4-11 are listed on Table 4-11 as revised to reflect the material in paragraphs 4.1.1 thru 4.4 and Figures 4-1 thru 4-11.

Revised Table A-1 is attached to this response for your convenience. No further change to wording in 255 is necessary.

Comment Table - A-1 Nuclear Instrumentation System Pre amp + filter shown on fig 4-2 to be inside containment, environmental cond. Category "A-2" but environ. equip category "4" the two are incompatible.

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Response

Table A-1 was revised to reflect the correct category for the l nuclear instrumentation system pre-amplifier and filter.

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TABLE A-1 CLASS IE ELECTRICAL EQUIPMENT AND DATA LISTING ',

(12) (7) (1) (15) (2) (15) (3) (15) (14) (15) .

MODULE OR OPERATING REQUIREMENTS ENVIR.COND. ENVIR. EQUIP. h0TES SYSTEM COMPONENT LOCA MSLB SEIS SSD LOCATION CATEGORY CATEGORY INTERFACE REF. 255 PAR Process Process Dectors Varies by Location and Varies by Varies by Varies by 4.1.1 Instrumentation Signal Converter Design Design Design Design Contained in Panel Mounted Recorder Application Application Application Varied Systems Panel Mounted Indicator .

Isolation Device x IO) CB I4)

Nuclear Instrmen- Fissior. Chamber x x A2 1 (11) 4.1.2 tation System Detectors & Cable Pre-Amplifier & Filter x(8) x x CB(5) A2 1 (11) 'g'I*2 Signal Processor for Log Power & Linear Power x(8) x x CR H 4 (9) (10) (11) 4.1.2 Safety Channels Reactor Coolant Proximity Probe for CB(0) A2 1 (11) 4.1.3 Pump Speed Shaft Speed x x Sensing System Extension Cable x x CB(6) A2 1 (11) 4.1.3 Pulse Transmitter x x CB(5) A2 1 (11) 4.1.3 Signal Processor x x CR H 4 (9) (10) (11) 4.1.3 CEA Position Reed Switch Assy.& Cable x x CB(4I A2 1 (11) 4.1.4 Indicating Refueling Disconnect Panel x x CB(4) A2 1 (11) 4.1.4 System Isolator x x CR H 4 (9) (10) (11)

Plant Protection Reactor Protection System x x x x CR-AB H 4 (9)(10)(11) 4.1.5 System Cabinet Engineered Safety Features x x x x CR-AB H 4 (9) (10) (11) 4.1.5 Actuation System ESFAS Aux. Relay ESFAS Actuation Circuitry x x CR H 4 4.1.6 Cabinet

TABLE A-1 CLASS IE ELECTRICAL EQUIPMENT AND DATA LISTING (12) (7) (1) (15) (2) (15) (3) (15) (14) (15)

MODULE OR OPERATING REQUIREMENTS ENVIR.COND. ENVIR. EQUIP. NOTES SYSTEM COMPONENT LOCATION S

LOCA MSLB SEls S_SD. CATEGORY CATEGORY INTERFACE REF. 255 PAR DNDR/LPD CPC I/O Modules x CR H 4 4.1.7 Calculator System CPC CPU and Memory x CR H 4 4.1.7 CEAC CP') and Memory x CR H 4 4.1.7 Signal Isolators x CR H 4 Supplementry Protection System SPS Pressure XMTR. x CB(5) B 1 (9)(10)(11) 4.1.8 SPS Indicator x CR H 4 4.1.8 Supplementary Protection x CR H 4 (9)(10)(11) 4.1.8 System Logic Assy.(SPLA)

Remote Input Sub- RIS isolation x CR H 4 4.2.1 System Various Systems Digital Isolation Device x x x x CR H 4.2.4 Assy.

4 (9)(10)(11)

Nuclear Service Electric Valve Motor x x x x CB,0C V-1, V-2 1 (10) 4.3.1 Valves in Various Operators Systems as SIS, Electric Solenoid Process x x x x CB,0C V-1, V-2 4.3.2 SCS, CSS, & CVCS 1 (10)

System Valves Electric Solenoid Operator x x x x CB,0C V-1, V-2 1 (10) 4.3.3 Pneumatic Pilot Valves Electric Limit Switch for x x x x CB,0C V-1, V-2 1 (10) 4.3.4

.' Open/Close Position Indi-7 lj ,

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MODULE OR OPERATING REQUiHEMENTS ENVIR.COND. ENVIR. EQUIP NOTES SYSTEM COMPONENT LOCA MSLB SEIS SSD LOCATIDN CATEGORY CATEGORY INTERFACE REF. 255 PAR-Nuclear Service Pump High Pressure Safety x x x AB D 1 (10)(13) 4.4.1 Motors in Various Injection Pump Systems CVSC, IRS, low Pressure Safety x x x x AB D 1 (10) 4.4.2 CSS & ECCS Injection Pump Containment Spray x x x AB D 1 (10) 4.4.3 Pump Motor Charging Pump Motor x x x AB D 1 (10)(13) 4.4.4 Chemical Spray Addi- x x AB D 1 (10) 4.4.5 tion Pump Motor

Table A-1 Huclear-Instrumentation System Pre amp + filter shown on fig 4-2 to be inside containment, environmental cond. Category "A-2" but environ. equip category "4" the two are incompatable.

Response

Table A-1 was revised to reflect the correct category for the

, nuclear instrumentation system pre-amplifier and filter.

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, Appendix B

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B.2 Sumary . \ ,

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in - Our initial coment is still; not answered. Either change the

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'Th'e summary paragraph has'bden revised to reflect the initial EG8G comment, and to clarify, that the ten tables were not derived from the Figures B-1 througn B-6. Please see the following page for the proposed new wording, b

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l Comment APPENDIX B TYPICAL ENVIRONMENTAL CONDITIONS AND TEST PROFILES B.2 Summary Paragraph 2 states that Table B-1 through B-14 are derived from Figures B-l through B-6. With the exception of Figure B-3, all of these figures are inside containment. This means that 10 tables derived from it include radiation, pressure, humidity and spray for at least three different outside containment environments.

B.3 Environmental Conditions An equipment location description that is more definitive than just inside or outside containment (out-of-doors, in the auxiliary building, control room, etc.) is required to make this section usable and understandable. This might also make it possible to coordinate the four normals with the eight abnormals.

1. Response The purpose of Appendix "B" is to define Typical environmental con-ditions and associated environmental test profiles. Tables 8-1 through B-14 were developed for the purpose of defining a limited set of clearly established environmental conditions that could be associated with specific equipment and/or locations. Appendix A correlates generic pieces of equipmer.t with its corresponding environmental cate-gory designator.

Environmental conditions, as found in the Tables of Appendix B cannot be defined by location other than inside or outside containment because of the differences in plant design. As an example the environment of an auxiliary building at one plant may be different than that of another. Defining this would defeat the purpose of a generic qualifi-cation program document.

Comnent The two worst-case valve categories are confusing. They are not found in CESSAR-F, Section 3.11 and the reason for making special categories here is not shown.

2. Response This comment is addressed in the revision of CESSAP.-F Section 3.11.

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Coninent i Table B-2. This table is for MSLB inside containment but, for the pressure profile, references Figure B-2, which is LOCA pressure.

3. Response Table B-2 has been revised, see attached sheet on following page.

. The MSLB pressure profile is to be same as LOCA pressure profile Figure B-2.

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TABLE B-2 CATEGORY "A-2" ENVIRONMENTAL CONDITIONS (MSLB: :IN-_ CONTAINMENT)

ENVIRONMENTAL R NGE DURATION PARAMETERS TEMPERATURE, F FIGURE B-4 0-12 MIN.

FIGURE B-1 (AFTER 12 MIN.)

PRESSURE, PSIG SAME AS LOCA PROFILE FIGURE B-2 SH STEAM / AIR MIXTURE 0-12 MIN.

HUMIDITY SAT. STEAM / AIR MIXTURE (AFTER 12 MIN.)

RADIATION.-RADS 4.5 X 104y (TID)

CHEMICALS NOTE '1' NOTE 1 - 4400 PPM BORON AS H B0 , 50-100' PPM HYDRAZINE AS N H AND p4H TO-10.

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Appendix B B.2 Summary Our initial comment is still not answered. Either change the paragraph or supply the figures that were used to define the 10 tables.

Response -

The summary paragraph has been revised to reflect the initial EG&G comment, and to clarify that the ten tables were not derived from the Figures B-1 through B-6.

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Comment Tables B-3 and B CESSAR-F. Table 3.11 B-2 is used as a reference even though it is not listed in Section 2.0. It should either be referenced in Section 2.0 or duplicated in this appendix.

Tables B-5 and B-6. The low-end temperature goes down to 55 F.

CESSAR Table 3.11A-1 uses 60 F as a minimum.

3 Table B-10. The specified radiation dose is less than 10 Rads.

CESSAR Table 3.11A-1 gives 104 Rads.

Figure B-1. This figure shows a 200* elbow at about 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />.

CESSAR Figure 3.11A-1A shows this elbow at about 264 hours0.00306 days <br />0.0733 hours <br />4.365079e-4 weeks <br />1.00452e-4 months <br />.

Figure B-4. This figure has a peak of 370*F. CESSAR Figure 3.11 A-3 does not show a 370 F maximum. (This CESSAR figure is a duplicate of CESSAR Figure 3.llA-1A).

Figure B-6. This figure shows about one-half of Figure 3.11A-5 CESSAR values.

Response

Please see previous response to Appendix B.

Thfs' comment will be addressed in the revision of- Section 3.11.

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Comment Tables B-5 through B-8. The note on these tables giving an eight-hour limit is confusing. Does it mean that plant shutdown is initiated after eight hours outside the normal band or that operating studies show that for the 50-year life less than eight hours are expected outside the normal band. For Table B-5, the eight and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> specifications do not coordinate. '

Response

The eight hour period was selected on the basis of engineering judgement as a reasonably conservative period for the plant operators i

to (1) recognize that actual conditions in the non-harsh environments have exceeded their normal values and to (2) restore those environ-ments to within normal limits. Purchasers of these components will be informed that the period of assured operability in the abnormal environment conditions is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (based on testing) and that off-normal procedures should contain provisions for appropriate actions should it not be possible to restore normal environmental conditions within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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r Comment Table B-5 B-8 Is this response going to be included in the text? It should be.

Also the number of expected abnormal incidents per year or over 5 the lifetime of the equipment and how this relates to mild environment qualification should be mentioned.

Response

The eight hour explanation for Tables B-5 through B-8 has been included in Appendix B Par. B.2 " Summary Text."

Please see the response for Paragraph 4.2.3.1 for the response to the second paragraph above.

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Comment Figure B-7. This typical test profile is intended to envelope equipment in environments shown in Figures B-1 through B-6. The maximum test temperature is 305*F, which is to include 15 F for margin. The maximum temperature shown in Figure B-1 through 2-6 is 370'F. This indicates that a test temperature including a 15 F margin would be at 385 F. The reviewer assumes that 290 F (the test temperature without margin) was derived as the satura-tion temperature for 60 psig. The reviewer also assumes that this was done in accordance with IEEE 323-1974, Section 6.3.1.5(1) .

This method was incorrect since this IEEE section applies to margin ,

only, and then only in the case where saturated steam is to be used. (

In this case, the in-containment humidity is specified as superheated steam, which then forces a high temperature than saturation unless the higher pressure (to meet saturation for the required temperature) is used.

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Response

See Section 3.4.1 write-up. Figure B-7 has been replaced with Figures B-7A and B-7B.

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Response to verbal question on thermal equivalence methods.

Discussion of Thermal Eouivalence For Main Steam Line Break (MSLB) thermodynamic conditions C-E plans to qualify instrumentation in the following manner:

1) A spectrum of MSLB break areas will be analyzed. The conservatively calculated mass / energy (m/e) release to the containment from thhe affected SG will be modelled following the NRC approved methods of Appendix A of NUREG 0588. The SGNIII computer code will be used to determine the m/e release as a function of break size. CESSARF generic NSSS enveloping data will be used for this analysis.

2) The containment pressure / temperature (p/t) thermodynamic response to the m/e data will be conservatively determined for each case of 1) above. The NRC approved methods of Appendix B, part 1, NUREG 0588 will be used. Credit will be taken for the safety grade containment sprays in this analysis. The spray delay time and the spray rate will be conservatively modelled; these conservatisms are in addition to those required in Appendix B, Part 1, of NUREG 0588. C-E's NRC approved containment code (CONTRANS) will be used for the analysis. As appropriate, either plant specific data or enveloping data will be used for this analysis.

3) Each component to be tested will be modelled to conservatively determine its time dependent temperature. The containment p/t time dependent response for each MSLB area case will be used as a forcing function for this analysis. The heat transfer coefficients and the mode of heat transfer will be conservatively I modelled using the NRC approved methods of Appendix B, part 2, NUREG 0588. A subroutine imbedded in the CONTRANS code will be used to rigorously solve the heat conduction equation for each component. The result of this calculation will be the time dependent surface temperature (Ts) of each component for each MSLB break area. The highest value of Ts (Txmax) will be used in determining the adequacy of a given thermal environmental qualification test profile; see

! (4), below.

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4) C-E will test each component in a thermal environment (See (5), (6) and (7) below) which will heat the surface of the component to at least TSmax as defined in 2) above. Verification that the surface of the component has been heated to at least TSmax will be accomplished either by:

a) a conservative calculation which will minimize the heat flux to the component using the test profile as a forcing function, or b) thermocouple measurements at the surface of the component, or c) " soaking" the component in a saturated steam / air environment for at least 10 minutes.

5) C-E's experience with 1) through 4) above shows that most components are sufficiently massive such that the values of LOCA seldom exceed 290*F. 290*F has been chosen since it is conservatively representative of containment saturated steam / air conditions following a TSmax;this temperature and its associated pressure are shown in Figure 1. C-E will use this thermal profile for LOCA and MSLB related testing only where it can be demonstrated (using the methods described in 1 through 4 above) that this profile heats the component surface to at least TSmax.

6) If there are components for which testing via Figure 1 does not heat the component surface to at least TSmax, then these components will be tested in a harsher environment which will heat the component surface to at least TSmax.

7) There may be components which are only credited for safety analysis calculations for selected ranges of MSLB areas; for MSLB break areas outside I

the selected range, these components are not credited in safety analyses.

For these components. TSmax will be determined by considering only the appropriate MSLB break area range. These components will be tested with a suitable environmental testing profile which will heat the surface of each component to att least TS nax as determined by the narrower range of MSLB areas.

J Coment GENERAL OBSERVATION APPENDIX "C" + "D" While these Appendices are intended to be qualification plans, they are very general and inadequate to show an acceptable qualification program.

If an actual age conditioning report, a qualification test procedure, a qualification test report and a qualification data summary and evaluation package aere to be mada a part of CENPD-255, a much better example of ra to qualify equipment would be achieved. l l

Response As addressed in Paragraph C.1 Purpose ,the attached Qualification Plans are only outlines of plans to be used and should not represent detailed vendor prepared qualification plans.

The Age Conditioning Report; Qualification Test Procedure; Qualification Test Report and Summary are plant and equipment specific in nature and will be made available for E.Q. audit 2 by the NRC.

No further chang to CENPD-255 wording is necessary.

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Carnent Appendix C 2nd Paragraph Pge 4/21 " for equipment inside containment LOCA".

Change LOCA to LOCA/MSLB Response Revised LOCA to LOCA/MSLB in 2nd Paragraph Page 4/21. See Section 1.0 of Appendix C for additional wording.

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t Cocment . Appendix "C" REF.'3 2 IEEE 323-1974 is IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations-Response The correct IEEE Reference will be added to Reference 3 2 Appendix C.

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Coment 4.1.2 No mention here of MSLB, yet App. A, CENPD 255 states that it is required for MSLB. Operability time is shown in Table 1 to be 70 min.

Response See Section 4.0 in Appendix C for revised wording.

Coment - Appendix "C" Page 14 of 21.

Is 70 min. the required operating time and does it include margin?

70 min. chem. spray duration incompatable with Figure 3, Chem. spray duration missing for pulse transmitter.

Response

10 minutes is the required operating time of Reactor Speed Sensing System during the FGLB. An additional 60 Pdnutes is added to the 10 minute operational time to meet the 1 br.

margin Criteria.

Duration of Chemical Spray was changed to 60 min, to be compatible with Fig. 3 in Appendix C.

The 60 minute duration for Chemical Spray was added to the Table 1 Qualification Parameters for the Pulse Transmitter.

Please see the revised Table 1 of Appendix "C".

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j Carnent .ippendix "C" 4.2.4 Which profiles in Ref. 3.4?

Response

The profiles B-7A and B-11, and Figures in Appendix "B" shall be added to 4.2.4 wording.

i Comment Appendix "D" 4.2 3 Specify which profile in Reference 3 3, what the appropriate voltage and frequency variations are, and what functional capabilities will be monitored.

Response

The profile as shown in Reference 3 3 Appendix "B" Figure B-10 is the applicable profile and is shown on Figure 3 in this Appendix.

The appropriate voltage and frequency variations and

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monitored functional capabilities are not within the scope of 255 as a Generic Document. However, the above information is furnished in test vendor qualification plans, test reports and specific design specifications.

Please see the revised Section 4.2 3 of Appendix "D".

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i Comment Section 4.2.5.2 It is assumed that information supplied here will be used to simulate equipment on the R.S.P. Is this true?

Will accelerometer data at the point of attachment be compared with the seismic test data of the simulated equipment to establish its adequacy for this application?

Response This information is to be used for determining dummy loads for actual equipment simulation during seismic testing.

The accelerometer data from the simulated equipment is compared to the actual equipment accelerometer data from its Generic Module curve to insure that seismic integrity is maintained.

Specific seismic information will be addcessed by seismic test plans and reports as furnished to meet Qualification Criteria.

Please see Revised Section 4.2.5.2 of Appendix "D".

Coment Appendix "D" section 4.2.2 A list showing what equipment in the R.S.P. is tested with the panel, what is qualified eslewhere, and where it is qualified, should be listed here.

Response An equipment list for the remote shutdown panel is not within the scope of 255 " Appendix D". The above information is furnished by the Test Vendor Qualificaiton Plan, Test Reports and Design Specifications. This plan is intended to outline major areas of qualification to be completed and not intended to provide specific qualificaiton details.

No further change to wording in 255 is necessary.

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ATTACHMENT 2 REVISED SECTION 3.11 TO CESSAR-F i

i 3.11 ENVIRONMENTAL DESIGN OF MECHAMICAL AND ELECTRICAL E0IIIPMENT The design criteria with respect to environmental effects on the electrical and mechanical equipment of the Reactor Protective System and the Engineered Safety Features System to ensure acceptable performance in all environments (normal and accident in harsh and non-harsh environment) depend upon eouipment location and function. Such equipment is designed to meet its performance requirenents under the environmental and operating conditions in which it will be required to function and for the length of time for which its function is reouired. As f ar as practical, eouipment for these systems is located outside the Containment Building or other areas where adverse environmental conditions could exist. Compatibility of mechanical and electrical equipment with environmental condition is provided within the following design critera:

A. For operation under normal conditions the systems are designed to remain functional after exposure within the following ranges of environmental 7

conditions:

1. Design temperatures maintained at the equipment locatf or during normal '

i I operation by the ventilating and cooling system described in Section l 9.4 Temperature ranges are given in Appendix 3.11A, Table 3.11A-1 thru 3.11 A-14. l

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2. Relative humidity ranges are given in Appendix 3.11A, Table 3.11A-1 l

thru 3.11 A-14.

3. Pressure ranges are given in Appendix 3.11A, Table 3.11A-1 thru 3.11A-14.

4. Maximum expected integrated radiation exposures for 40 years at the eouipment location during normal operation are given in Appendix 3.11 A, Table 3.11 A-1 thru 3.11 A-14. (

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B. In addition to the normal operation environmental reauirements given in listing A above, the mechanical and electrical components required to mitigate the consequences of a design basis event (DBE) or to attain a safe shutdown of the reactor are designed to remain functional after exposure to l the environmental canditions anticipated following the specific DBE which they are intended to mitigate. Anticipated environmental conditions and requirements are listed below.

1. The temperature, pressure, and humidity ranges following the design bases accidents such as the loss of coolant accident (LOCA), the main steam line break (MSLB), control element assembly ejection, or feedwater line break (FVLB), " Worst Case" combined (LOCA & MSLB) are l indicated in Appendix 3.11A.

2. The time integrated post accident radiation doses are indicated in Appendix 3.11A. Eauipment will be designed for the types and levels of radiation associated with normal operation plus the radiation associated with the limiting design basis accident (DBA). If more than one type of radiation is significant each type may be considered separately.

3.11.1 EQUIPMENT IDENTIFICATION AND ENVIRONMENTAL CONDITIONS Appendix 3.11B lists and categorizes systems reouired to mitigate a DBE or to obtain a safe shutdown. Specific equipment and components for each system are discussed in the appropriate section of the safety analysis report as referenced in appendix 3.118. The major component categories, such as motor-operated valves, pump motors, instrumentation and pressure boundary eaufpment in each system, and the location of the components by area are also provided.

I 3.11-2 i

I 3.11.2 OUALIFICATION TESTS AND ANALYSES Qualification tests and analyses performed in accordance with the methodologies defined in CENPD 255 Rev. 03 on NSSS instrumentation and electrical equipment (including pump and valve motors and electrical accessories) fulfill the reauirements of IEEE Standrd 323-1974, and " Category 1" of NUREG 0588. For mechanical equipment, environmental aualification is based on Engineering, Evaluation, and Material Selection where sufficiently reliable data is available.

3.11.2.1 Component Environmental Design and Oualification for Nonnal Operation Eauipment listed in Appendix 3.118 is designed for 40 years of continuous operation in the temperature, pressure, humidity, and radiation environment that exists at the eauipment location during normal operation, assuming proper routine preventive maintenance is performed, such as periodic replacement of seals and packing.

Appendix 3.11A provides the ranges of the design temperatures, pressure, and humidities, as well as the exposures to chemical spray and radiation for each area in which safety-related eouipment listed in Appendix 3.11B is located.

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3.11.2.2 Component Environmental Design and Oualification for Operation After a Design Basis Event in Harsh and Non Harsh. Environments Equipment listed in Appendix 3.11B is designed to remain functional in the temperature, pressure, humidity, and chemical spray environment conditions that exist at the equipment location after the design basis LOCA. This equioment is also designed for the maximum calculated integrated radiation exposure after the design basis LOCA, as discussed in 3.11.5. The temperature, pressure, and humidity environment inside the containment after a LOCA is discussed in detail in Section 6.2.1.3. The containment spray characteristics are given in Section 3.11-3

6.2.2.1. The integrated post-accident radiation dosa for those areas at which equipment is located is given in Appendix 3.11A. The temperature, pressure, and humidity environment inside the centainment after a MSLB is discussed in detail in Section 6.2.1.4.

The requirement of the General Design Criteria, Appendix A to 10CFR50, are met as follows:

o Criterion 1 - Quality Standards and Records, refer to Section 3.1.1.

o Criterion 4 - Environmental and Missile Design Basis, refer to Subsection 3.1.4 o Criterion 23 - Protection System Failure Modes, refer to Section 3 .1 .19 .

o Criterion 50 - Containment Design Basis, refer to Section 3.1.43 and 6.2.1.

The requirements of the Quality Assurance Criterion III, Appendix B to 10CFR50 are met as discussed in the Design and Procurement Q.A. Program (See Chapter 17).

The recommendations contained in the documents discussed below, listings A i through D, and other applicable Regulatory Guides and Standards have also been l

utilized.

i A. Regulatory Guide 1.30, Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment.

l B. Regulatory Guide 1.73, Qualification Tests of Electric Valve Operators Installed Inside and Containment of Nuclear Power Plants. A description of the tests and analysis by which active NSSS valves are qualified is provided in Section 3.9.2.2.

3.11-4 l

l

C. The qualification methods and documentation requirements of IEEE Standard 323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations and " Category 1" of NUREG 0588, are discussed in CENPD- l 255 Rev. 3 (Reference 1).

D. Pressure boundary conoonents inside the containment are designed for the appropriate temperature and pressure environment in accordance with the applicable code to which the component is constructed.

l Qualification testing is not considered necessary for such components.

RADIATICN IN HARSH AND NON-HARSH ENVIRONMENT Electrical Eouipment will be designed for the types and levels of radiation associated with normal operation plus the radiation associated with the limiting Design Basis Accident (DBA). These levels are defined in Appendix 3.11A. If more than one type of radiation is significiant, each type may be applied separately. -

4 Electrical Equipment which is exposed to radiation above 10 Rads will be irradiated to its anticipated Total Integrated Dos 7 (TID) prior to type testing unless determined by analysis that radiation does not effect its ability to perform its required function. Where the application of the accident dose is planned during DBA testing, it need not be included during the aging process.

4 Electrical Eouipment which will be exposed to radiation levels 10 Rads or below will be analyzed to be determined whether low level radiation could impact its ability to perform its required function.

Electrical Eouipment will be qualified to the typical radiation environments defined in Appendix 3.11A, as required.

3.11-5

c-(

Gamma Cobalt-60 is considered an acceptable gamma radiation source. Other sources N may be found acceptable, and will be justified. Electrical Equipment will be '

tested to typical gamma radiation levels defined in Appendix 3.11A. ]

Beta y Electrical Eauipment exposed to beta radiation will be identified and an analysis will be performed to determine if the operability of the eouipment is affected by beta radiation ionization and heating e,ffects. Qualification will be performed by test unless analysis demonstrates that the safety functiuon will not be degraded by Beta exposure. Eauipnent will be tested and/or analyzed to the beta radiation levels defined in Appendix 3.11A. Where testing is recommended; gamma equivalent radiation source will be used.

Neutron Electrical Equipment exposed to neutron radiation will be identified and neutron radiation levels defined. When actual neutron dose qualification testing is not performed, an equivalent gamma radiation dose will be used for qualification testing to simulate neutron exposure. The basis'for establishing an equivalent ganma radiation dose will be provided.

Paints / Radiation Effects Electrical Equipment; an analysis will be performed addressing paint exposure to beta and gamma radiation, if required. Qualification of painted equipment will be by test if analysis indicates that the safety function of the equipment -

could be impaired by paint failure due to radiation.

9 3.11-6

? '&'

/

Chemical Spray Af ter a postulated accident, such as the LOCA or MSLB, components located in the Containment Building may be exposed to a chemical spray from a solution used to remove iodine from the containment building atmosphere. Equipment will be environmentally tested to these conditions and performance recuirements demonstrated during and after the test. The most severe spray composition will be determined by single failure analysis of the spray system. Corrosion effects due to long term exposure will be addressed, as appropriate.

Where qualification for chemical spray environment is recuired, the simulated spray will be initiated at the time shown in Appendix 3.11A.

Typical values of chemical spray composition, concentration and pH are defined ia Appendix 3.11 A, Tables 3.11 A-1, 3.11 A-2 and 3.11 A-13.

3.11.3 -QUALIFICATION TEST RESULTS .

3.11.3.1 NSSS Instrumentation and Electrical Eauipment Qualification testing and analyses of NSSS Instrumentation and Electrical Equipment are discussed in Reference 1.

3.11.3.2 NSSS Mechanical Eauipment Qualification test results.and analyses of NSSS Mechanical Equipment are i provide'd in Section 3.9.2.2.

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3.11.4 CLASS 1E INSTRUMENTATION LOSS OF VENTILATION EFFECTS l

loss of ventilation is discussed in the Applicant's SAR. Interface criteria are presented in Ch5pter 7.

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l 3.11-7

~

~

Class IE equipment which is located in the control roce or similar areas includes the following:

Plant Protection ~ System Cabinet (PPS)

Auxiliary Relay Cabinet ( ARC)

Auxiliary Protective Cabinet (APC)

Main Control Panels Process Instrument Cabinet Other instrumentation, siich as process transmitters and signal converters and the reactor trip switchgear system circuit breakers, are located in the Auxiliary Building or Containment Building. Ecuipnent in these areas is qualified for the maximum expected temperature, radiation, humidity, and pressure under which the equipment is' expected t'o operate.

The following are the narrol and abnormal environmental conditions for which C-E Class 1E safety-related eouipment is qualified to operate according to the service location of the equipment and the expected environmental condition.

Appendix 3.11A, Tables 3.11A-1 thru 3.11A-14 which define typical environmental conditions and associated environmental test profiles are defined in Figures 3.11 A-6A thru 3.11 A-10.

3.11.5 CHEMICAL SPRAY , RADI ATIOH, HUMIDITY , DUST, SUBMERGENCE, AND POWERSUPPLY VOLTAGE AND FREQUENCY VARIATION 3,11.5.1 Chemical Enviroranent i

! Eagineered Safety Feature Systems are designed to peform their safety-related t

functiont in the temperature, pressure, and humidity conditions described in Section 3.11.1 and' Sections 6.2 and 6.3. In addition, components of ESF systems inside the contairment are designed to perform their safety-related i

[

L

~ - 3.11-8

functions in the presence of the existing chemical environment, resulting from the boric acid and hydrazine solutions recirculated through the Safety Injection System (SIS) and Containment Spray Systems (CSS). The SIS is designed for both the maximum and long-term boric concentration and pH. These chemical environment conditions are given in Appendix 3.11A.

3.11.5.2 Radiation Environment The cocponents in the Engineered Safety Feature and Reactor Protection Systems are designed to meet their performance recuriements under the environmental and operating conditins in which they will be required to function and for the length of time for which their function is required. The comoonents are designed to ensure acceptable performance under normal operational radiation exposure in addition to the single most adverse post accident environnent. The normal operational exposures are based on the design source terms provided in Section 11.1 and Section 12.2. Radiation environments for those components for which the most adverse accident conditions are post LOCA are based on the source term assumptions consistent with Regulatory Guides 1.4 and 1.7.

Radiation environments for those compon0nts for which the most adverse accident condition is other than the LOCA (wuch as the nain steam line break, feedwater line break or CEA ejection) are based on conservative estimates of the fuel assembly gas gap activities and maximum Reactor Coolant specific activities as discussed in Section 11.1.

HUMIDITY Eauipment not subjected to steam environments during DBE testing will be environmentally tested to short term high humidity levels prior to operation and performance reautrements demonstrated during and after the test. Eaufpment that is subjected to steam environments will be subjected to the appropriate test profiles in Appendix 3.11A.

DUST Dust environments will be considered when establishing service conditions and qualification recuirements. The potential effects of dust exposure will be evaluated relative to effects upon eauionent safety function performance.

3.11-9

Where dust could have a degrading effect on eouipment safety function performance, it will be addressed in the cualification program through the development of a maintenance program and/or an upgrading of equipment interface requirements.

SUBMERGENCE Equipment locations and operability reauirements will be reviewed to establish whether or not specific equipment could be subject to submergency during its required operating time. Flood levels both inside and outside containment will be reviewed and potential impacts on equipment oualification appropriately addressed. Where operability during submerger.cy is reauired, cualification will be demonstrated by type test and/or analysis supported by partial type test data.

Power Supply Voltage and Frecuency Variation Power supply voltage and frequency variation is addressed in several areas throughout the eauipment design and verification process. During the design process interface recuriements dictate the acceptable range of power supply variation. Equipment specifications incorporate these interface requirements into the design to ensure acceptable operation within the defined range of power supply voltage and frequency variation. Upon eauipment fabrication and completion, design verification tests are performed to demonstrate design a dequency .

4 3.11-10

REFERENCES

1. " Qualification of Combustion Engineering Class 1E Instrdmentation", CENPD-255 Rev. 3, Combustion Engineering, Inc. , Windsor, Connecticut.

2. Griess, J. C. and Bacarella, A. L., " Design Considerations of Reactor Containment Spray Solutions", CRNL-TM-2412, Part III, Oak Ridge National Laboratory, Oak Ridge, Tennessee, December,1969.

3. Kircher, J. F. and Bcwman, R. E., " Effects of Radiation on Materials and Components", Van Nostrand Reinhold, New York,1964.

i 0

3.11-11

g, APPENDIX 3.11 A TYPICAL ENVIRONMENTAL CONDITIONS AND TEST PROFILES FOR ,

STRUCTURES AND COW NENTS

APPENDIX 3.11A TYPICAL ENVIRONMENTAL CONDITIONS AND TEST PROFILES F0 P, STRUCTURES AND COMPONENTS l

l

This appendix defines the generic environmental qualification requirements for CESSAR scope structures and components. The requirements are given in categories which combine various locations and conditions of design for environmental qualification purposes.

. _ . _ _ _ . = , _ _ . . _ _ _ . . . _ - . . . . . _ _ . _ ._ _ ._.____ -_ _ _ . . _ . _ _ . _ _ . _ _ _ _ .

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i l TABLE OF CONTENTS i

i CHAPTER 3 i

i I

l APPENDIX 3.11A

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t I 'Section Sub.iect Page No.

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3.11A.1 DEFINITION OF ENVIRONMENTAL CONDITIONS AND PROFILES 3.11A.1 i

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LIST OF TABLES CHAPTER 3 APPENDIX 3.11A Table Subj ect 3.11A-1 Category "A-1" Environmental Conditions (LOCA: In-Containment) I 3.11A-2 Category "A-2" Environmental Conditions (MSLB: I n-Containment) 3.11 A-3 Category "B" Environmental Conditions (Normal In-Containment) 3.11A-4 Category "C" Environmental Conditions 3.11A-5 Category "D" Environmental Conditions 3.11A-6 Category "E" Environmental Conditions 3.11A-7 Category "F" Environmental Conditions 3.11A-8 Category "G" Environt. ental Conditions 3.11A-9 Category "H" Environmental Conditions 3.11A-10 Category "I" Environmental Conditions (Outside Plant Buildings) 3.11A-11 Category "J" Environmental Conditions 3.11A-12 Category "K" Environmental Conditio'ns (Outside Plant Buildings) 3.11A-13 Category "V-1" Environmental Conditions (Worst Case: In Containment) 3.11A-14 Category "V-2" Environmental Conditions (Worst Case: Outside Containment) l l

LIST OF FIGURES CHAPTER 3 APPENDIX 3.11A Figure Subj ect 3.11A-1A Typical Containment Atmosphere Temerature Condition following (LOCA) 3.11A-1B Typical Containment Atmosphere Pressure Condition following (LOCA) 3.11A-2 Typical Annulus Atmosphere Temperature Conditfor, following (LOCA/MSLB) i 3.11A-3 Typical Containment Atmosphere Temoerature Condition following i (MSLB) 3.11A-4 Typical Containment Radiation Dose following (LOCA) 3.11A-5 Typical Containment Gamma Dose Rate following (LOCA) 3.11A-6A Typical Containrent Building Environmental Test Profile for Category "A-1" "A-2" and "V-1" Environmental Conditions 3.11 A-6B Typical Containment Building Environmental Test Profile for Category "A-1" "A-2" and "V-1" Environmental Conditions 3.11A-7 Typical Environmental Test Profile for Category "C" Environmental Conditions 3.11A-8 Typical Inside Cabinet Environmental Test Profile for Category j

"C" Environmental Conditions 3.11A-9 Typical Environmental Test Profile for Category "H." and "J" Environmental Conditions 3.11A-10 Typical Inside Cabinet Environmental Test Profile for Categories "H" and "J" Environmental Conditions l

3.11A-1 DEFINITION OF ENVIRONMENTAL CONDITIONS AND PROFILES The purpose of this appendix is to define typical environmental conditions and associated environmental test profiles.

SUMMARY

Figures 3.11A-1 A through 3.11 A-5 provide typical post accident environmental conditions. These figures are not " test" profiles and therefore do not include margin.

Tables 3.11A-1 through 3.11A-14 provide a series of tables titled

" Category "XX"" Environmental Conditions". These tables were developed for the purpose of defining a limited set of clearly established environmental conditions that could be asst -iated with specific equipment and/or locations. Appendix 3. . .A utilizes and illustrates this approach by correlatinp a generic piece of equipment with its corresponding environmental category designator.

These tables do not define actual test conditions or parameters and therefore do not include margin.

Figure 3.11A-6A and 3.11 A-6B are the in-containment test profiles that correspond to the post accident environmental conditions defined in Figures 3.11A-1 A through 3.11A-5 and Tables 3.11 A-1, 3.11 A-2 and 3.11 A-13. Both Figure 3.11 A-6A and 3.11 A-6B incorporate and illustrate reouired margin. For an explanation of the use of these profiles see Sectior 3.4.1 of CENPD 255, Rev. 03.

Figures 3.11A-7 through 3.11A-10 are test profiles for equipment located outside containment. These test profiles also incorporate margin.

3.11A-1

The test profiles included herein represent " typical" examples of qualification test profiles and are not intended to represent the complete set of all test profiles utilized.

ENVIRONMENTAL CONDITIONS A. Tables 3.11A-11 and 3.11A-2 list typical parameters for design basis accident conditions inside containment (Environmental Categories "A-1" and "A-2").

B. Table 3.11 A-3 lists typical parameters for normal environmental conditions inside containment (Environment Category "B") .

C. Tables 3.11A-4, 3.11A-11 and 3.11A-12 list typical parameters for normal environment conditions outside containment (Environment Categories "C", "J" and "K").

D. Tables 3.11 A-5 through 3.11 A-10 list typical parameters for i abnormal environment conditions outside containment (Environment Categories "D", "E", "F", "G", "H" and "I").

E. Table 3.11A-13 lists typical " Worst Case" parameters for valves inside containment (Environment Category V-1).

I F. Table 5.11A-la lists typical " Worst Case" parameters for valves outside containment (Environment Category V-2).

I G. Figures 3.11A-1 A through 3.11 A-5 provide profiles for typical post accident environment conditions.

I H. Figures 3.11A-6A and 3.11A-6B represent simulated environmental profiles for equipment located inside containment, as appropriate (Environment Categories "A-1",

"A-2" an d "V-1") .

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3.11A-2 l

I. Figures 3.11 A-7 and 3.11A-8 represent simulated

' environmental conditions for equipment located outside containment, as appropriate (Environment Category "C").

J. Figures 3.11 A-9 and 3.11 A-10 will be used to simulate environment conditions for equipment located outside containment, as appropriate (Environment Categories "H" and

. "J").

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3.llA-3

TABLE 3.114-1

. CATEGORY "A-1" EilVIR0tliiE?!TAL CONDITI0ilS (LOCA: IN-C0ilTAli!:;EilT)

ENVIRONMEBITAL 1 - -

g_ ; rf:"E t/O :C !sTIO:i l TEMPERATURE, F FIGURE 3.llA-1A ' '

PRESSURE, PSIG FIGURE 3.11A-1B SUPERHEATED STEAM / I.

HUMIDITY AIR MIXTURE RADIATIO!!, RADS FIGURES 3.11A-4 #0 3.11A-5 i

CHEMICALS NOTE '1' 1 l - ,

( ,

. i NOTE 1 - 4400 PPM BORON AS H 30 ,

5 3 50-100 PPM HYDRAZI!!E AS M H24 i

[

H AND P 4 TO 10. -

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TABE 3.11A-2 CATEGORY "A-2" EilVIR0i!MEFITAL COBIDITIO.'lS (NSLB: Ill-CollTAI."i:El!T)

I

..

3-.-,

c... 1c... 2....._ ,w ,g ..

PARAMETERS

' -- FIGURE :3.11A-3 0 .12 Mill.

TEMPERATURES F FIGURE 3.11-lA (ARER 12 tilfl.)

SAFE AS LOCA PROFIE PRESSURE, PSIG FIGURE 3:11A-1B SH STEAM / AIR MIXTURE 0-12 MIN'.'

HUMIDITY SAT'.' STEAM / AIR MIXTURE (AFTER 12 MIN.)

~

RADIATIO!!, RADS 4'.5 X 104 y (TID)

CHEMICALS NOTE '1' 30 , 50-100 PPM HYDRAZIt!E AS N 2Hu NOTE 1 - 4400 PPM BORO?! AS H53 AND PH 4 TO 10.

i TABE 3.11A-3

. CATEGORY "B" EilVIR0!!iiEllTAL CONDITIONS (NORMAL: 1:!-CO.'; Tali;.ME:!T) c,,,,,,-....._., I r:*  :.::

E n M .ic tc.r.0 Misc aum i lu.i TEMPERATURE, F 55 TO 122 CONTINU0US PRESSURE, PSIG 05 2 CONTINUQUS HUMIDITY, % 20290 ,

CONTINU0US RADIATION, RADS NOTE '1' (TID)

NOT APPLICABLE CHEMICALS NOTE 1 - DOSE VARIES WITH COMPONENT (SEE CESSAR-F', TABLE 3'.'11B-2)

O

TABLE 3.11A-4 P

4 MENTAL CO.lDITIONS CATEGORY "C" ENVIRO.

EMv!m""r! Tat '

"1-  :" ?!.T : ' .'.

i.... J. _ -.' ,

TEMPERATURE, F 55 TO 104 , CONTINUOUS PRESSURE, PSIG 0 CONTINU0US HUMIDITY, % 20 90 CONTINUGUS NOTE '1' RADIATION, RADS NOTE '2' (TID)

NOT APPLICABLE CHEMICALS l

NOTE 1 - AT OR AB0VE 800F, THE MOISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT 800F (DEWPOI NOTE 2 - DOSE VARIES WITH COMPONENT (SEE CESSAR-F, TABLE 3.11B-2).

O e

T: a :..x.-:

j CATEGORY "D" ENVIR0f! MENTAL CONDITIONS ,

ENVIRONMENTAL RANGE OR DURATION PARAMETERS MAXIMUM I; HR.

'?-112

. ,1 TEMPERAUTRE, F 104 TO 55 AFTER 4 HR.

ALL PRESSURE, PSIG 0 DURATION 20-90 HUMIDITY, % NOTE '2' NOTE '1' 4 X 10 6 y (TID)

RADIATION, RADS NOT APPLICABLE CHEMICALS NOTE 1 - AT OR ABOVE 80 F,THE MOISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE 0 HUMIDITY AT 800F (DEWPOI AT OR AB0VE 120 F, THE MOISTURE COMTENT OF 77 F).

IS THAT WHICH PRODUCES 905 RELA.TIVE HUMIDITY AT 0

120 F (DEUPOINT GF 11FF).

NOTE 2 - LIMITED TO 3 HOURS OUTSIDE THE NORMAL ~ RAN '

CATEGORY "C" UNLESS OTHERWISE SPECIFIED.

1 l T."1E 3. "? c CATEGORY "E" ENVIR0iiMENTAL CONDITIONS l

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l EN'/IRC';"E:!TAL RANGE OR PARAMETERS MAXIMUM DURATION l l

55 TO 330 0 - 3 MIN.'

r

,-..___._.._; e_ ,

104-55 AFTER 3 MIN.

3 0-3 MIN.

PRESSURE, PSIG 0 AFTER 3 MIN.

I 100 0-3 MIN.

HUMIDITY, %

NOTE '2' AFTER 3 MIN.

(NOTE '1')

RADIATION, RADS ~< 103 (TID)

CHEMICALS NOT APPLICABLE NOTE 1 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGO "C" UNLESS OTHERWISE SPECIFIED.

NOTE 2 - AT OR ABOVE 80 F, THE MOISTURE CONTENT IS THAT WHICH I PRODUCES 905 RELA.TIVE HUMIDITY AT S00F (DEMPOINT OF

- 77UF).

P"' E 3.!!;-7 CATEGORY "F" EllVIR0i! MENTAL C0!!DITIOlS ENVIRONMEilTAL P.r "r r-~ F"SE DURATION TEMPERATURE, F FIGURE 3.11A-2 (t0TE '2')

PRESSURE, PSIG 0 ALL DURATION SAT. STEAM / AIR NOTE '2' HUMIDITY MIXTURE RADIATION, RADS NOTE 'l'

~

CHEMICALS NOT APPLICABLE  !

4 y (TID) AND FOR  :

NOTE 1.- FOR UNCONTROLLED ACCESS AREAS 1 X 10 CONTROLLED ACCESS AREAS 4 X 10 6 y (TID).

i NOTE 2 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RA!!GE OF CATEGORY "C" UNLESS OTHERWISE SPECIFIED.

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IsiE3.11A-u CATEGORY "G" E:r/IRO:::'E:!TAL C0:lDITIO.4S 4

ENVIPO!'"E!!T.4L I

i TEMPERATURE, F FIGURE 3.11A-2 (iDTE '1')

PRESSURE, PSIG 0 ALL DURATION 1 l

l SAT. STEAM / AIR '

HUMIDITY NOTE '1' MIXTURE ,

RADIATION, RADS I.'1X104 y (TID)

CHEMICALS NOT APPLICABLE NOTE 1 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "C" UllLESS OTHER'dISE- SPECIFIED.

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l[U i. 3.E.-9 CATEGORY "H" E!!VIRONME!!TAL CONDITIO!!S g..., .... .._.._

rn:.c.. 6:..d RAliGE DURATION TEMPERATURE, F 55 TO 104 NOTE '2' PRESSURE, PSIG 0 ALL DUPATION HUMIDITY, % 20-90 NOTE '2' NOTE '1' RADIATION, RADS

~

<103 (TID)

CHEMICALS NOT APPLICABLE NOTE 1 - AT OR ABOVE 80 F, THE M0ISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT 80 F.(DEWPOINT OF 77 F). ,

NOTE 2 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL rah!GE OF CATEGORY "J" UNLESS OTHERWISE SPECIFIED.

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TABLE 3.llA-10 CATEGORY "I" EliVIR0!iMEilTAL C0ilDITIONS (0UTSIDE PLANT EUILDIN'iS) f c. . , . - - . . . . . .

ttnd62 CUT.:,::.'.

PAEiu,c taa F -30 TO 122 N0TE '1' TEMPEPATURE,

' 0 ALL DURATION PRESSURE, PSIG 100 NOTE '1' HUMIDITU %

RADIATION, RADS <103 (TID)

NOT APPLICABLE CHEMICALS NOTE 1 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANG "K" UNLESS OTHERWISE SPECIFIED.

- TABE 3,llA-11 -

T CATEGORY "J" Ei: VIRO.i:EilTAL C0::DITIO:lS l

l f I l PARAMETERS RANGE DURATI0il TEMPERATURE, OF 65 TO 85 CONTINUOUS PRESSURE, PSIG 0 CONTINUOUS i

HUMIDITYS% L10-60 . CONTINUGUS RADIATIO 5 RADS <105(TID)

CHEMICALS NOT APPLICABLE i

T/SLE 3.llfbl2 CATEGORY "K" EINIR0ilMEilTAL CO:lDITICils

~

(0UTSIDE PLAFlT BUILDIf1GS) .

E"'/F'""~"T;L  !

D'J.1ATIC:.

PARiuZiE.15 RAiUE

-30 TO 120 CONTINUOUS TEMPERATURE, F 0 CONTINUOUS PRESSURE, PSIG 20-90 HUMIDITY','% CONTINUOUS NOTE '1' RADIATION', RADS <103 (TID)

NOT APPLICABLE CHEMICALS

.J l

NOTE 1 - AT OR AB0VE 80 F', THE MOISTURE CONTENT IS THAT W PRODUCES 90% RELATIVE 0 HUMIDITY AT 80 F (DEW AT OR AB0VE 120 F, THE MOISTURE CONTE!!T IS 77 F).

THAT WHICH PRODUCES 90% RELATIVE HUMIDIT (DEWPOINT OF 1160F).

e 8

TABif 3.llA-]3 l CATEGOIV "-1" O :~~ '~ T L Z Z II C!3 il0TE 3 (W0r,ST CASE:  !?l-C0:: TAI::ME!!T):

RANGE DURATI0il ENVIRO l!-: ENTAL PARAMETERS 60 - 122 CONTINUOUS  ;

NORMAL 1

FIGURE 3.1]A-1A c.. p. e v. . ,.,: e , o e. LOCA ei..._ _

FIG 5E 3.1]A-3 0-12 FiIN. f MSLB FIGURE 3.1]A-JA.

AFTER 12 i1IN.

NORMAL 0-5 - CONTINUGUS

.FIGUPE 3.11A-1B LOCA PRCSSURE, PSIG ,

l

, FIGURE 3.11A-1B MSLB NOTE '1' NORMAL SAT. STEAM / AIR ALL DURATI0il LOCA MIXTURE HUMIDITY, % SH. STEAM / AIR

( 0-12 MIN.

MStB MIXTURE SAT. STEAM / AIR AFTER 12 MIN.

MIXTURE RADIATION, RADS 1 X 108 (TID)

CHEMICALS NOTE '2' l

0 FOR 80 F TO MAXIMUM NOTE 1 - 95% RELATIVE HUMIDITY (RH) AT 60 TO S0 F, 5

TEMPERATURE FIXED MOISTURE C0tlTENT IS EQUIV NOTE 2 30 , 50-100 PFil HYDRAZINE AS N H24 ANU E" 4400 PF?i BORON AS H3 3 4 TO 10.

NOTE 3 - COMBINED " WORST CASE" CONDITION FOR N

IAbi13.EA .t4 CATE3C.'J:' "'/-I" C::'.':T," ~:T '. CDITIC:S 0.0RST CASE: OUTSIE CONTAl"?:Eili): iiOTE 2 RANGE DURATION ENVIRONMENTAL PARAf1ETERS

, NORMAL 60-10l1 CONTINUOUS

' TEMPERATURE, UF i j

~

60-330 0-3 fiin.

MSLB FIGURE 3.1]A-2 'AFTER 3 MIN.

NORMAL 0 CONTINUCUS LOCA 0 A R DU N ION PRESSURE, PSIG 3 0-3 NIN'.

MSLB l ,

0 AFTER 3 MIN.

NORMAL NOTE '1' HUMIDITY' % SAT. STEAMIAIR LOCA MIXTURE ALL DURATIO'!

) SAT. STEAM / AIR l MSLB MIXTURE ALL DURATI0'l

'~

ifADIATION, RADS 5X107 (TID) ,

~

~iiEMICALS C

NOT APPLICABLE

~ NOTE 1 - 95% RELATIVE HUMIDITY (RH) AT 60 TO 80 F. FOR 80 F T0 r1AXIMUM l TEMPERATURE FIXED MOISTURE CONTENT IS EQUIVALENT TO 95% RH .

I I

AT 80 F. "

NOTE 2 - COMBINED " WORST CASE" CONDITIO:' FOR NORMAL /LOCA/MSLB ENVIR0i!"

l l

~

~

. Figure 3.11A-1A , .

TYPICAL CONTAINMENT ATMOSPHERE TEMPERATURE CONDITION FOLLOWING LOCA 5 03 , , , , ,

400 -

} .

E- .

~

6300 -

ja .. .

g200 -

RAMP TEMPl.:'T.TURE FROM INITIAL 2

AMBIENT C0!: DITION (120 F) TO PEAK -

.' iti U 100 - TEMPERATURf G50 F) OVER 10 SECONDS .

~

0 ' ' ' ' ' -

0 1 2 3 4 5 10 10 10 10 10 E~ 10 10 0

TIME, MINUTES . . -

s. . . .

e '

e e

5 FIGURE 3.11A-1B TYPIC AL CONTAINMENT ATMOSPHERE PRESSURE CONDITION FOLLOWING LOCA 70 r i i i i 60 ,,

50 g -

[ 40 81 h30 E

RAMP I ' ESSURE FROM INITIAL AMBIENT .

CONDI D ON (0 PSIG) TO PEAK PRESSURE _

20 ._

(60 PSIC) OVER 10 SECONDS .

10 -

l i ' ' '

0 -I 0 2 3 4 5 6 10 .)1 10 10 10 10 10 TIME, MINUTES

b FIGURE 3.11A-2 TYPIt AL ANNULUS ATMOS'PHERE TEMPERATURE CONDITION

-FOLLOWING. LOCAIMSLB '

500 , , , , ,

400 - -

O g{ 3m _.

E M ~

y 2W - -

s:

100

--I I I I '

0 0 2 3 4 5 6 10 g 31 10 10 10 10 10 TIME, MIN.UTES o

r FIGU'?E 3.11A-3 TYPICAL CONTAINMENT ATMOSPHERE TEMPERATURE CONDITION FOLLOWING MSLB 4M i i i i 350 300 -

Ei ~

~

f250 g RAMP TEMPERATURE FROM INITIAL AMBIENT g 0 CONDITION (120 F) TO PEAK TEMPERATURE ~

2M -

0 (370 F) OVER 10 SECONDS i

j

' - 5 150 i

6 8 10 12 i 0 2 4 TIME, MINUTES  :

e

• O I

FIGURE 3.11A-4 TYPIC AL CONTAINMENT RADIATION DOSE FOLLOWING LOCA-10 10 _ 7 , ,,,,,, , , , ,,,,, , , , , , , , , , , , , , , , , , , , , , , ,

l 10 r =

i _

o _

& 8 0 -

, y _

W-10  :  :

o  :  :

o. _

y .

10 = . -

=

106

. . , , i iiil i i i i iiiil , i i i i iil . . > > iil i . . iii 10 100 4

1 1000 10 TIME, MINUTFS p

(llII l O .

4 0

A  ; - _ D - _

1 C i i

O s e

L .

G .

N ,

I .

W .

0 O i 0

L g

. II

. 0

. 1 L . .

- O .

F .

E .

T g A .

R 5 E -

0

- g i

0 A S i

, 1 1

. 1 O .

D .

N 3 , I

. E R

A .

. M..

U G

M E I M . '

M F A I T

G . i 0 g

i

, 1 T . ,

N .

E i M e N i I o A i T

N O g s

i 1

C .

i i ,

L i

~

A '

C a -

I .

P e Y

T

- - , - - e  : - - - _- _ - - - - -

6 0

1 1 Ima<m , <& wmoo 1lllll l' 1l iIlll ll Ifll

~

FIGURE 3.11A-6A .

TYPICAL CONTAlf;t1ENT BUILDING ENVIRONMENTAL TEST PROFILE FOR CATEGORY "A-1","A-2"Afl0 "V-1" ENVIRONMEllTAL C0flDITIONS .

l k 66 PSIG g

g 4 4 65 PSIG I -- DESIGN BASIS EVENT TRANSIENTE g I~\ ADDITIOf!AL PEAX TRN5 :i I---+  ;

l,4PSIG 60 PSIG PRESSURE hs - 63 m

s - \  ;

\ *

\

\

g

. So s

5'O 1EST TIME 11M11t0 DY StrtTY RELATED _

\

TEST TIME tiMITED BY SArETY ' IATED ~ TUNCIION REQUIRWENT

• - IUNC110N REQUIREML .;

StlPERilEATED

\ *

-o SUN Rl!! ATED %

g sitv.*JAIR \ gge , SIEAM/ AIR \ ,

{

pui- '!FIED STEAMIAIR X g n en mr \ ,3Qt -3,pp

\ .A C '-A \ i3,fg -s -

[

N

. \ \ 35ff \ 319F TMP, E,R AT,UR E,,,, , , _ _ _ \ . 3G a

o n3

" s \ 3gI a

• ~s% g \

7N g *

.* \

IE'.'r;R ATUP E N\ . ,

s - 20 A . .

.i g .

iTEMP.)

s STABILIZE AT NORMAL I 5!AB1 tile AT NORMAL is (TEMP.

ENVIRONMLNT .

-g INVIRONY.ENT *

- 10 W' -

\ INITIATE CHEMICAL .

lie trRESSURO \, PRESSURD SPRAY. ,

~ *

• g 0

1000 10000 0 10 100 10 ,

0 2 '

SEC tit E, MINU1; ;

~

- CUALIFICATION LEV;'. 8/83,

, ---- TEST LIVEL .

e O .

q .

i FIGURE 3.11A-6B 1 YPICAL CONTAINMENT BUILDING ENVIRONMENTAL TEST PROFILE l OR CATEGORY "A-1","A-2" AND ' V 1" ENVIRONMENTAL CONDITIONS i

4 TR NS :

4 DESIGN BASIS EVENT TRANSIENT >

75.PSIG Saturation Pressure for 305 F

[ 75 PSIG Steam / Air liixture 3 .

PRESSURE N N - 60 G0 PfilG .

! l \ PRE: ' illE

~

GO PSIG \ , TEST TIME LIMITED BY SAFETY. ,

RELATED FUNCTIONAL REQUIREMENT

\ (*U: AM/ AIR e 400 \ U ' -(TURE) _

40 g

\

3050F E (305F

\

-- - d. _ _ _(STEAM / AIR MIXTURE) 3 o - 300  % s TEMPERATURE '*% - 30 mw m

,, N i. ] N g H

N N

3 2000F g\

g200 ~ ?!!0 F Cl . ' 'i -

'20 m 9 QUALIFICATION 4 ' STABILIZE AT NORMAL

$ TEMPERAll!: t! s F.NVIRONMENT ~ LEVEL w y4 g  : --- TEST LEVEL 100 -

I, STABILIZE r g 4

10 NORMAL INITIATE CHEMICAL SPRAY q+f ENVIRONi' ilT k .

> I I 1 e  !

I l I 2 10 1028 10 102 103 104 TIME, Mir>U ; US TIME, MINUTES -

FIGURE 3,11A-7 TYPICAL riiVIRONMENTAL TEST PROFILE FOR CATEGORY "C" ENVIRONMENTAL CONDITIONS 170 RH < 9W.

- (NO HUMIDITY CONTROL)

I NOTES:

l NOTE 4 l 150 -

RH = 90% ! 1. T = TIME TO STABILIZE TEST TEMPERATURE-EkTERNAL TO TEST ITEM l

lT S 1350F l 2. NO CONDENSATION SHALL FORM ON THE

~ ~

TEST ITEM DURING ANY PHASE OF THE -

8 HOURS 130 -

l , TESTING 1 1200F 3. TEST TEMPERATURE EXTREME INCLUDES ~ '

~

150F MARGIN i 8 HOURS

4. RH CORRESPONDSTO A DEWPOINT OF 116 F_

0

$[110 0

4 .-

E -

g 90 --

I" ~

• 750F AMBIENT 750F AT/.. NT 70 - ,

EO -

T3 40 0 F _

~

8 HOURS ,

30 DURATION O

FIGURE 3.11A-8 T Yi'ICAL INSIDE CABINET ENVIRONMENTAL TEST PROFILE FOR CATEGORY "C" ENVIRONMENTAL CONDITIONS 170 j' I NOTE 4 RH < 90%

~ ~

l ~

l (NO HUMIDITY CONTROL) 153 F l 150 -

l 8 HOURS NOTES.

~ l 1. T = TIME TO STABILIZE TEST -

! ThMPERATURE EXTERNAL TO l TESTITEM

~

,1 '; ,

l 2. NO CONDENSATION SilALL FORM ~

1200F l

~

, ON Tile TESTITEM DURING ANY -

& PHASE OF Tile TESTING ,

8 HOURS -

ui 110 -

3. TEST TEMPERATURE EXTREME ~

INCLUDES 15 F MARGIN E - 4. RH CORRESPONDESTO A _

g DEWPOINT OF 1160 F

$ 90 - -

t" iSOF AM. LNT 750F AMBIENT -

70 -

50 -

T3 400F

.8 HOURS .

30 DURATION O

l l

l FIGURE 3.11A-9 TYPICAL ENVIRONMENTAL TEST PROFILE FOR CATEGORIES "H" AND "J" i ENVIRONMENTAL CONDITIONS l 170 RH < 90 %

~ -

(NO IlUMIDITY CONTROL) 150 -

NOTES.

I

1. T = TIME TO STABil.lZE TEST l NOTE 4 I ThMPERATURE EXTERNAL TO TEST ITEM 130 -

l E i " 95 l TS 2. NO CONDENSATION SilALL FORM ON

~~

~ l 1190F l Ti1E TEST ITEM DURING ANY PHASE g OF THE HSTING l 8 HOURS

3. TEST TEMPERATURE EXTREME y110 -

l INCLUDES 150 F MARGIN l

h ~

! 4. RH CORRESPONDES TO A DEWPOINT ~

$  ! OF 770 F l

$ 90 -

.rS l g  ::00F 750F AMBIENT

[ ~ , LOURS

~750 70 - AMBir. - -

- . _ l 50 -

T3 400F _

8 HOURS DURATION

'I

~

FIGURE 3.11A-10 TYPICA1. INSIDE CABINET ENVIRONMENTAL TEST PROFILE FOR CATEGORIES"H" AND "J" ENVIRONMENTAL CONDITIONS 170 RH < 00%

~ -

l NOTE 4 l (NO IlUMIDITY CONTROL) 150 -

l l NOTES-TS 1. T = TIME TO STADILIZE TEST

- 'l 1370F l T!MPERATURE EXTERNALTO -

l l 8 HOURS TESTITEM 7 130 -

lI: I = 90% l

2. NO CONDENSATION SHALL FORM ON Tile TEST ITEM DURING ANY

~

u. - l PHASE OF THE TESTING -

l

! 3. TEST TEMPERATURE EXTREME y 110 -

l INCLUDES 150 F MARGIN -

l 0 ~

l 4. RH CORRESPONDESTO A DEWPOINT OF 770F

~

w l .. i i l g 90 -

T] 3 -

p u)0F g ~

~T. ; ,0URS 75'F AMBIENT ~

~

i 70 AkBl_ilt _

I 50 - -

T3 400F _

8 HOURS 30 -

I DURATION f I

ATTACHMENT 3 REVISION 3 TO CENPD-255 QUALIFICATION OF CLASS IE EQUIPMENT

.