ML20215L446
| ML20215L446 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/21/1986 |
| From: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| To: | Sells D Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, LIC-86-532, TAC-51091, TAC-64447, NUDOCS 8610290038 | |
| Download: ML20215L446 (73) | |
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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102-2247 402,536 4000 October 21, 1986 LIC-86-532 Mr. D. E. Sells, NRC Project Manager PWR Project Directorate #8 Division of PWR Licensing - B U.S. Nuclear Regulatory Commission Washington, D.C. 20555
References:
1.
Docket No. 50-285 2.
Letter NRC (D. E. Sells) to OPPD (R. L. Andrews) dated June 18, 1986 3.
Letter OPPD (R. L. Andrews) to NRC (D. E. Sells) dated July 8,1986 (LIC-86-328) 4.
Letter OPPD (R. L. Andrews) to NRC (D. E. Sells) dated April 1, 1985 (LIC-85-ll7)
Dear Mr. Sells:
Conformance to Regulatory Guide 1.97, Revision 2 Omaha Public Power District received Reference 1 regarding your review of OPPD's response to Generic Letter 82-33 forwarded by Reference 4.
Included in Reference 2 was a request for additional information regarding certain items related to exceptions taken to Regulatory Guide 1.97, Revision 2.
Forwarded herewith is Revision 1 to OPPD's response to Generic Letter 82-33 which provides the additional information requested. A table is provided in which summaries your comments and OPPD's response.
In addition to the specific information requested, Revision 1 also provides other revised information pertaining to the conformance of Fort Calhoun Station to the provisions of Regulatory Guide 1.97, Revision 2.
Attachment I lists the page reference and summary of changes included in Revision 1.
If you have any questions, please contact us.
Sincerely 8610290038 861021 PDR ADOCK 05000285 P
PDR R. L. Andrews Division Manager Nuclear Production RLA/me
[h cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.
\\
Washington, DC 20036 Mr. P. H. Harrell, NRC Senior Resident Inspector Ig
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ATTACHMENT 1 LIST OF CHANGES FORT CALHOUN STATION REGULATORY GUIDE 1.97. REV. 2 RESPONSE REVISION 1 Page 2 Changed 5.0 to Include Status Page 4 Editorial Correction Page 5 Update Section 2.3.2.2a to Reflect Update of Electrical Equipment Qualification Program Page 8 Update A.3.,
OPPD Position to Reflect New Inverters and Battery Chargers Page 20 Change 5.0 Title to Include Status Page 20 Added E0P Abbreviation and Define SPDS Term Page 21 Update 5.1.2 to Include ATWS Transmitter Modification Page 22 Continued 5.1.2 Update Changed Subcooled Margin Monitor to Reflect SPDS Only Added Discussion on Subcooling and ATWS to 5.1.3 Page 23 Changes 5.1.3 Summary to Reflect SPDS Being Operable Page 25 Revised 5.4.1 to Provide Additional Information Concerning Accumulator Tank Level and Pressure Page 26 Continued Revision of 5.4.1 from Page 25 Page 27 Change 5.4.3 to Reflect Proposed Addition Versus Upgrade Added Units to "200 RDT" in 5.4.4 Revised 5.4.5 to Reflect Addition Versus Upgrade Page 28 Deleted Exception Taken to Containment Sump Water Temperature Changed 5.4.7 to 5.4.6 Change 5.4.8 to 5.4.7 Page 29 Changed 5.4.8 to 5.4.7 i
Changed 5.4.9 to 5.4.8 Changed 5.4.10 to 5.4.9 Page 30 Changed 5.4.10 to 5.4.9
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Page 31 Added 5.4.10 to Discuss Component Cooling Water Temperature Added 5.4.11 to Discuss Component Cooling Water Flow Added Section 5.5 Type E Variables Added Revised Meteorology Commitment Page 32 Updated 6.1.1 to Show Coraplete Updated 6.1.2 to Show Complete Updated 6.1.3 to Show Installed Updated 6.1.4 to Reflect ATWS Updated 6.2.1 to Clarify Category and Equipment Addition Updated 6.2.3 to Reflect Proposed New Channels Move 6.2.5 to Page 33 Page 33 Moved 6.2.5 from Page 32 Added 6.2.6 Sump Temperature Schedule Added 6.3 Type E Variables Added 6.3.1 Meteorological Schedule Table 1, Page 1 Updated II.2 to Reflect ATWS Updated II.3 to Reflect QSPDS/SPDS Table 1, Page 2 UpAted III.1 to Reflect New RTDs Upuated III.2 to Reflect New RTDs Updated III.3 to Reflect Qualified CETs Table 1, Page 20 Updated VII.3 to Reflect New Channels to be Installed Updated VII.4 to Reflect Installation Schedule Updated VIII.2,3 Changed Reference Number Table 1, Page 21 Updated IV.1 and IV.2 to Provide Additional Discussion Table 1, Page 21 X.2 Changed Reference Number Table 1, Page 25 Updated Meteorology V.1 and V.2 to Reflect Calibration Revision Required Table 1, Page 26 Updated V.3 to Reflect Calibration Revision Required Table 1, Page 28 Updated VI.B.2 to Reflect SER
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ATIAC11 MENT 2 VARTABIE EXCEPTION 'IAKEN BY OPPD RESPCNSE SUMERY Revision 0 Revision 1
- l. Am=0ator (Safety Iniection) Tank Tank status is not required for Additional justification for not in-Isvel and Pressure safe shutdown fran a DBA.
cluding these variables is prwided.
- 2. Containment Suno Water band 6ture Sung t.-.1 - shire is not a Reconnend adding a single channel of mea-l permin=ive for RAS. Susp stu. cum:aat qualified to 10 GR 50.49 and t-s - & Lire can be inferred from IEEE 344-1975 during the 1988 refueling CE7f's.
outage.
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- 3. Otmoonent Coolincr Water Flow to ESF Transmitter is in a mild Provide additional justification for the System envitu==:aut for at least the first use of alternate means of measurenent 20 mimtes of a DBA. 'Ihis is whidt is envitu==adally qualified or is considered adar==te to establish in a mild envitu===>L.
Proper system operation.
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- 4. Cuiu r= sit Coolinct Water Tencerature TE-2800 is in a mild envisu==ait Provide justification for an alternate i
for at least the first 20 minutes means of measuring these t% dtures.
of a DBA.
2*.ds is considered Variables are located in a mild i
W ute to establish proper envitu=== >t.
l system operation.
- 5. Wind Direction OPPD anheitted an accuracy of Establish a calibration prmartwe to 5.4 *, required is 15*.
insure 15' ura=riainty limit. 'Ihis will require an uncertainty analysis as 1
defined in Regulatory Guide 1.23.
Please note this analysis will have to P
be ocupleted for wind speed and atmospheric stability ( T) as well.
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REVIS's0N 1 FORT CALHOUN STATION REGULATORY GUIDE 1.97, REV 2
RESPONSE
.C_QE
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0BJECTIVE The objectives of this review are to:
I.
Provide additional information on certain Reg. Guide 1.97 variables which the NRC has taken issue with the District's request for exemptions (see Reference a and Table 1, attached).
II.
Determine an installation schedule if the review conducted in Item 1 indicates hardware should be added.
III.
Update the Reg.
Guide 1.97 submittal to reflect Items 1 and 2 and those modifications which have been completed since the April 1, 1985 submittal date (see Reference b for original submittal).
METHOD I.
Each variable will be reviewed for its:
a.
Requirement in the E0P's b.
Alternate indication available to support correct system performance, and availability of alternate indication to derive the variable in question.
c.
Each section will contain a conclusion section.
II.
Variables requiring hardware installation:
a.
Assess if it is an online or outage modification.
b.
Recommend inclusion in the 1987 outage or online list or the 1988 outage list.
III.
Update of the Reg. Guide 1.97 submittal will be completed by:
a.
Review of the Reg. Guide 1.97 submittal and update to reflect j
I and II, (Reference 2).
b.
Review of the MR files and related SER's.
REFERENCES:
a.
Letter D.
E.
Sells to R.
L. Andrews, dated June 18, 1986, "Conformance to Regulatory Guide 1.97, Revision 2."
b.
LIC-85-117, dated April 1, 1985, " Reg. Guide 1.97 Compliance".
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E0P-01, Reactor Trip d.
E0P-03, Loss of Coolant Accident e.
E0P-05, Uncontrolled Heat Extraction f.
E0P-20, Functional Recovery Procedure g.
01-RC-4, 0I-RC-11, OP-7, OP-8 h.
USAR Section 6 i.
Il405-M-10 J.
TS-FC-86-121P k.
Pass SER's dated 1/1/83 and 9/1/83 l.
Meteorological calibration procedures:
6272, 6273, 6274, 6275, 6276, 6277, 6278, 6279, 6280, 6281, 6282, 6283, 6284, 6285 m.
Hot and cold leg temperature calibration procedures:
B/1120,B/112H n.
Reg. Guide 1.23, " Meteorology" o.
GSE Task FC-75-21, "110M Weather Tower" p.
15381-ICE-3219 Rev.
3, "QSPDS Data Base Description" i
q.
Rosemount drawing 104MA r.
CP493, 494, 495, 496 i
s.
MR-FC-84-140, MR-FC-81-99 REVIEW 1,
Review the five Reg. Guide 1.97, Revision ? variables listed in Section 4
of Reference a.
to determine what additional justification is available to support the exemption request, or what other action (including hardware upgrade) should be taken.
I.
accumulator Tank (SI tank) Pressure and level 3
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E0P reauirement:
A review of E0P -
1, 3,
5 and 20 (References c, d, e, f) indicate that no specific information on the SI tanks is required.
The only reference to SI tank pressure in the E0P is by reference to the cold (normal cooldown) shutdown procedure 01-RC-4 in which the tanks are isolated at less than 400 psia prior to going below SI tank pressure in the RCS.
The 400 psia can be determined by RCS instrumentation, which precludes the need for SI tank information in the E0P's.
b.
Alternate indication to support correct system performance or indicate the variable in auestion The SI tanks are passive in nature in that no operator or automatic action via any active component (air or electric powered) is required, nor could any be expected to be used in insuring the SI tank inventory is used in DBA function. With this criteria there is no specific confirmatory action for the SI tank, nor is there any criteria to determine proper function of the SI tanks based on SI tank parameters.
Proper tank performance is concluded based on the reactor parameters of cooling (CET's and/or RTD's) and RCS inventory.
This is considered adequate since these are the E0P goals.
c.
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Conclusion:==
Based on the above discussion, no further action is required.
The SI tank level and pressure instruments do not require upgrading.
II.
Containment sumo water temperature a.
E0P reauirement:
A review of E0P 1,
3, 5,
and 20 (References c, d, e, f) indicates no requirement for the sump temperature. The only reference to a sump temperature requirement is in the USAR j
Section 6.2.5.
The ESF system performs adequately to insure j
the NPSH of the SI pumps is adequate for recirculation actuation (USAR Section 6.2.6 Reference 8).
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b.
Alternate indication to suonort correct system performance or l
indicate the variable in auestion l
There is no action the operator can take (above automatic actuation of the ESF system) to insure SI pump NPSH, thus additional indication would not be beneficial.
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There is no alternate method of determining the sump temperature.
In the case of a LOCA it can be inferred from RCS temperature many hours into the DBA but inaccurately due to the containment cooling, and becomes more inaccurate with reduced break size.
In the event of a MSLB there is no way of determining the sump temperature.
c.
Conclusion.
A Category 2 instrument per Regulatory Guide 1.97 should be added to assist in overall system performance evaluation.
III. Component coolina water flow to ESF system a.
E0P reauirements:
E0P -
1, 3,
5, and 20 safety function status check require pump running verification.
b.
Availability of alternate indication to determine system performance and alternate variable indication.
The CCW system operation can be confirmed by motor current (which is proportional to flow), direct reading containment cooling unit discharge flows, (F416, F417, F418, F419) and CCW system valve position indication.
c.
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Conclusion:==
The alternate indication available provide ample system performance indication.
It should also be noted that the raw water system is provided as a fully redundant system to the CCW system.
This system is provided with adequate flow indication (F-2890 and F2891).
No further instrumentation is required.
i IV.
Component coolina water temperature a.
E0P reauirement:
E0P -
1, 3,
5, and 20 do not require CCW temperature monitoring.
b.
Alternate indication to sunnnrt correct system oerformance, I
and availability of alternate indication.
T-493, T-494, T-495, and T-496 provide heat exchanger outlet i
temperature to CCW pump suction, T-2800 is provided for CCW pump discharge temperature.
These are considered equivalent l
in monitoring CCW system performance.
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'The -four temperatures are located in a mild environment and are considered CQE.
c.
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Conclusion:==
TE-493, TE-494, TE-495, and TE-496 should be substituted as j
the category 2 variables. No other action is required.
V.
Wind Direction a.
E0P reouirement:
This variable is required for the EPIP dose assessment.
b.
Alternate indication available to suonort system performance and alternate variable indication.
Tiie Omaha NOAA weather station serves as a backup source of 4
information, l'
It should be noted that according to specification of GSE Task i
FC-75-21 (110M Weather Tower) the instruments are designed to meet the Reg. Guide 1.23 accuracy of iS*.
c.
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Conclusion:==
I All wind speed, wind direction, and differential temperature require an analysis and calibration uncertainty determination to meet Regulatory Guide 1.97 and 1.23 uncertainties.
VI.
Replacement schedule i
j Containment Sumo Water Temperature j
The addition of this sensor will require a refueling outage for installation and will include a cable installation from the Control Room to the containment.
Based on the outage installation requirements, installation should be completed in the 1988 refueling outage.
l Wind Direction 1
An uncertainty analysis in compliance with Reg. Guide 1.23 is required.
The next scheduled time for calibration is the spring of 1987 six month calibration.
Please note, all meteorological l
instruments must have the uncertainty analysis completed.
VII.
Reaulatory Guide 1.97 Submittal Update to Reflect Completed l
Construction i
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A.
Reactor Coolant Pressure (Cat. 1)
Based on the ATWS event analysis, the expected peak RCS pressure resulting for a Diverse Scram System trip is 2600 psia. A transmitter range of 1900 to 2900 psia is being installed during the 1987 refueling outage.
This is considered acceptable as stated in the NRC letter (Reference a).
B.
Reactor Coolant System Hot and Cold lea Temperature: Subcooled Marain Monitor (Cat. 1).
The hot and cold leg RTD's have been replaced per MR-FC-84-140.
Subcooling is calculated by the QSPDS, which was installed per MR-FC-81-99.
Temperature ranges were revised from the proposed 0*F-750*F to 50*F-700*F which is in conformance to Reg. Guide 1.97 requirements.
Subcooling is calculated using the wide range pressure channels (0 to 2500 psia).
It should be noted that the ATWS event pressure channels (1900 - 2900 psia) are not considered to be required for subcooling calculations. The ATWS event is an overpressure event in which subcooling is not of prime concern.
C.
Vessel level Monitorina (Cat. 1)
The vessel level system has been installed and is functional.
The District has not yet received an SER from the NRC.
D.
Containment Atmosohere Temoerature (Cat. 2)
The containment ventilation fan inlet temperatures as proposed in the Reg.
Guide 1.97 compliance letter (Reference b) are not considered to be adequate to provide a representative temperature for containment, see Reference J.
A multisensor system monitoring temperature at various levels of containment is proposed.
E.
Primary coolant oxvaen content This variable is not required per SER's (Reference k) transmitted to the District.
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TABLE 1 VARIABLE EXCEPTION TAKEN BY OPPD 1.
Accumulator (safety injection)
Tank status is not required for Tank Level and Pressure safe shutdown from a DBA.
2.
Containment Sump Water Sump temperature is not a
Temperature.
permissive for RAS.
Sump tempera-ture can be inferred from the CET's.
3.
Component Cooling Water Flow to Transmitter is in a
mild ESF System.
environment for at least the first 20 minutes of a DBA.
This is considered adequate to establish proper system operation.
Cooling Water TE-2800 is in a mild environment 4.
Component Temperature.
for at least the first 20 minutes of a DBA.
This is considered adequate to establish proper system operation.
5.
Wind Direction OPPD submitted an accuracy of 5.4*, required is 5*.
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FORT CALHOUN STATION REGULATORY GUIDE 1.97, Rev. 2
RESPONSE
ES-84-07 OCTOBER 1986 Rev. 1
C0NTENTS Page 1.0 PURPOSE.............................
3 1.1 Introduction........................
3 2.0 CRITERIA.............................
3 2.1 General...........................
3 2.2 Identification of Variables.................
3 2.3 Design and Qualification Criteria (Reg. Guide 1.97) and District's Position....................
4 3.0 METHODOLOGY FOR REVIEW......................
18 4.0
SUMMARY
OF DISTRICT'S REVIEW...................
19 5.0 EXCEPTIONS TO Reg. Guide 1.97, REV.2 AND STATUS UPDATE......
20
/b 5.1 Type "A" Variables.....................
21 5.2 Type "B" Variables.....................
24 5.3 Type "C" Variables.....................
25 5.4 Type "D" Va ri abl es.....................
25 5.5 Type "E" Variables.....................
31 6.0 DESIGN DESCRIPTION AND SCHEDULE FOR IMPLEMENTATION OF IDENTIFIED UPGRADES.......................
31 6.1 Type "A" Variables......................
31 6.2 Type "D" Variables......................
32 7.0 REFERENCE DOCUMENTS........................
32 ATTACHMENTS Table 1 i
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Fort Calhoun Station Regulatory Guide 1.97, Rev. 2 Response 1.0 PURPOSE
1.1 INTRODUCTION
NUREG-0737, Supplement 1 (Ref. 7.1) required utilities to review compliance with Reg. Guide 1.97, Rev. 2, dated December 1980, "Instru-mentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," and to identify instrumentation necessary to monitor plant variables and systems following an accident.
In response to these requirements, the District submitted a plan and a schedule for performanc. of Reg. Guide 1.97, Rev. 2 review (Ref. 7.2). The purpose of this report is to summarize the evaluation of applicable existing instrumentation at the Fort Calhoun Station against the criteria of Reg. Guide 1.97, Rev. 2.
The evaluation was intended to determine compliance, compliance with exceptions, or non-compliance with the criteria of Reg. Guide 1.97, Rev. 2.
Based upon this evaluation, several upgrades are planned for the accident monitoring instrumentation at the Fort Calhoun Station to comply with the requirements of Reg. Guide 1.97, Rev. 2.
A schedule for implementation of these upgrades is included in Section 6.0 of this report.
2.0 CRITERIA 2.1 GENERAL 2.1.1 The following sections describe the specific criteria utilized by OPPD in evaluating the accident monitoring instrumentation at the Fort Calhoun Station.
2.2 IDENTIFICATION OF VARIABLES 2.2.1 PWR Variables Per Reg. Guide 1.97, Rev. 2 The following are definitions of variables investigated in this study, quoted directly from Reg. Guide 1.97, Rev. 2:
A.
Type A Those variables to be monitored that provide the primary information required to permit the control room operators to take the specified manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis accident events..
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Primary information is information that is essential for the direct accomplishment of the specified safety functions; it does not include those variables that are associated with contingency actions that may also be identified in written procedures.
A variable included as a Type B, C, D or E does not preclude that variable from also being included as Type A.
B. Type B
...those variables that provide information to indicate whether, plant safety functions are being accomplished.
[ 21 Plant safety functions are (1) reactivity control, (2) core cooling, (3) maintaining reactor coolant system integrity, and (4) maintaining containment integrity (including radioactive effluent control).
Variables are listed with designated ranges and category for design and qualification requirements. Key variables are indicated by design and qualification Category 1.
C. Type C Those variables that provide information to indicate the Jotential for being breached or the actual breach of the Jarriers to fission product releases. The barriers are (1) fuel cladding, (2) primary coolant pressure boundary, and (3) containment.
D. Type D Those variables that provide information to indicate the operation of individual safety systems and other systems important to safety.
These variables are to help the operator make appropriate decisions in using the individual systems important to safety in mitigating the consequences of an accident.
E. Type E Those variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and continually assessing such releases.
2.3 Design and Qualification Criteria (Reg. Guide 1.97, Rev. 2) 2.3.1 Each licensee must identify the different types of instru-mentation, explain their function and show that this instru-mentation is within the Reg. Guide 1.97, Rev. 2 parameters.
To accomplish this, each individual variable was assigned a Design and Qualification Criteria Category that outlines the specific requirements that each variable is to meet.
The Design and Qualification requirements applicable to these categories are discussed in Section 2.3.3 below..
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2.3.2 Clarifications and Revisions to NRC Reg. Guide 1.97, Rev. 2 requirements.
2.3.2.1 Fort Calhoun Unit I was operating at the time Regulatory Guide 1.97, Rev. 2, was issued.
Accordingly Fort Calhoun is required to meet the pro /isions of NUREG-0737 and the Commission Memorandum and Order (CLI-80-21) instead of Reg.
Guide 1.97 for those items addressed by NUREG-
- 0737, 2.3.2.2 Subsequent ta issuance of Reg. Guide 1.97, Rev. 2, the staff has issued several clarifications and revisions, amending the applicability and require-ments of the Reg. Guide. A summary of these changes as they apply to Fort Calhoun Unit 1 is provided below.
a.
NUREG-0737 Supplement #1 stated that it was acceptable to rely on currently installed equipment if it would measure over the range indicated in Reg. Guide 1.97 (Rev. 2) even if the equipment was presently not environ-mentally qualified. Environmental qualifi-cation requirements were codified in 10 CFR 50.49. Based on the date of the Fort Calhoun Operating License, these requirements are as specified in the 00R guidelines. Accordingly it is our interpretation that the environ-mental qualification requirements of Reg.
Guide 1.97 have been superseded by 10 CFR 50.49.
Items referenced in Table 1 as being A
qualified to 10 CFR 50.49 have been included in the District's EEQ program.
b.
During regional briefings the staff clarified that QA requirements for existing instru-mentation shall be better than or consistent with the QA requirements as they applied at the time of issuance of construction permit (instead of Regulatory Guide 1.97 require-ments).
2.3.3 The Design ar't Qualification requirements applicable to various categeries defined in Reg. Guide 1.97, Rev. 2 are as follows. The District's position on each specification follows the Reg. Guide's category requirements for the respective specification.
- A.
CATEGORY I 1.
EQUIPMENT QUALIFICATION Reg. Guide Requirements The instrumentation should be qualified in accordance with Reg.
Guide 1.89, " Qualification of Class 1E Equipment for Nuclear Power Pla'ts," and the methodology described in NUREG-0588,
" Interim itaff Position on Environmental Qualification of Safety-Related Electrical Equipment." Qualification applies to the complete instrumentation channel from sensor to display where the display is a direct-indicating meter or recording device.
Where the instrumentation channel signal is to be used in a computer-based display, recording, and/or diagnostic program, qualification applies from the sensor to and includes the channel isolation device. The location of the isolation device should be such that it would be accessible for maintenance during accident conditions. The seismic portion of qualification should be in accordance with Reg. Guide 1.100, " Seismic Qualification of Electrical Equipment for Nuclear Power Plants," Instrumentation should continue to read within the required accuracy following, but not necessarily during, a safe shutdown earthquake.
Instrumentation whose ranges are required to extend beyond those ranges calculated in the most severe design basis accident event for a given variable should be cualified using the guidance provided in paragraph 6.3.6 of ANS-4.5.
DISTRICT'S POSITION Environmental Qualification As discussed in Section 2.3.2, the environmental qualification criteria outlined in the Reg. Guide has been superseded by 10 CFR 50.49 for Categories 1 and 2.
Compliance with 10 CFR 50.49 ruling is therefore considered adequate to meet the environmental qualification requirements of Reg. Guide 1.97 Category 1 (and 2) instrumentation. For Category 1 variables, the sensors and/or transmitters which are located in a harsh environment have been or will be replaced to comply with 10 CFR 50.49 requirements.
However, the remaining components of these instrument loops (such as indicators, power supplies, etc.) are located in a mild environment, were not required to be qualified to 10 CFR 50.49 requirements and were not replaced. These components were analyzed / tested per the requirements applicable at the time of issue of construction permit..
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A.
CATEGORY 1 (Continued)
Seismic Qualification Reg. Guide 1.97, Rev. 2 requires certain post-accident monitoring instrumentation to be qualified to Reg. Guide 1.100. The District has complied with this requirement (where applicable) on post-accident monitoring instrementation installed per NUREG 0737 requirements (such as containment hydrogen analyzers, containment high-range radiation monitors, etc.) However, the majority of the post-accident monitoring instrumentation was installed during initial construction and was not upgraded. The seismic qualifi-cation issue is also being addressed by the Commission through other means such as unresolved safety issue G-46.
Pending final resolution of this issue, the District believes that the seismic qualification requirements applicable at the time of issuance of the construction permit are adequate to meet the intent of Reg.
Guide 1.97.
Seismic qualification of electrical components is discussed in the Fort Calhoun USAR, Appendix F.
Requalification
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or replacement of these components to latest requirements would not significantly improve plant safety. The District, therefore, takes exceptions to upgrading the existing instrumentation to comply with Reg. Guide 1.100 requirements.
In summary, the seismic requirements of Reg. Guide 1.97, Rev. 2 have been applied to post-accident instrumentation installed because of the requirements of NUREG-0737 and instrumentation upgraded per 10 CFR 50.49. These requirements (where applicable) will also be applied to future upgrades. However, the existing instrumentation which was not upgraded per NUREG-0737 or 10 CFR 50.49, complies with the requirements applicable at the time of issuance of the construction permit. This is considered adequate to meet the intent of Reg. Guide 1.97, Rev. 2.
2.
REDUNDANCY Reg. Guide Requirements No single failure within either the accident-monitoring instru-mentation, its auxiliary supporting features, or its power sources concurrent with the failures that are a condition or result of a specific accident should prevent the operators from being presented the information necessary for them to determine the safety status of the plant and to bring the plant to and maintain it in a safe condition following that accident. Where failure of one accident monitoring channel results in information ambiguity (that is, the redundant displays disagree) that could lead nparators to defeat or fail to accomplish a reouired safety function, additional information should be provided to allow the operators to deduce the actual conditions in the plant. This may v--.
2.
REDUNDANCY (Continued)
Reg. Guide Requirenents (Continued) be accomplished by providing additional independent channels of information of the same variable (addition of an identical channel) or by providing an independent channel to monitor a different variable that bears a known relationshi) to the mul-tiple channels (addition of a diverse channel.)
Redundant or diverse channels should be electrically independent and physi-cally separated from each other and from equipment not classified important to safety in accordance with Regulatory Guide 1.75,
" Physical Independence of Electric Systems," up to and including any isolation device. At least one channel should be displayed on a direct-indicating or recordine device.
(Note: Within each redundant division of a safety system, redundant monitoring channels are not needed except for steam generator level instru-nentation in two-loop plants.)
DISTRICT'S POSITION The District has reviewed the redundancy requirements of Reg.
Guide 1.97, Rev. 2. The majority of the Category 1 variable monitoring instrumentation at the Fort Calhoun Station is com-prised of four completely independent channels. Only a few cases have been noted in which two completely independent channels are available.
In these cases we believe there is sufficient diversity among the instrumentation systems currently available so that information ambiguity will not be caused by a failure of any s' ingle channel. The District believes that the use of two completely independent channels meets the intent of Category I redundancy requirements and thus it has been noted in Table 1 that these loops are in compliance with the Reg. Guide.
3.
POWER SOURCE Reg. Guide Requirements The instrumentation should be energized from station Standby Power sources as provided in Regulatory Guide 1.32, " Criteria for 5afety-Related Electric Power Systems for Nuclear Power Plants,"
and should be backed up by batteries where momentary interruption is not tolerable.
DISTRICT'S POSITION The instrumentation which is identified as being powered from a Class IE power supply in Table 1 is energized from the station standby power sources and is backed up by batteries. However, the power distribution system was designed ard installed in accordance with the requirements that applied at the time of issuance of the construction permit (Ref. USAR Section 8) rather than those of Reg. Guide 1.32.
Note that during the 1985 refueling outage the station's battery chargers and inverters
/
were replaced with " equal to or better than" equipment. The USAR Section 8 criteria is still considered valid..
4.
CHANNEL AVAILABILITY Reg. Guide Requirements The instrumentation channel should be available prior to an accident exce)t as provided in paragraph 4.11, " Exemption", as defined in IEEE Standard 279 or as specified in the Technical Specifications.
DISTRICT'S POSITION No exception is taken to this criteria. The availability of vital instrumentation is governed by the Fort Calhoun Technical Specification requirements. This criterion is not specifically headlined in Table 1 since the District is in compliance with this criteria.
5.
QUALITY ASSURANCE Reg. Guide Requirements The recommendations of the following regulatory guides pertaining to quality assurance should be followed:
" Quality Assurance Program Requirements (Design and Construction)"
" Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment" Regulatory Guide 1.38
" Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants" Regulatory Guide 1.58
" Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel" Regulatory Guide 1.64
" Quality Assurance Requirements for the Design of Nuclear Power Plants" Regulatory Guide 1.74
" Quality Assurance Terms and Definitions" Regulatory Guide 1.88
" Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records" Regulatory Guide 1.123
" Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants".
Reg. Guide Requirements (Continued)
" Auditing of Quality Assurance Programs for Nuclear Power Plants" Regulatory Guide 1.146
" Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants" Reference to the above regulatory guides (except Regulatory Guide 1.30 and 1.38) is being made pending issuance of a regulatory guide (Task RS 002-5) that is under development and will endorse ANSI /ASME NQA-1-1979, " Quality Assurance Program Requirements for Nuclear Power Plants."
DISTRICT'S POSITION As discussed before, it was clarified during regional meetings that the QA requirements for existing instrumentation shall be better than or consistent with the QA requirements as they applied at the time of issuance of the construction permit rather than Reg. Guide 1.97 requirements. Additionally, NUREG-0737 contained certain QA requirements of its own. The District's position on the various QA requirements applicable to Fort Calhoun Unit 1 is delineated in the Fort Calhoun QA program as described in the Fort Calhoun USAR (Appendix A), and the Quality Assurance Plan.
Nuclear Safety Related components and services which fall within the scope of 10 CFR 50 Appendix 8 and 10 CFR 50.49 are classified as CQE (Critical Quality Elements). CQE components are procured and maintained in accordance with the District's QA plan. Unless otherwise noted in Table 1, Category 1 and 2 instrumentation falls with the definition of CQE and is procured and maintained in accordance with the applicable requirements.
The District believes that compliance with the requirements as outlined in our Quality Assurance Plan is adequate to meet the intent of Reg. Guide 1.97 Rev. 2.
We therefore take exception to meeting the QA requirements as detailed in Reg. Guide 1.97.
6.
DISPLAY Reg. Guide Requirements Continuous indication (it may be by recording) display should be provided. Where two or more instruments are needed to cover a particular range, overlapping of instrument span should be provided..
DISTRICT'S POSITION The District, while taking no exception to this requirement, would like to clarify that the displays available on demand on the Safety Parameter Display System (SPDS) are considered continuous displays.
7.
RECORDING Reg. Guide Requirements Recording of instrumentation readout information should be provided. Where direct and immediate trend or transient inform-ation is essential for operator information or action, the recording should be continuously available on dedicated re-corders. Otherwise, it may be continuously updated, stored in computer memory, and displayed on demand.
Intermittent displays such as data loggers and scanning recorders may be used if no significant transient response information is likely to be lost by such devices.
DISTRICT'S POSITION Recording capabilities are noted in Table 1.
B.
CATEGORY 2 1.
EQUIPMENT QUALIFICATION Reg. Guide Requirements The instruinentation should be qualified in accordance with Regulatory Guide 1.89 and the methodology described in NUREG-0588. Seismic qualification according to the provisions of Regulatory Guide 1.100 may be needed provided the instrumentation is part of a safety-related system. Where the channel signal is to be )rocessed or dis) layed on demand, qualification applies from t1e sensor throug1 the isolator / input buffer. The location of the isolation device should be such that it would be accessi-ble for maintenance during accident conditions.
DISTRICT'S POSITION The District's position on equipment qualification for Category 2 requirements is the same as that discussed in Section 2.3.3.A.1 for Category 1 instrumentation. For Category 2 instrumentation located in a mild environment it is noted that the requirements of 10 CFR 50.49, (environmental qualification) are not applic-able..
No specific seismic qualification requirements were referenced in Reg. Guide for Category 2.
However, there are several systems used for accident monitoring which have transmitters that are seismically qualified to IEEE-344-1975.
If qualified to the standard, it is so noted.
2.
REDUNDANCY Reg. Guide Requirements No Specific Provision.
DISTRICT'S POSITION Since no specific provisions for redundancy were listed, the District finds that the instrumentation loops provided meet the Category 2 requirements.
3.
POWER SOURCE Reg. Guide Requirements The instrumentation should be energized from a high-reliability power source, not necessarily Standby Power, and should be backed up by batteries where momentary interruption is not tolerable.
DISTRICT'S POSITION Instrumentation as specified in the Reg. Guide is to be powered by a highly reliable source. The District has reviewed the power supply systems for Category 2 instrumentation and takes no exception to this requirement.
4.
CHANNEL AVAILABILITY Reg. Guide Requirements The out-of-service 1.;terval should be based on normal Technical Specification requirements on out of service for the system it serves where applicabli or where specified by other requirements.
DISTRICT'S POSITION The District takes no exception to this requirement. Out of service intervals for instrumentation are based on the Technical Specifications in accordance with the Reg. Guide requirements..
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5.
QUALITY ASSURANCE Reg. Guide Requirements The recommendations of the Regulatory Guide pertaining to quality assurance listed under paragraph 1.3. i.e. of this guide should be followed. Reference to the above reg. guides (except Reg.
Guides 1.30 and 1.38) is being made pending issuance of a Reg.
Guide (Task RS 002-5) that is under development and will endorse ANSI /ASME NQA-1-1979. Since some instrumentation is less impor-tant to safety than other instrumentation, it may not be neces-sary to apply the same quality assurance measures to all instru-mentation. The quality assurance requirements that are imple-mented should provide control over activities affecting quality to an extent consistent with the importance to safety of the instrumentation. These requirements should be determined and documented by personnel knowledgeable in the end use of the instrumentation.
DISTRICT'S POSITION The District's position on QA requirements is as discussed in Section 2.3.3.A.5 for Category 1 instrumentation.
6.
DISPLAY Reg. Guide Requirements The instrumentation signal may be displayed on an individual instrument or it may be processed for display on demand by a CRT or by other appropriate means.
DISTRICT'S POSITION The District takes no exception to the above requirements, and specifies display location in Table 1.
7.
RECORDING The method of display may be by dial, digital, CRT, or stripchart recorder indication. Effluent radioactivity monitors, area radiation monitors, and meteorology monitors should be recorded.
Where direct and immediate trend or transient information is essential for operator information or action, the recording should be continuously available on dedicated recorders. Other-wise, it may be continuously updated, stored in computer memory, and displayed on demand.
DISTRICT'S POSITION The District takes no exception to the above requirements.
i.
I i
C.
CATEGORY 3 1.
EQUIPMENT QUALIFICATION Reg. Guide Requirements I
The instrumentation should be of high-quality comercial grade and should be selected to withstand the specified service envi-ronment..
i DISTRICT'S POSITION h
The District takes no exceptions to this requirement.
2.
REDUNDANCY Reg. Guide Requirements No Specific Provisions, j-DISTRICT'S POSITION Same as per the Reg. Guide requirement.
1 3.
POWER SOURCE Reg. Guide Requirenents No Specific Provisions.
DISTRICT'S POSITION i
Same as per the Reg. Guide requirement.
4.
CHANNEL AVAILABILITY Reg. Guide Requirements No specific provisions.
DISTRICT'S POSITION I
Same as per the Reg. Guide requirement.
l S.
QUALITY ASSURANCE Reg. Guide Requirements No Specific Provisions, i
DISTRICT'S POSITION Same as per the Reg. Guide requirement.
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6.
DISPLAY Reg. Guide Requirements The method of display may be by dial, digital, CRT, or strip chart recorder indication. Effluent radioactivity monitors, area radiation monitors, and meteorology monitors should be recorded.
Where direct and immediate trend or transient information is essential for operator information or action, the recording should be continuously available on dedicated recorders. Other-wise, it may be continuously updated, stored in computer memory, and displayed on demand.
DISTRICT'S POSITION Same as per Reg. Guide requirement.
D.
ADDITIONAL CRITERIA FOR CATEGORIES 1, 2, and 3 Reg. Guide Requirements 1.
The followina criteria should apply to Categories 1 and 2:
a.
Any equipment that is used for either Category I or Category 2 should be designated as part of accident monitoring instru-mentation or systems operation and effluent-monitoring instrumentation. The transmission of signals from such equipment for other use should be through isolation devices that are designated as part of the monitoring instrumenta-tion and that meet the provisions of this document.
DISTRICT'S POSITION We believe that the above requirement is overly restrictive. The use of post-accident instrumentation should be encouraged for both normal operation and for other safety functions. This will improve operator awareness and confidence in such instrumenta-tion.
If the loop consists of safety grade (CQE) and non-safety grade (non-CQE) components, the non-CQE. portion should be iso-lated from the CQE portion through isolators.
Isolation devices meeting the requirements as they applied at the time of issuance of the construction pennit are provided between safety grade (CQE) and non-safety grade (non-CQE) portions of instrument loops.
Isolation devices for instrumentation in-stalled per NUREG-0737 requirements comply with the requirements of NUREG-0737.
In view of the above the District takes exception to the speci-fied Reg. Guide 1.97, Rev. 2 requirements outlined above.
l
- L
D.
ADDITIONAL CRITERIA FOR CATEGORIES 1, 2, and 3 Reg. Guide Requirements 1.
(Continued) b.
The instruments designated as Types A, B, and C and Categories 1 and 2 should be specifically identified on the control panels so that the operator can easily discern that they are intended for use under accident conditions.
DISTRICT'S POSITION:
Identification and marking is being addressed by NUREG-0737, Supplement 1, item I.D.I. (Control Room Design Review). Where appropriate, the instrumentation will be identified to improve operator interface.
2.
In addition to the above criteria, the following criteria should apply to Categories 1, 2 and 3:
a.
Servicing, testing and calibration programs should be specified to maintain the capability of the monitoring instrumentation.
For those instruments where the required interval between testing will be less than the normal time interval between generating station shut-downs, a capability for testing during power operation should be provided.
b.
Whenever means for removing channels from service are included in the design, the design should facilitate administrative control of the access to such removal means.
c.
The design should facilitate administrative control of the access to all setpoint adjustments, module cali-bration adjustments, and test points.
d.
The monitoring instrumentation design should minimize the development of conditions that would cause meters, annunciators, recorders, alarms, etc., to given anoma-lous indications potentially confusing to the operator.
Human factors analysis should be used in determining type and location of displays.
The instrumentation should be designed to facilitate e.
the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules, f.
To the extent practicable, monitoring instrumentation inputs should be from sensors that directly measure the desired variables. An indirect measurement should be made only when it can be shown by analysis to provide unambiguous information..
o D.
ADDITIONAL CRITERIA FOR CATEGORIES 1, 2, and 3 4
Reg. Guide Requirements 2.
(Continued) g.
To the extent practicable, the same instruments should be used for accident monitoring as are used for the normal operations of the plant to enable the operators to use, during accident situations, instruments with which they are most familiar. However, where the required range of monitoring instrumentation results in a loss of instrumentation sensitivity in the normal operating range, separate instruments should be used, h.
Periodic checking, testing, calibration, and calibra-tion verification should be in accordance with the applicable portions of Regulatory Guide 1.118.
"Per-iodic Testing of Electric Power and Protection Sys-tems," pertaining to testing of instrument channels.
(Note: Response time testing not usually needed.)
DISTRICT'S POSITION:
To the extent applicable, and as required by IEEE-279-1968 and-NUREG-0737, the above requirements are incorporated in the in-strumentation provided at Fort Calhoun. The additional criteria of Reg. Guide 1.97, Rev. 2, section 1.5 will be applied to any new instrumentation.
D.
ADDITIONAL CRITERIA FOR CATEGORIES 1, 2, and 3 Reg. Guide Requirements i
3.
Sections 6.2.2, 6.2.3, 6.2.4, 6.2.5, 6.2.6, 6.3.2, 6.3.3, 6.3.4 and 6.3.5 of ANS-4.5 pertain to variables and variable ranges for monitoring Types B and C variables.
In conjunc-tion with the above-listed sections of ANS-4.5, Tables 1 and 2 of this regulatory guide (which include those variables mentioned in these sections) should be considered as the minimum number of instruments and their respective ranges for accident-monitoring instrumentation for each nuclear power plant.
DISTRICT'S POSITION Exceptions are noted in Table 1..
l 3.0 METHODOLOGY FOR REVIEW
.3.1 Type A Variables l
The District reviewed Reg. Guide 1.97, Rev. 2 to evaluate whether the Fort Calhoun Accident Monitoring Instrumentation complied with the i
specified requirements. The District's first step in evaluation of the Reg. Guide was to identify all systems which could provide the i
variables which were defined in the Reg. Guide. All variable types were identified in the Reg. Guide with the exception of Type A vari-ables. These variables, according to the Reg. Guide, are plant specific and should meet the definition of Type A variables as noted j
in Section 2.2 of this response.
The District delineates Type A variables as those that are the plant specific variables, which provide the primary information required to permit the Control Room operator to take pre-planned manual action to accomplish safe shutdown for a DBA event. Variables associated with contingency actions are not included.
After review of the Combustion Engineering Emergency Procedures Guidelines, Rev. 2, (Ref. 7.3) the Type A list was developed. The l
Fort Calhoun Station designated Type A variables are:
Safety Functions FC Type "A" Variables I
Reactivity Control Neutron Flux i
I II RCS Inventory / Pressure Control Hot and Cold Leg Temper-atures III Core & RCS Heat Removal Subcooled Margin Monitor Core Exit Temperature RV Level Pressurizer Level Pressurizer Pressure S/G Level, S/G Pressure IV Containment Combustible Containment H Concentration 2
Gas Control V
Containment Radiation High-Range Containment Radiation Monitors This list is consistent with the ANSI /ANS 4.5(1980) recommendations which were the basis for the Reg. Guide 1.97 requirements.
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4.0
SUMMARY
OF DISTRICT'S REVIEW 4.1 After a thorough review of the Reg. Guide and tabulation of the data sheets, a brief sumary for each variable was tabulated. The result is the information as shown in Table 1.
The following information is found in Table 1:
1.
Reg. Guide 1.97 Category requirements or NUREG-0737 Specifications 2.
Instrument Range 3.
Environmental Qualification 4.
Seismic Qualification 5.
Quality Assurance 6.
Redundancy 7.
Power Supply 8.
Recording 9.
Location of Display 10.
Comments Data Sheets used for preparation of Table 1 are not included in this package but will be retained by the District as back up documen.ation.
l Table 1 identifies the Regulatory Guide requirements in the areas specified, as well as the District's position in meeting those speci-fications.
In those cases where the criteria is not met, a justi-i fication for non-compliance is provided or a commitment for component upgrade is made.
4.2 The instrument ranges and categories which were specified in Reg.
Guide 1.97, Rev. 2 were used unless Reg. Guide 1.97, Rev. 3 provided less stringent requirements. Table 1 footnotes specify those l
variables on which the District has referenced Reg. Guide 1.97, Rev. 3 instrument ranges or categories.
Where Table 1 references a range of 0-100% for various tank levals, this indication is referred to the actual instrument taps rather than i
full span of the tank. The District believes that this is a conserva-tive measurement and provides the control room operators with the necessary information.
4.3 For each variable listed in the Reg. Guide it is noted whether the District had existing instrumentation to provide the monitoring of the variable.
Identification tag numbers are listed beneath the variable.
The abbreviations shown in the table are defined as follows:
j Radwaste Panel AI-100 PostAccidentSamplingSystem(PASS) Panel AI-194 Aux. B1dg.-
Auxiliary Building Category from Reg. Guide 1.97, Rev.2 CAT.
Component Cooling Water CCW Containment Cont.
Core Exit Thermocouple CET System ContainmentSpray(Flow)
CSS Design Pressure I
DP(F)
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i 4.0
SUMMARY
OF DISTRICT'S POSITION 4.1 (Continued)
Control Room CR Emergency Diesel Generator EDG Emergency Operation Facility l d.
EOF Emergency Operating Procedures E0P Emergency Procedure EP Emergency Response Facility ERF Heated Junction Thermocouple HJTC High Pressure Safety Injection HPSI Heat Exchanger HX Low Pressure Safety Injection LPSI NPSH Net Positive Suction Head Not Required N/R Post Accident Sampling System PASS Quench Tank QT Reactor Coolant System RCS Regulatory Guide RG Reactor Vessel RV Shutdown Cooling Heat Exchanger SCHX Subcooled Margin Monitor SCMM Steam Generator S/G Safety Injection j
SI Safety Injection Refueling Water Tank i
SIRWT Safety Injection Tank SIT Safety Parameter Display System, (synonymous g
SPDS with plant computer)
Technical Specifications TS Updated Safety Analysis Report USAR 5.0 EXCEPTIONS TO REGULATORY GUIDE 1.97 REV. 2 AND STATUS UPDATE General Table 1 provides a comparison of the Reg. Guide requirements with the i
available instrumentation. This table also notes compliance or non-com-pliance in the Comment section of the Table. No further review was deemed necessary upon determination that the instrument loop was qualified to the appropriate category requirements. This section addresses those loops which were not determined to be in compliance with the areas governed by the Reg. Guide. A majority of these areas were determined to be acceptable based on further analysis. This consisted of analyzing the existing equipment functions and design bases. Areas where analysis indicated that the intent of the Reg. Guide was not met were considered for upgrading.
Equipment upgrade was identified in Table 1 and the actual design descrip-tion and upgrade schedule are discussed further in Section 6.0.
The following justifications are the District's basis for deviations from the Reg. Guide. The intent of the guideline, which is to provide monitoring systems in the accident situation, is met in all cases. The analyses have been segregated into sections covering the specific variable types.
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5.1 Type A Variables 5.1.1 Neutron Flux (CAT.1)
The function specified above is performed by instrument loops N-001,002,003,004 made up of the excore detectors located in containment, amplifiers located in the Auxiliary Building and Wide Range Log Channel Drawers located in the control room. Four source range monitors (SRM's) and four wide range instrument mnitors (IRM's) are provided for flux indication. All SRM and IRM detectors consist of dual fission chambers. The Excore detectors were replaced during the 1984 outage with fully qualified components. The detectors, amplifiers, and cable assemblies are qualified to Reg. Guide 1.89 and 1.100 and with the methodology described in NUREG-0588, CAT I.
However, the balance of the equipment such as the Wide Range Log Channel Drawers, which provide signal processing and indication for neutron flux, have not been upgraded and are in compliance with the requirements applicable at the time of issuance of the construction permit. The District believes the above deviations from the requirements are justified as discussed in Section 2.3.3.A.I of this report.
Summary Position - The District believes that the existing instrumentation loops for neutron flux measurement are adequate to perform the intended accident monitoring func-tion. Thus, no modifications are proposed.
5.1.2 Reactor Coolant System Pressure (CAT.1)
The function specified above is performed by pressurizer pressure instrument loops P-105/P-115 and by proposed loops P-120A and P1208 (scheduled to be installed during the 1987 refuelingoutage). These loops are in compliance with the g
requirements of Reg. Guide 1.97 Rev. 2 except as noted herein:
j This function is performed by P105/P115 pressure loops for the LOCA/MSLB bounded DBA events, and by P120A/P1208 pressure loops for the ATWS bounded Design Basis Events (DBE).
j _
l
e 5.1.2 Reactor Coolant System Pressure (CAT.1)
(Continued)
~
a Range e
L P105/P115 0 psia to 2500 psia
/
P120A/P1208 1900 psia to 2900 psia An analysis of the pressure transient for Fort Calhoun d
Station ATWS and assuming a Diverse Scram System (ATWS rule) reactor trip results in a peak pressure of 2600 psia. OPPD believes the range of 0 psia to 2900 psia is adequate for all DBE's.
Seismic Certain portions of the P105/P115 instrument loops have been upgraded to IEEE-344-1975. However, the entire loops are not qualified to IEEE-344-1975. The sensors are qualified.
Other components of the loop are qualified to the seismic requirements which were applied at the time the construction pennit was issued.
Instrument loops P120A and P1208 will be qualified to meet the requirements of IEEE344-1975.
b For further discussion with regard to seismic qualification, see Section 2.3.3.A.1.
Summary Position The proposed additions to address the ATWS rule will resolve b
the Reg. Guide 1.97 RCS pressure requirement, 5.1.3 Reactor Coolant System Hot and Cold leg Water Temperature, Subcooled Margin Monitoring (CAT.1)
Fort Calhoun Unit 1 is provided with redundant subcooled margin monitors which were designed and installed to the-requirements of Reg. Guide 1.97 Rev. 2.
The SPDS SMM's receive their inputs from the following temperature and pressure loops:
Hot Leg Temperature:
T112H A/B T122H A/B Cold Leg Temperature:
T112C A/B T122C A/B Pressurizer Pressure P-105 P-115 Note, subcooled margin indication is not provided above 2500 psia. The ATWS event (trip occurring via the Diverse Scram System) is a high pressure transient of brief duration, thus subcooling is of secondary concern.
Performance can be 8
monitored via the 1 cop RTDs, the CET's and P120A or P1208.
OPPD considers the instrumentation adequate.,
DISTRICT'S POSITION:
The SPDS performs two additional subcooled margin calculations. These additional calculations are based on representative Core Exit Thermocouple (CET) temperature, and upper head temperature as sensed by the reactor vessel level Heated Junction Thermocouple (HJTC) probes.
Both of the above mentioned temperature input (CET and HJTC)
/t loops are fully qualified to both 10 CFR 50.49 and Reg.
Guide 1.100. Their temperature ranges of 32-2300*F far exceed those required by the Reg. Guide for SMM temperature inputs.
All three calculations share the same pressure inputs (P-105 and P-115). These transmitters and loops are dis-cussed in Section 5.1.2.
SUMMARY
The District believes that adequate instrumentation is provided to perform the intended Accident Monitoring Function, and meets the requirements of Reg. Guide 1.97 Rev.
2.
5.1.4 Vessel Level Monitoring (CAT. I)
The function specified above is indirectly measured by the Reactor Vessel Level Monitoring System (loops Y-116A/B) comprised of the Heated Junction Thermocouples and the Safety Parameter Display System (SPDS). The displays are provided in the control room, TSC and E0F through the SPDS portion of the ERF computer.
These loops are in compliance with the requirements of Reg.
g Guide 1.97.
5.2 Type B Variables 5.2.1 Containment Isolation Valve Position (CAT.1)
Containment Isolation Valve Position is provided via the limit switches on the valves. These limit switches are environmentally qualified to 10 CFR 50.49 requirements.
As noted in Table 1, limit switches provided on the follow-ing valves are environmentally qualified to 10 CFR 50.49 (D0R Guidelines) but do not meet the Category I seismic requirements of Reg. Guide 1.97..
n,
5.2.1 Containment Isolation Valve Position (CAT.1)
(Continued)
Containment Isolation Valve Location PCV-742 F/H Aux. Bldg.
HCV-7468 Aux. Bldg.
HCV-425 B/D Aux. Bldg.
HCV-467 B/D Aux. Bldg.
HCV-204 Aux. Bldg.
HCV-206 Aux. Bldg.
HCV-13888/1387B Aux. Bldg.
HCV-1559A/1559B Aux. Bldg.
HCV-1550A/15608 Aux. Bldg.
HCV-2603A/2603B Aux. Bldg.
HCV-2983 Aux. Bldg.
HCV-400C/401C/402C/403C Aux. Bldg.
HCV-438 B/D Aux. Bldg.
I HCV-500 A/B Aux. Bldg.
HCV-506 A/B Aux. Bldg.
HCV-507 A/B Aux. Bldg.
HCV-508 A/B Aux. Bldg.
HCV-509 A/B Aux. Bldg.
HCV-1395, 1386 Aux. Bldg.
HCV-1749 PCV-1849 Aux. Bldg.
?
DISTRICT'S POSITION The above listed limit switches were seismically designed to the requirements applicable at the time of issuance of the construction permit. The justification for not upgrading the seismic qualification of these limit switches is pro-vided in Section 2.3.3.A.I.
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5.2.1 Containment Isolation Valve Position (CAT.1)
(Continued)
Summary Position The District believes that valve position indication pro-vided by the existing limit switches is adequate. Thus, no modifications are proposed.
5.3 Type C Variables No exceptions taken.
5.4 Type "0" Variables 5.4.1 Accumulator Tank Level and Pressure The four (4) Safety Injection Tanks (Accumulators) are passive devices which discharge into the Reactor Coolant System (RCS) in the event of a Loss of Coolant Accident and certain of the Uncontrolled Heat Extraction (steam line break) events.
It remains the District's position that environmentally qualified instrumentation is not required on the Safety Injection (SI) tanks.
For the design basis accidents discussed in the USAR the addition of the SI Tank level and pressure provides little, if any, information in establishing the status of the core, the RCS, or the containment.
The goal of the Emergency Core Cooling System (ECCS) is to maintain the core in a cooled, covered, and subcritical condition. The SI Tanks provide a readily available source of borated water available without any active (pump start, fj remotely operated valve opening, etc.) equipment function.
The SI Tank isolation valves are open and their motor operator's power source is switched off. Two check valves are forced open by the SI Tank's over pressure (a minimum of 240 psig) and discharge directly into the cold legs of the RCS.
Based on the above description the following discussions are provided to support the District's position:
1.
Instrumentation provided for operator intervention The SI Tank discharge to the RCS requires only that two check valves open. The only remote operated valve is open and deenergized. There is no action that can be taken by the operator.
In addition, the SI Tanks discharge at a time into the event where operator action is not assumed or credited. Automatic action must mitigate the event.
5.4.1 Accumulator Tank Level and Pressure (Continued) 2.
Overpressurization of the SI Tanks Following a DBA This is not considered a credible event.
If the check valves between each of the SI Tanks and the Low Pressure Safety Injection System (LPSI) were to fail the LPSI system would pressurize the tank to approximately 195 psig which is less than the tank relief valve pressure set point of 275 psig. The LPSI system remains functional.
Two check valve failures would be required to result in RCS pressure on the tank. This is not considered to be a credible event.
3.
Indicator of ECCS Performance / Core Cooling The SI Tank instrumentation would provide no useful information in any long term core status and at best shows that the tanks did supply some cooling water to the RCS. Given the passive nature of the SI Tanks' function this can be surmised from RCS pressure. Exact volume is unneeded.
Core cooling and inventory are confirmed by direct verification for the RCS hot and cold leg by RTD's, the Core Exit Thermocouples, and Reactor Vessel Level t$L Monitor. These provide evidence of proper ECCS function. No information could be inferred about the core by using SI Tank information than can not already be derived by several other available variables.
4.
Loss of an SI Tank at the Time of DBA There is no action an operator can take to correct this problem should it occur.
Instrumentation will be operable up to the time of a DBA insuring accumulator inventory to mitigate a DBA.
If failure were to occur at the time of the DBA, all resources available to the operator are automatically started as part of the system response to the DBA. On line failures are governed by the Technical Specifications.
Instrument qualification will not increase SI Tank reliability.
Based on these four discussion regarding the function, accident diagnosis, failure and reliability, it is OPPD's position that these variables (SI Tank Pressure and Level) are not required for safe shutdown.
5.4.2 Safety Injection Tank Pressure (CAT.2)
See 5.4.1 discussion.
l.
5.4.3 Quench Tank (QT) Pressure (CAT. 3)
The function specified above is performed by the QT pressure instrument loop, (I.D. No. P-131).
b The quench tank pressure loop is in compliance with the requirements of Reg. Guide 1.97 except as noted below:
Range:
Reg. Guide 1.97, Rev. 2 specifies that quench tank pressure measurement should be 0 psig to design pressure.
The design pressure of the Fort Calhoun Quench Tank is 100 psig. The existing range on the pressure transmitters is 0-25 psig.
Summary Position Additional indication will be added consistent with Reg.
Guide 1.97 requirements. The proposed modification is discussed further in Section 6.2.1.
5.4.4 Quench Tank Temperature (CAT. 3)
The function specified above is performed by the Quench Tank temperature instrument loop (I.D. No. T-133).
This loop is in compliance with the requirements of Reg.
Guide 1.97 except as noted beluw:
Range: The temperature sensor is a 200 ohm dual-element, platinum RTD. One element of this RTD is input directly into a panel indicating meter, TI-133. This indicator is calibrated for a range of 0-300 F.
The second element of the RTD is input directly into the SPDS computer. The SPDS will indicate temperature over the entire range of the 200 b
ohm RTD. This range encompasses the specified 50-750 F range of Reg. Guide 1.97, Rev. 2.
Summary Position The District believes that the ranges described above are sufficient to cover all postulated conditions for the Quench Tank.
5.4.5 Containment Atmosphere Temperature (CAT.2)
A review of the location of T-714, 716, 718, and 720 indicates that these sensors cannot provide an accurate g
representation of containment temperature. The District plans to install a multi-sensor temperature measuring system in containment which meets category 2 requirements..
5.4.5 Containment Atmosphere Temperature (CAT.2)
(Continued)
Environmental Oualification: The Reg. Guide 1.97, Rev. 2 specifies that the instrument loops are to be environmental-ly qualified to IEEE-323-1974.
Summary Position The District will install environmentally qualified loops in
/j, accordance with 10 CFR 50.49. See Section 6.2.3 for schedule.
5.4.6 Radioactive Gas Decay Tank Pressure (CAT. 3)
The function of measuring the specified variable is to monitor the storage volume of the Radwaste System.
The function specified above is performed by instrument loops (I.D. No. P-517,518,519,520) located on the Radioactive Gas Decay Tanks in the Auxiliary Building.
These loops are in compliance with the requirements of Reg.
Guide 1.97 except as noted below:
Range: Reg. Guide 1.97, Rev. 2 requires that, for Decay Tank, monitoring an instrument range of 0-150% of the tank's design pressure should be provided. The existing range for the Decay Tanks sensors is 0-100% of the tank's design pressure. The tank's design pressure is 150 psig.
DISTRICT'S POSITION The District will upgrade the range to 0-150% of the tank's design pressure.
Summary Position The existing instrumentation loops, after upgrading, will be adequate to perform the intended Accident Monitoring Func-tion. See Section 6.2.2 for schedule of modification.
5.4.7 RCS Letdown Flow (CAT.2)
The variable listed above is to provide operator information with the status of RC letdown flow.
The function specified above is performed during normal operation by the Letdown flow transmitter loop (F-212).
DISTRICT'S POSITION:
During an accident situation the letdown system is isolated, and thus readout of letdown flow would be meaningless.
Thus this parameter is not required for accident monitoring..
5.4.7 RCS Letdown Flow (CAT.2)
(Continued)
Id Summary Position No upgrades are proposed for this instrumentation loop.
5.4.8 Volume Control Tank Level (CAT.2) lb The variable listed above is to provide operator information with the status of the VCT level.
The function specified above is performed during normal operation only by the VCT level transmitter loop (L-219).
DISTRICT'S POSITION:
Upon SIAS the Safety Injection Pumps take suction from the SIRWT and inject borated water at refueling boron concentra-tion into the reactor coolant system, to increase shutdown margin. The Volume Control Tank portion of the Chemical Volume and Control System is bypassed during this emergency infection mode. Thus monitoring of the VCT level for injection purposes would be meaningless. This instrument loop is not required for achieving safe shutdown or for performing accident monitoring.
Summary Position Thus, the District will not upgrade the currently installed level transmitters to meet the 50.49 ruling.
5.4.9 Residual Heat Removal lA The Fort Calhoun Station Residual Heat Removal (RHR) is accomplished in a post-accident situation by either the steam generators and shutdown coding or the Long Term Core Cooling System and shutdown cooling depending on the type of Design Basis Event being considered.
The Steam Generators (defined as intact generator, Auxiliary Feedwater, and Main Steam Power Operated Safety Valves) are used to cool down for all DBE's including the class of LOCA (breach of the the RCS) in which the primary system remcins above 700 psia.
Long Term Core Cooling (defined as HPSI, pressurizer auxiliary spray, HPSI-CVCS inter-connection, and SDCHX to HPSI suction flow) provides both hot and cold leg injection to prevent boron precipitation. This system is used when the RCS is below 700 psia..
5.4.9 Residual Heat Removal (Continued)
Shutdown cooling is defined as RCS hot leg to LPSI suction, LPSI system, and SDCHX including spray isolation and LPSI-Containment Spray cross-connect. This system may be used below 265 psia, 300 F.
Please note that for the RCS breach resulting in pressures above 700 psia the use of the PORV's as a flow path if both steam generators are not available is used. This is con-sidered a backup. The District believes that the perfor-mance of RHR can be monitored by the use of the CET's and Vessel Level Monitoring previously discussed (Category 1 items).
The District believes that for RHR monitoring the following variables insure operator information of system performance:
Steam Generators SG Pressure SG Level AFW Flow Main Steam Safety Position Indication LTCC HPSI Flow Charging Flow Aux Spray Valve Position SD Cooling LPSI Flow Cont Isol Viv on RCS Position Indication SDC Flow
- SDCHX Outlet Temp.*
RCS Information RCS Pressure RCS Hot Leg Temp.
RCS Cold Leg Temp.
CET HJTC - Vessel Levei
- Require Upgrade DISTRICT'S POSITION The District will upgrade the two noted items as described in 6.2.4 and 6.2.5.
1 30-c.
.__y._
5.4.10 Component Cooling Water Temperature to Engineered Safety Features (ESF) System Fort Calhoun has presently installed one RTD instrument loop on each of the four (4) component cooling / raw water heat exchanger outlets. These are installed in a. mild environment and meet the original plant design requirements which OPPD interprets as equivalent to Category 2.
These process signals are not recorded. Each of the temperature channels is equipped with a high temperature alarm set at 120 F.
The instruments' calibrated span is 0 F to 300 F.
Core and containment cooling are the central issues with respect to the Component Cooling Water (CCW) system function. Cooling malfunctions can be diagnosed using direct, i.e. RCS temperature indication. The existing CCW heat exchanger outlet temperature can then be consulted to aid in determining if a CCW malfunction has occurred.
l It is the District's position that these four temperature channels in their present configuration provide adequate system performance information and is of adequate resolution to determine proper system function.
/[
No change to this existing instrumentation is believed to be required.
5.4.11 Component Cooling Water Flow to ESF System It is the District's position that adequate instrumentation is presently installed to monitor the performance of the Component Cooling Water (CCW) system.
CCW pump motor current, which is proportional to flow, can be monitored on each of three CCU pump motors.
In addition, low CCW flow out of each of the containment air cooling units provides alarmed indication of CCW system failure.
All the previously discussed CCW system monitoring instruments presently meet Category 2 requirements.
5.5 Type E Variables No exceptions taken.
5.5.1 Wind Direction, Wind Speed Atmospheric Stability Calibration and instrument uncertainties for meteorology variables will be redefined to comply with Regulatory Guide 1.97 accuracy requirements..
6.0 DESIGN DESCRIPTION AND SCHEDULE FOR IMPLEMENTATION OF IDENTIFIED UPGRADES 6.1 Type A Variables 6.1.1 RCS Hot Leg Temperature Complete.
6.1.2 RCS Cold Leg Temperature I A.
Complete.
6.1.3 Reactor Vessel Level Monitoring Ib Complete SER not issued.
6.1.4 RCS Pressure The high range pressure transmitters will be installed d
during the 1987 refueling outage.
6.2 Type D Variables 6.2.1 Quench Tank Pressure The existing equipment does not meet the Reg. Guide 1.97 range requirement of 0 to design pressure.
In order to be s
in compliance a new instrument loop will be installed with
/L an increased range of measurement. The installation will meet Category 3 requirements.
The loop will be modified during the 1987 refueling outage, to provide the required range.
6.2.2 Radioactive Gas Decay Tank Pressure The pressure transmitter ranges on the radioactive gas decay tanks will be broadened from 0-100% of the design pressure to 0-150% design pressure. This modification will be performed during or before the 1987 refueling outage.
6.2.3 Containment Atmosphere Temperature
(
Temperature channels will be added, which meet the require-g ments of Category 2.
This will be completed during the 1987 refueling outage.
6.2.4 Shutdown Cooling Flow The transmitter for Shutdown Cooling Flow will be replaced with an environmentally qualified component. This modifi-cation will be performed during the 1987 refueling outage.
l l.
6.2.5 Shutdown Cooling Heat Exchanger Outlet Temperature The RTDs for Shutdown cooling heat exchanger outlet temperature (T-339, 340) will be replaced with environ-mentally qualified components. This modification will be performed during the 1987 refueling outage.
6.2.6 Containment Sump Temperature A Category 2 temperature loop will be added during the 1988 d
refueling outage.
6.3 Type E Variables 6.3.1 Calibration will be redefined and implemented during the f
first biannual calibration during the spring of 1987.
7.0 REFERENCED DOCUMENTS 7.1 Supplement I to NUREG-0737 Requirements For Emergency Response Facilities (Generic Letter No. 82-33) 7.2 Letter from OPPD (W.C. Jones) to NRC (R.A. Clark) dated April 15, 1983 (LIC-83-093).
7.3 Combustion Engineering Emergency Procedures Guidelines, Rev. 2.
7.4 Fort Calhoun Emergency Procedures 7.5 Fort Calhoun System Descriptions 7.6 Fort Calhoun Critical Quality Element List 7.7 Fort Calhoun Electrical Equipment Qualification Report (10 CFR 50.49, Generic Letter 82-09).
7.8 Regulatory Guide 1.97, Rev. 2 and Rev. 3.
7.9 Fort Calhoun Station Unit No. 1 Updated Safety Analysis Report (USAR) 7.10 Fort Calhoun Station AMI Status Sheets; GSE - Nuclear Engineering Study 84-07.
7.11 Letter from OPPD (R. L. Andrews) to NRC (d. R. Miller) dated September 28, 1984 (LIC-84-323).
~
TABLE 1 COMPARISON OF 70PT CA!JiDUN STATION tMIT NO. I snozemw. ATION WITH PEGUIMOPT GUIDE 1.97 REY. 2 Rewicm w d TYPE *A' VARIAPLIS
,0NER i ma 4 m-w i gg RANGE Dff QUAL.
SEIS QUAL.
PfDUND.
SUPPLT RECORDING DISPLAY IACATION CfW9ffWrS 1
PEACTIVITY CONTROL
-6
- 1. Neutron Flux R.G.
1 10,,bM W.1 R.G. 1. M WW IE W red h G an M M e In complim v12 (NT-Col, 002, OPIC 1
USAR 10 4-125%
10CTR50.49 IEEE-344-75**
TIS IE SPDS CR, SIOS exceptions noted in Section 5.1.1 C03, 004) 11 FCS INVFW! ORT /PPESSURE CONTROL
- 1. Prasouriser Level R.G.
1 0-100%
CAT.1 R.G. 1.100 REQUIRED IE Required One Charmel Continuous (LT-1011/Y)
OPID 1
USAR 0-100%
10CTR50.49 IEEE-344-75+
YES 1E Recorded CR, SPDS In Compliance
- 2. ICS Pressure R.G.
1 0- psig CAT.1 R.G. 1.100 REQUIRED IE pequired One Channel Continuous (PT-105, 115)
OPID 0737 0737 0-2500 psig 10CTR50.49 IEEE-344-75*
YIS 1E Recorded CR, SIOS See Section 5.1.2 (PT-120A, PT-1205) 1 0737 1900-2900 psig 10CTR50.49 IEEE-344-1975 YES IE SPDS CR, SIM See Section 6.1.4
- 3. Degrees of Subcooling R.G.
1 200*F to 35'T CAT.1 R.G. 1.100 REQUIPID 1E Required One Channel Continuous In Compliance (SIOS)
OPPD 0737 0737 618'r subcooled 10CTR50.49 IEEE-344-75 YES 1E SIOS CR, SFDS See Section 5.1.3 g
to 668'F superheated C/R-Not required.
+ - The entire loop is not qualified to IEEE-344-1975, only portions, including the sensors are qualifted.
e. The transmitters located in the harsh environment were replaced per 10CTR50.49. The new transmitters are quellfled per IEEE344-1975 and 10CTR50.49. All other components of the loop are qualified per the seismic requirements which applied at the time the construction permit was issued. (Reference Appendix F of the USAR).
ee. The entire loop is not qualified to IEEE-344-1975, only the encore detectors and amplifiers are qualtfled. The balance of equigment is qualifted to original seismic qualification.
- QA requirements for categories 1,2, and 3 are shown in Section 2.3.3.A.S.
R.G. - Regulatory Guide 1.97, Rev. 2 requirements.
1-Rev. 1 Date 10/2/96
TABLE 1 Ct1MPARI90N OF FORT CALHOUN STAffte 1987T SF). I areiru.,rm ATI(W N111f RIX77LATORT GIDE 1.97 hEV. 2 RFOUTRDENTS TYPE 'A" VARI DI,ES PONER INSTRUMDff gg RANGE DfV QUAL.
SETS QUAL.
RfDUND.
SUPPLY RECORDING DISPEAT IDCATION CC#WGNTS III CORE & PCS HEAT RD10 VAL
- 1. Cold Leg R.G.
1 50-700*F**
CAT.1 R.G. 1.100 REQUIRED IE Required One Channel Continuous See 5.1.3 d
Temperature OPPD 0737 0737 50-700*F 10CFR50.49 IEEE-344-75 TES IE SPDS SPDS b
50*F-700*F**
CAT.1 R.G. 1.100 REQUIRED 1E Required one Channel Continuous See 5.1.3
- 2. flot lag R.G.
1 Temperature OPPD 0737 0737 50*F-700'F 10CFR50.49 IEEE-344-75 YES IE SPDS SPDS 200-1650*F CAT.1 R.G. 1.100 REQUIRID 1E Required One Channel Continuous See Ref. 7.11
- 3. Cors Exit R.G.
1 Temperature
. OPfD 0737 0737 32-2300*T 10CFR50.49 IEEE-344-75 YES, 7 per quad.
IE SPDS STOS In Compliance RC-7D (1-28) 200*F to 35'r CAT.1 R.G. 1.100 REQUIRED IE Required One Channel Continuous
- 4. Degrees of R.G.
1 Subcooling CPPD See Type A variables, Item III.3 y
r e - The entire loop is not qualified to IEEE-344-1975, only the sensors are qualifted.
- QA requirements for categories 1,2 and 3 are shown in Section 2.3.3.A.5 e. Proposed range
- - Reg. Guide 1.97, Rev. 3 Rev. 1 Date 10/2/96
.m l
T MLE I Ct*PARTSfW OF PORT CAf>4AM STAffolf TWIT NO.1 INSTRTMENTATION NfDf REGUIATORY GUIDE 1.97 REV. 2 RECCIRFMDrfS t
TYPE *A" VARIABLES PONER C
RANGE DrV OtfAL.
SEfS QUAL.
RfDUND.
SUPPLY Rfr0RDING DISPEAY TACATION C0pOfDffS 3g INSTRfMDrr III fDRE & RCS ffEAT RDIOVAL (Continued)
- 5. RV !avel R.G.
1 Bottoe of Hot
- CAT.1 R.G. 1.100 REQUIRED IE REQUIRED One Channel Continuous In Compliance (Y-116A/B) tag to top of f
Vessel OPPD 0737 0737 Top of Core 10CFR50.49 IEEE-344-75 YES IE SPDS SIOS to top of l
Vessel
- 6. S/G tavel R.G.
1 Tube Sheet to CAT.1 R.G. 1.100 REQUIRED 1E REQUIRED One Channel Continuous (LT-911 A/B)
Separator (LT-912 A/B)
OPIO 0737 0737 Tube Sheet to 10CFR50.49 IEEE-344-75 YES 1E SPDS SPDS, CR In Compliance Separator (0-100%)
ATM to 20%
CAT.1 R.G. 1.100 REQUIRED IE REQUIRED One Channel Continuous
- 7. S/G Pressure R.G.
1 (IT-913 A/B) above lowest (PT-914 A/B) safety valve setting.
OPPD 0737 0737 ATM to 20%
10Cf750.49 IEEE-344-75 TIS 1E SPDS CR, SICS In Compliance 0-1200 psia
- - Peg. Guide 1.97 Rev. 3 requirement.
- DA requirements for categories 1,2 and 3 are shown in Section 2.3.3.A.5 Rev. 1 nate In/2/M
TABLE 1 (TelPARISON OF P03rf CAtE0tM STATION IDi!T NO. I filSTRONDrrATION WITH Rff;UTA10RT GUIDE 1.97 REV. 2 FEQUIRDtE3ffS TYPE "A" VARIABLES PONER im rv.,-.
C RANGE DIV QtfAL.
SEIS QUAL.
RIDUIO.
SUPPLY RECORDING DISPtAY IKATION CODBEENTS 3g IV CONTAID5tDfT COMRUSTIBLE GAS CONTML
- 1. Containment R.G.
1 0-104 CAT.1 R.G. 1.100 REQUIRfD 1E Required One Channel Continuous R Concentration OPIO 0737 0737 0-10%
10CTR50.49 IEEE-344-75 YES 1E Recorded SPDS, CR, In Compliance (VA-81A/B)
V CoertAinstDrr RADIAT!rw
~7
- 1. Containment High R.G.
1 1.10 R/HR CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous
~7 Range Radiation 1.10 R 11R
~7 (RM-091A,101-0918)
OPID 0737 0737 1.10 R/HR 10 CFR 50.49 IEEE-344-75 YES 1E Recorded G, SPDS In Compliance s
- QA requirements for categories 1,2 and 3 are shown in Section 2.3.3.A.5 I
l l Rev. I n.,.
,nister
1 TABLE 1 CONPApfSON OP PORT CALHOUN STATTCBf UNIT W.1 INSTRISTENTATirW NITH PEGUTATORY GUIDE 1.97 REY. 2 FFOUIPDENTS TYPE 4 " VARfARLES POWER INSTPtDfENT CA RANGE INV CUAL.
SEIS CUAL.
RfDtMD.
SUPPLY REtISDING DISFTAT IDCATION COPWENTS Jg I REACTIVITY CONTROL
- 1. Neutron Plux R.G.
1 10 4-100%
CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous OPID See Type A Variables, Item 1.1
- 2. Control Rod R.G.
3 Pull in or Not N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand Posittee Highly Reliable (CIEC 's)
OPPD 3
USAR Pull in or Not CR, SIDS In Compliance
- 3. IICS Soliele Boron R.G.
3 0-6000 ppu N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required On Demand Concentration (SL-251 OPID 0737 0737 0-6000 ppe Backup by Rarorded Chart Recorder In Compliance Grab Sample See Note 1
- 4. IICS Cold Leg R.G.
3 50-400*P N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required on Demand N;tir Temperature (TT-113 OPID 3
USAR O-600*P 1E Recorded CR, SPDS In Compliance TT-123)
It g C0nLING
- 1. RCS Hot leg Temp.
R.G.
1 50-700'F**
CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous OPID See Type A variables, Item !!!.2 Nota 1 - The PASS lon chromatograph w!!! Le used as the primary boron concentration measurement for accident monitoring in lieu of the boronneter. The ton chromatograph was design.d to NUREG-0737 requirements and can measure RC, LFSI and contairment sump samples.
- 04 requirements for categories 1,2 and 3, Section 2.3.3.A.5 N/R - Not Pequired
- - Reg. Guide 1.97, Rev. 3 E.S.P. = No Specific Provision 4 88'. I Date 10/2/96
TABLE 1 C0IEPARTSON OF FORT CALHnUN STATION INTT W. I avowunwi ATICM WITH REGUTAFRT CUIDE 1.97 Rfv. 2 RECUTRDIDrTS TYPE "B" VARIABLIS POWER CA RANGE BfV QUAL.
SE!S QUAL.
RfDUND.
SUPPLT RIEORDING DISP!AT 12CAff0N Cop 0'DffS Jg INSTPUNENT 11 COPE COOLING (Continued)
- 2. 3CS Cold Ing Temp.
R.G.
1 50-700*F**
CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous OPID See Type A Variables, item Ilf.1 i
- 3. RCS Pressure R.G.
1 0-4000 psig CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous OP19 See Type A Variables, item 17.2
- 4. CET R.G.
3 200-1650*F N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required on Deand OPID See Type A Variables Item III.3
- 5. DV !svel R.G.
1 Btm of Hot tag ** CAT.1 R.C. 1.100 REQUIRED IE N/R One Channel Continuous Nonttoring to top of Vessel OPPD See Type A variables, Item III.5 O. Degrees of R.G.
2 200*F - -35'r CAT.2 N.S.P.
N.S.P.
Highly Reliable Required on D e and
- Subcoeffng 0FFD See Type A Variables, item II.3 co - Reg. Guide 1.97, Rev. 3.
- QA requirements categories 1,2 and 3 shown in Section 2.3.3.A.5 N/R - Not Required N.S.P. o No Specific Provision
. R*V. I Date 10/2/R6
l TATTLE 1 COMPARISON OF FORT CALHnm STATION WIT NO. I arr.>trursuv1 ATION WITH RETTIATORT GUIDE 1.97 REY. 2 REQUIRDitNTS TYPE "B" VARIABLES POWER CA RANGE Div QUAL.
SEIS OUAL.
REDOND.
SUPPLY RfC011 DING DISPtAY ff1CATf0N COMEDfTS l
INSTRUMDIT Jg
!!! MfNTAINING PEACTOR l
CootAFP SYSTDI INTECRITY 1
- 1. RCS Pressure R.G.
1 0-4000 psig CAT.1 R.G. 1.100 REQUIRID 1E Required One Channel Continuous CPPD See Type A Variables, Item it.2 l
Sump, (0-32")
CAT.2 N.S.P.
N.S.P.
Highly Reliable Required on Demand 2;. Containment Sump R.G.
2 Natar Level OPPD 0737 0737 5 - 37 in.
10CFR50.49 IEEE-344-75 YES 1E Recorded CR, SiOS In Compliance l
(Narrow)
(LT-599, 600) j 0-600,000 Gal.
CAT.1 R.G. 1.100 REQUIRID 1E Required One Channel Continuous 2b. Containment Stamp R.G.
1 Nattr Level (N1de)
OPfD 0737 0737 0-600,000 Gal.
10CFR50.49 IEEE-344-75 YES 1E Recorded CR, SPDS In Compliance (LT-387 A/B/C/D (0-27.5 ft.)
LT-388 A/B/C/DI
- 3. Contrinment R.G.
1 0-D.P.
CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous in Ccap11ance Pressure OPIO 1
USAR 195 psig 10C71t50.49 IEEE-344-75+
YES IE Recorded CR, SICS (PT-783, 784)
TV MTNTAINING CONTAINMDrr IFTE'GRITY 1.
Containment R.G.
1 C1so/Not C1sd CAT.1 R.G. 1.100 REQUIRED 1E N/R on Demand See Section 5.2.1 Isolation Valve See list belows those Containment Isolation Valves which close upon Position receipt of CIAS (" Containment Isolation Actuation Signal")
e - the entire loop is not qualtfled to IEEE-344-1975, only the sensors are qua!!fied.
- OA requirements categories 1,2 and 3 shown in Section 2.3.3.A.5 N/R - Not Required N.S.F. = No Specific Provision Rev. I pate In/7/M
e TABLE 1 COMPARISON OF FORT CAIROUN STATION 11 NIT NO.1 TNSTRUNINTATION WITH RIUUIAT0kY GUIDE I.97 REV. 2 REgtITRDIENTS TYPE *B" VARIABLES PONER INSTRL'NINT CJA g RANGE DV CUAL.
SETS QUAL.
RfDUND.
SUPPLY RfEURDING DISPIAY ffCATION COMEDfTS JV NAINTAINING CONTAINMDrf INTEGRITY (Continued)
A.
PCV-742 A/C/E/G 1
USAR Cisd/Not C1sd 10CTR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS In Compliance B.
PCV-742 B/D 1
USAR C1so/Not Cisd 10CTR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS In Compliance C.
PCV-742 F/H 1
USAR C1sd/Not Cisd 10CFR50.49 Original Plant YES*
IE N/R CR, S106 See 5.2.1 D.
HCV-746 A 1
USAR Cisd/Not C1sd 10CFR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS in Compliance E.
HCV-746 B 1
USAR C1sd/Not Cisd 10CFR50.49 Original Plant YES*
e T.
HCV-425 A/C 1
USAR C1sd/Not C1sd 10CFR50.49 IEEE-344-75 YES*
IE N/R CR, SIOS In Compliance I
G.
HCV-425 B/D 1
USAR C1sd/Not C1sd 10CTR50.49 Original Plant YES*
H.
HCV-467 A/C 1
USAR Cisd/Not C1sd 10CFR50.49 IEEE-344-75 YES*
- - With the exception of those penetrations which are exempt from the requirement of double isolation (Ref. USAR Section 5.9.51 all mechanical penetrations are provided with two isolation valves E/R - Not Required
! Rev. I n...
w r, rer
TABLE 1 COMPARISDN OF FORT CAIJWMW STATION IMIT NO.1 INSTMNDrfATION NTTH REGU!ATORY GUIDE 1.97 REV. 2 REQUIRDIPNFS TYPE "B" VARIABLES POWER IW3TRUNDfT gg RANGE DfV QUAL.
SETS QUAL.
RIDUND.
SilPPLY DITORDING DISPTAY IDCATION CGetDrfs IV MAINTAINING CONTA!!GtDf7 trtEGRITY (Continued) 1.
HCV-467 B/D 1
USAR Cisd/Not C1sd 10CTR50.49 Original Plant YES*
IE N/R CR, SPES See 5.2.1 J.
NCV-500 A/B 1
USAR C1sd/Not C1sd 10CFR50.49 Original Plant YES*
HCV-506 A/B 1
USAR Cisd/Not C1sd 10CTR50.49 Original Plant YES*
HCV-507 A/B 1
USAR C1sd/Not C1sd 10CFR50.49 Original Plant YES*
HCV-508 A/B 1
USAR s C1sd/Not Cisd 10CFR50.49 Original Plant YES*
HCV-509 A/B 1
USAR C1sd/Not Cisd 10CFR50.49 Original Plant YES*
TCV-202 1
USAR C1sd/Not Cisd 10CFR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS In Compliance P.
IICV-204 1
USAR Cisd/Not C1sd 10CFR50.49 Original Plant YES*
HCV-241 1
USAR C1sd/Not Cisd 10Cf1t50.49 IEEE-344-75 YES*
- - Nith the exception of those penetrations which are exempt f rom the requirement of double isolation (Ref. USAR Section 5.9.51 all mechanical penetrations are provided with two isolation valves d
N/R = Not Required q
9-Rev. 1 No. WS/su:
~.
i 1
i TABLE 1 COMPARISON OF PORT CALH0tM STATION tMIT to.1 INSTptMDFTATION WITH RE0titATORY GUIDE 1.97 REV. 2 REQUIRDENTS j
TYPE "B" VARIABLES 1
POWER CA RANGE DN QUAL.
SEfS QUAL.
- REDtMD, SUPPLY RELTSDING DISPtAY t/1 CATION C0pSENTS 1
INSTRUNDfY Jg IV NAttrfAINING CONTAINF*.]
INTYERTTY (Continueo)
R.
HCV-206 1
USAR Cisd/Not Cisd 10CFR50.49 Original Plant YES*
HCV-1387A, 1388A 1
USAR C1sd/Not Cisd 10CTR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS In Compliance i
t T.
HCV-1387B,13888 1
USAR Cisd/Not C1sd 10CFR50.49 Original Plant YES*
HCV-1385, 1386, 1
USAR C1sd/Not C1sd 10CFR50.49 Original Plant N0*
IE N/R CR, SPDS See 5.2.1 HCV-1749, PCV-1849 V.
HCV-1559 A/B 1
USAR s Closed /Open 10Cf1t50.49 Original Plant YES*
IE N/R CR, SPDS See 5.2.1 HCV-1560 A/B
- 15. HCV-2603A, 2604A 1
USAR Closed /Open 10CFR50.49 Original Plant YES*
HCV-2603B, 2604B 1
USAR Closed /Open 10CFR50.49 IEEE-344-75 YES*
1E N/R CR, SPDS In Compliance Y.
HCV-2504A, 2506A 1
USAR Closed /Open 10CTR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS In Compliance HCV-2507A 3.
HCV-2504B, 2506B 1
USAR Closed /Open 10CTR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS In Compliance HCV-2507B
- - Nith the exception of those penetrations which are exempt from the requirement of double isolation (Ref. USAR Section 5.9.5) all mechanical penetrations are provided with two isolation valves N/R - Not Required Rev. 1 Date 10/1/nr.
i j
TABLE 1 COMPARISON OF FORT CAIJ100N STATION tMIT 90.1 4
INSTRIBID8TATION NITH REWIA10RY CUIDE 1.97 REV. 2 REQUIRDIDrr$
TYPE "B" VARIABLES POND j
INSTRUNDff gg RANGE DfV QUAL.
SEIS QUAL.
REDtlND.
SUPPLY Rfr0RDING DISPtAY IACATION C0fGEDirS IV NA!NTAINING CONTAIDStDrr INTEGRITY (Continued)
AA. HCV-820A, 821A 1
USAR Closed /Open 10CTR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS in Compliance BB. HCV-820B, 8218 1
USAR Closed /Open 10CFR50.49 IEEE-344-75 YES*
1E N/R CR, SPDS In Compliance CC. HCV-881, 882 1
USAR Closad/Open 10CTR50.49 IEEE-344-75 N0*
IE N/R CR, SPDS In Compliance DD. HCV-4004/B/D 1
USAR Closed /Open 10CFR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS In Compliance HCV-401A/B/D HCV-402A/B/D HCV-403A/B/D s
i EE. HCV-400C 1
USAR Closed /Open 10CFR50.49 Original YES*
IE N/R CR, SIM See 5.2.1 HCV-401C Plant HCV-402C HCV-403C FF. HCV-438 A/C 1
USAR Closed /Open 10CFR50.49 IEEE-344-75 YES*
IE N/R CR, SPDS In Compliance CG. HCV-438 B/D 1
USAR Closed /Open 10CTR50.49 Original Plant YES*
IE N/R CR, SIOS See 5.2.1 1
e - Nith the exception of those penettstions which are except from the requirement of double isolation (Ref. USAR Sect. 5.9.51 all mechanical penetrations are provided with redundant 1
1 solation valves N/R - Not Required
" Rev.1 p.o. mis m
e.
4 4
TABLE 1 CONPARISON OF FORT cat.HDUN STATION TWIT NO.1 TMSTRtMDFTATIfW NITM RFGtTIATORT GUIDE 1.97 REY. 2 REQUIRDENTS TYPE *B" VARIABLES PONDt CA RANCE Div CUAL.
SEIS CITAL.
RfDOND.
SUPPLY PEDDRDfMG DISPfAY ti1 CATION C009ENTS INSTRUNENT Jg IV ISINTAINING CQfTAIIGG3ff INTErRITY (Continued)
Mif. MCV-883A 1
USAR Closed /Open 10CFR$0.49 IEEE-344-75 YES*
IE N/R CR, SIOS In Compliance MCV-884A II. C V-8838 1
USAR Closed /Open 10CFR50.49 IEEE-344-75 YES*
IE N/R CR, S106 In Compliance MCV-8848 JJ. MCV-1107A 1
USAR Closed /Open 10CFR50.49 IEEE-344-75 YES*
It N/R CR, STOS In Compliance C V-1108A IEE. C V-11078 1
USAR Closed /Open 10CFR50.49 IEEE-344-75 TES*
IE N/R CR, SIOS In Compliance
]
HCV-1108A 5
LL. C V-2983 1
USAR Closed /Open 10CFR50.49 ORIGINAL ND*
1E N/R CR, SIOS See 5.2.1 PfANT 191. NCV-742 1
IISAR Closed /Open 20CFR50.49 IEEE-344-75 ND*
IE N/R CR, SPDS In Compliance A/B/C/D I
2.
Containment R.G.
1 10 pala-D.P.
CAT.1 R.G. 1.100 REQUIRED 1E Required One Continuous Channel Prsssure CPIO See Type B Variables, Item !!I.3
- - With the exception of those penetrations whicts are exmpt from the requirement of double isolation (Ref. USAR Sect. 5.9.51 all mechanical penetrations are provided with redemdant isolation valves
- QA requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
K/R - Not Required i
8"*
I Date 10/2/96
_--.m..
m m-TABt.E 1 COMPARISON OP F0p? CALHOUN STATION 13f17 IO.1 INSTRt9ENTATION WI19f REGUTATORT GUIDE 1.97 REV. 2 Prwn-a TYPE "C" VARIABLIS PONER TMSTRtMENT gg RANGE DfV QUAL.
SEIS 00AL.
REIMHO.
SUPPt.T RECURDING DISPfAT tirATION ColetDITS rUEt. CtAoorNG
- 1. CET R.G.
1 200-1650*P CAT.1 R.C. 1.100 REQUIPID 1E N/R One Continuous Channel CPIO See Type A Variables, item III.3
- 2. Radioactivity R.G.
1 T.S.-100 T.S.
CAT. 1 R.G. 1.100 REQUIRED 1E N/R One Channel Continuous See Note 1 Concentration OPIO 0737 0737 T.S.-100 T.S.
0737 Not Applicable None Non-Class Ai-194 In Compliance la primary coolant
(.5pC1/cc-100p (SL-16,40)
C1/ce)
- 3. Analysis of R.G.
3 10pC1/mi-10C1/m1**
N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand See Note 1 Primary Coolant OPPD 0737 0737 10pC1/m1-10C1/m1**
AI-194 In Compliance (Gamma Spectrum)
(SL-17 Grab Samples) s 11 RFAN C00 TANT PRESSURE Ee0UNDARY
- 1. RCS Pressure R.G.
1 0-4000 psig CAT.1 R.G. 1.100 REQUIRfD IE Required One Channel Continuous OPIO See Type A Variables, Item II.2
- 2. Containment Pressure R.G.
1 10-DP psia CAT.1 R.G.k.100 REQUIRED 1E Pequired one Channel Continuous OPIO See Type B Variables, Ites !!I.3 3a. Containment Sump R.G.
2 Sump, 0-32 in.
CAT.2 N.S.P.
N.S.P.
Highly Reliable Required On Demand Wattr Level OPPD (Narrowl See Type B Variables, Item Iff.2a Nota 1 - The PASS gross gamma detectors will be used as on line monitors for radioactivity and gamma spectrum analysis of DC samples in lieu of the Rad. Nonttor on the letdown line.
This monitor cannot be used since the letdown line is isolated in an accident. The gross gamma detectors are fully qualified to NUREG-0737 and can measure RC, LPSI and sump.
- QR requirements categories 1, 2 and 3 shown in Section 2.3.3.A.5.
i E/R - Not Required se - peg. Guide 1.97, Rev. 3 Requirement
}
N.S.P.
- No Specific Provision I Rev. I Date In/7/Pn
TABLE 1 COMPARTSON OF 70RT CALHOUN STATION INIT 10. I maarnw 6 ATION NITH REGUIATORT GUTCE 1.97 R1'V. 2 FECUIRENENTS TYPE "C" VARIARI.FS PONER CA RMEGE INV CUAL.
SE!S 00AL.
REDUIO.
S'TJFL RICollDING DISPtAT 10 CATION C019fINTS IN!:TRUMDfT lE rr Riacr0R CODraNr PRESSURE EDPNDART (Continued) 3b.Contairment Sump R.G.
1 0-600,000 gal.
CAT.1 R.G. 1.100 REQUIRED IE Required One Channel Continuous Natir level OPPD See Type B Variables, Jtem III.2b Gidel
- 4. Centainment R.G.
3 IR/HR-10"R/ Hit N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required Continuous In Compliance 7
Area Radiation CPPD 3
US7R
.1mR/HR-10 mR/HR Recorded (DH-070 thru 075)
- 5. Effluent R.G.
3 10',6p C1/cc-N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required on Demand In Compliance Radioactivity 10 8p C1/cc
~
Noble Gas OPPD 3
tlSAR 10 h C1/cc-Recorded
~
(181-057) 10 ap C1/cc COMEDiSER OFP GAS
!!! COIrfAINMDif
- 1. RCS Pressure R.G.
1 0-4000 psig CAT.1 R.G. 1.100 REQUIRID IE Pequired Continuous OPPD See Type A Variables, item !!.2
- 2. Containment R.G.
1 0-10%
CAT.1 R.G. 1.100 REQUIRfD IE Required One Channel Continuous M Concentration OPIO See Type A Variables, item IV.1
- QA requirements categories 1, 2 and 3 shown in Section 2.3.3.A.5.
N.S.P.
- No Specific Provision
-14 Fev. I Date 10/2/86
_ - ~._-
. +...
j l
L 1
l TABIE 1 g
COMPARISON OF PORT CAIJf00N STATION UNIT NO. 1 l
INSTRUNDirATION NITH PIXMLA70RY GUIDE 1.97 REV. 2 REQUIRDENTS i
TTPE "C" VARIAB12S i
PONUt TNSTWMNDff gg RANGE DN QUAL.
SEIS QUAL.
RIDUlm.
SUPPLT RFIDRDING DISf'!AT IKATION CUNtDirS 111 CoerraTNMDff (Continued) 2 l
- 3. Containment R.G.
1 10-3xD.P. psia CAT.1 R.G. 1.100 REQUIRID 1E Required One Chnnel Continuous In Compliance Pressure OPPD 0737 0737 195 psig 10Cf1t50.49 IEEE-344-75+
YES 1E Recorded CR, SPDS (PT-783, 794)
- 6
- 4. Containment R.G.
2 10 -pC1/cc-CAT.2 N.S.P.
N.S.P.
Highly Reliable Required On Demand Effluent Radio-10 apC1/ec i
activity (Noble OPPD 0737 0737 10'h1/cc-0737 Non-Class Recorded CR In Compliance 5
l Cases) 10 pC1/cc A
(RM-063)
- 5. See Note 1 6
- 6. Effluent Radio-R.G.
2 10 pC1/cc-CAT.2 N.S.P.
N.S.P.
Highly Rellat*1e Required On Demand activity (Aux.
103pC1/cc 6
Bldg.)
OPPD 0737 0737 10 pC1/cc-0737 Non-Class Recorded CR In Compliance 5
(RM-06 H 10 pC1/cc s
i e - The entire loop is not qualifted to IE M-344-1975, only the sensors are qualified.
- QA requirements categories 1, 2 and 3 shown in Section 2.3.3.A.5.
Note 1: Reg. Guide 1.97, Rev. 3 deleted requirement for " Radiation Exposure Rates (inside buildings or areas in direct contact with containment penetrations or hatchways)*
E.S.P. = No Specific Provision 4
t i
1 i
1 Rev. I j
l n,.. i n t$ r.,
TABLE 1 CtstPARf90N OF POPF CALNOON STATION 19ff? MD. I usm -. ATION WITH PEGU!A10RT GUIDE 1.97 REV. 2 RFOUTRF3ENTS I
TYPE "D" VARIAR!JS POWER INSTRUpeNT CJA g RANGE ENV QUAL.
SEIS QUAL.
RfDUND.
SUPPLY REcopDING DISPIAT IACATION C0pWENTS 1 RESTDUAL HEAT RINOVAL STSTDI
- 1. SHR System R.G.
2 0-110% D.F.
CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand See Section 5.4.9, Floe OPPD 0-110% D.F.
6.2.4
- 2. BHR System R.G.
2 40-350*F+
CAT. 2 N.S.P.
N.S.P.
Highly Pe11able N/R On Demand See Section 5.4.9, HI outlet Temp OPm 6.2.5 II SAFETT IE7tCTIGt SYSTDtS 13.5. 1. Tank Invel R.G.
2 10%-90%
CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand (LT-2904, 2924, OPPD 2
flSAR O-100%
Commercial Non-Class CR, STOS See Section 5.4.1 2944, 29641 Grade Ib.S.I. Tank Pressure R.G.
2 0-750 psig CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand (PT-2901, ;?21.
OPPD 2
tlSAR O-300 psig Commercial Non-Class CR, SPDS See Section 5.4.2 2941, 2961s Grade
- 2. S.I. Tank Isolation R.G.
2 Open/ Closed CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand In Compliance l
Vilve Position OPPD 2
OSAR Open/ Closed 10CTR50.49 Class IE CR, SFDS See Section 2.3.3.B (MCb 2914, 2934 2954, 29741
- 3. Boric Acid R.G.
2 0-110% D.F.
CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R on Demand l
Charging Flav OPITI 2
USAR 0-140 gpu Commercial Non-Class CR, SPDS In Compliance (7T-2361 0-117% D.F.
Grade
- I e - Reg. Guide 1.97, Rev. 3 E/R = Not Required
- Ok requirements categories 1,2 and 3 shown in Table 2.
- It is located in e11d environment and is exempt from 10CFR50.49 as discussed in Sections 2.3.3.A.1 and 2.3.3.B.1.
N.S.P. m No Specific Provision Ref. I Date 10/2/M
- l', >
/
' f,'
~ 'I s
i
+
./,4 s
N 4?
g1
/
4
,)
)
{ !
TABLE 1 CUNFANISON OF 90PT CALHOUN STAf!ON ISI!? 30.1 INSTPt99FFATION WITH REGUIATORT GUIDE 1.97 REV. 2 P!TUIRf3tfMTS TYPE "D" VARIAP!JS MAfER CA RANGE Div QUAL.
SE!S QUAL.
REDulO_._
SUPPLT RECORDING DISPtAT TACATION CtD9ffJfTS lg IETPtmt3rf 111 SAFETT INJIETION SYSTt3tS (Continued)
- 4. Flow le HPSI R.G.
2 0-110% D. F CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R on Demand (FT-313, 316, OPID 2
USAR 0-300 gpm 10C71t50.49 IEEE-344-75+
IE CR, SICS In Compliance 313, 3228 (0-11C%)
- 5. Floe in LPSI R.G.
2 0-110%
CAT.2 N.S.P.
N.S.P.
Highly Ra11able N/R On Demand (IT-328, 330, OPIO 2
USAR 0-1500 gym 10CFR50.49 IEEE-344-75+
IE CR, SPOS In Compliance 332, 334)
(0-1104
- 6. SIPerr level R.G.
2 Top to Botton CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand (LT-381, 382)
OPfD 2
USAR Top to Botton 10CFR$0.49 Non-Class CR, SPDS In Compliance (LT-382 Not On SIOS) s IV FRfMARY C00 TANT SYSTIM
- 1. BC Pump Status R.C.
3 Meter Current N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand CR, SPDS In CompItance (T-3268, 3269, OPID 3
USAR 0-4200rN 3270, 3271)
- 2. Primary System R.G.
2 Closed /Nat CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand Relist Valve Position Closed (IORV) or Flow OPIO 2
0737 Flow Through 10CP1t50.49 IEEE-344-75+
TES CR, SiOS In Compliance Through (IT-141, (accoustic) 142) (F102-1, 102-2)
- 3. Priszurizer level R.G.
1 Bottom to Top CAT.2 R.G. 1.100 REQUIRID IE Required One Channe:,ontinuous OPPD See Trpe A Variables, Item 11.1 l*/R - Not Required
- - The entire loop is not qualif ted to IEEE-344-1975, only the sensors are qualified.
- 04 requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
N.S.P. = No Specific Provision Rev. I thee M/7/e4
l TARLE 1 CtwrAplSON OF PORT CAIJt00N STATION ISIIT NO.1 im m. rm ATICW NITH REGUTATORY CUIDE 1.97 REV. 2 RF00fRDIENTS TYPE D' VARIAMLIS PONER INSTRUNDff gg RANGE Div QUAL.
SEIS QUAL.
REDUND.
StfPPLT RETRDING DISPtAT IDCATION CTSSENTS j
IV PRIMARY C00 TANT SYSTDI (Continued)
- 4. Pr2ssuriser Heater R.G.
2 Electric Current CAT 2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand Status OPID 2
USAR 0-900EN Commercial TES Non-Class CR, SISS In Compliance (T-3272)
Grade **
- 5. Quench Taak Level R.G.
3 Top to Botton N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand (LT-132)
OPID 3
USAR Top to Botton CR, ERP, SPDS In Compliance S. Quench Tank Temp-R.G.
3 50-750*P N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R on Demand See Sec. 5.4.4 Ettre OPPD 3
t)SA.
E-300*FICR)
CR, SISS In Compliance (TE-133)
+ 750*P(SPDS)
[
- 7. Quench Tank R.G.
3 O (C EP.
N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand See Sec. 5.4.3 and Pretsure OPID 3
USF*
v 25 r4Jg CR, SPDS Sec. 6.2.1 (PT-131)
..e 7s19)*
CECONDART SYSTDI
- 1. Steam Generator R.G.
1 Tube Sheet to CAT.1 R.G. 1.100 REQUIRED IE N/R one Channel Continuous lavs1 Separators OPit See Type A Variables, Item I!!.6
- 2. Steam Generator R.G.
2 20% Above Lowest CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand Prstsure Valve Setting CPIO See Type A variables. Item !!T.7 N/R - Not Required
- OA requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
e Proposed Range
- - It is located in mild environment and is exempt from 10CFR50.49 as discussed in Sections 2.3.3.A.1 and 2.3.3.B.I.
W.S.P.
- No Specific Provision D
I Date 10/2/96
__1 m
s-1
/
TABIZ 1 CONPARISON OF FORT CALHDN STATION WIT 90.1 INSTRtBE3FTATION WITH REGUTATURY GUIDE 1.97 REY. 2 REQUIRINDITS 4
TYPE T* VARIABLES 2
IEEE l
C LNC::
E31V QUAL.
SEIS 00AL.
REDt20.
SUPft.Y RECORDING DISPIAT I4 RATION ColeENTS j
IISTRUNENT 3g V SECOBOART SYSTEN (Continued) 1
- 3. Relief Valve R.G.
2 C1sd/Not C1sd CAT.2 N.S.P.
REQUIRED Highly lleliable N/R On Demand Position (MS-291,292)
OPIO 2
TEAR Cisd/Not C1sd 10CFR$0.49 IEEE-344-75 ND IE CR In Ccep11ance
- 4. Mata Feedwater R.G.
3 0-110% D.F.
N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required On Demand Flow In Compliance Recorded CR, SPDS (PT-1101,1102)
OPPD 3
USAR 0-110%g.F.
(0-4x10 lbs/hr)
VI AUX FE!!9ETER
- 1. Aux Feedwater R.G.
2 0-110% D.F.
CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R n On Demand Flow OPPD 2
USAR 0-110% D.F.
10CFR50.49 IEEE-344-75+
TIS Highly Reliable CR, SPDS In Compliance
[
(FT-1109, 1110)
(0-300 gpal I
-2). Condensate Storage R.G.
3 Plant Specific N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand In Compliance Tank Nater level OPI9 3
USAR Top-Botton Commercial Grade CR (LT-1191) 2b.Esergency Feed-R.G.
1 Plant Specific CAT.1 R.G. 1.100 REQUIRID IE Required One Continuous Channel j
wattr Tank Level OPI9 1
USAR 0-160" 10CFR$0.49 IEEE-344-75+
YES 1E S19S CR, SPDS In Compliance (LT-1183, 1188)
(0-100%)
VII CONTAftetENT COOLING SYSTEMS
- 1. Containment Spray R.G.
2 0-110% D.F.
CAT.2
_ N.S.P.
N.S.P.
Highly Reliable N/R On Demand Flow OPPD 2
USAR 0-5000 gpa h rcial TES Highly Reliable CR, SPDS in Compliance (FT-342,343)
(0-110% D.F.)
Grade
- N/R - Not Required e - The entire loop is not qualified to IEEE-340-1975, only the sensors are qualified.
- QA requirements categories 1,2 ard 3 shown in Section 2.3.3.A.5.
- - It is located in mild environment and is exempt from 10CFR50.49 as discussed in Sections 2.3.3.A.1 and 2.3.3.B.I.
This device will perform its intended function pritt to its environment being considered a harsh environment.
W.S.P. = No Specific Provision
- D* I Date 10/2/M
.-s TABLE 1 COMPARISON OF PORT CAIJ100N staff 0N UNIT NO. I mamu.u.m ATION WITH REGUIATORT GUIDE 1.97 REV. 2 REQUIRDIENTS TTPE "D" VARIABLES PONG C
RANGE DfV QUAL.
SEIS QUAL.
REDUND.
SUPPLY RECORDING DISPtAY IOCATION CufstDrfS 3 gA, INSTRONDfT VII CONTA!NNDff OX) LING STSTDis (Continued)
- 2. Heat Removal by the R.G.
2 Plant Specific CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand in Compliance Containment Fan OPm 2
USAR O-2500 gym 10CFR50.49 IEEE-344-1975 Class 1E EPDS, CR (PT-416, 417, 410, 419)
- 3. Containment R.G.
2 40-400*F CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand See 5.4.5, 6.2.3 Atmosphere OPPD 2
USAR 0-400*F Commercial Non-Class SPDS Temperature Grade
- 50-250*F CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand See 6.2.6 4
- 4. Containment Sump R.G.
2 l
Water Temperature OPPD l
VIII CHDifCAL AND VOLUNE CorrROL
- 1. Makeup Flav R.G.
2 0-110% D.F.
CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R on Demand OPm See Type D Variables, item II.3
- 3. Letdown Flow R.G.
2 0-110% D.F.
CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand (IT-212)
OPPD 2
USAR 0-110% D.F.
Commercial Non-Class CR, Sms See 5.4.7 Grade
- 3. Volume Control R.G.
2 Top to Botton CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R on Demand Tank Invel OPm 2
USAR 0-100%
Commercial Non-Class CR, SPDS See 5.4.8 (LT-219)
Grade N/R - Not Required
- 0A requirements categories 1,2 and 3 shown in Section 2.3.3.A.5 D.S.P. = No Specific Presentation 20-Re'. I Date 10/2/86
m TABLE I (T)NPARISON OF FORT CAIJIDUN staff 0N (MIT NO.1 INSTROPYETATIN WITH REGU!ATORT GUIDE 1.97 FfV. 2 RECUTRDfDffS TYPE "D" VARIAPLES POWER INSTRUMDrf C3 g RANCE Div CUAL.
SETS QUAL.
PfDUND.
SUPPLY RECORDING DISPLAY IDCAff0N COPFDfTS IV COOLING NATER SYSTDI
- 1. Component Cooling R.G.
2 40-200*F++
CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand NatIr Temperature OPTO 2
USAR 0-300*r N
CR See 5.4.10 (TE-493, 494, 495, 4961
- 2. Component Cooling R.G.
2 0-1101 D.P.
CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R on Demand See 5.4.11 d
Natsr Flow OPIO 2
USAR CR, SPDS X RADNASTE SYSTDES
- 1. High Invel Rad.
R.G.
3 Top to Botton No Provision N.S.P.
N.S.P.
No Specific N/R on Demand Liquid Tank Invel CPIO 3
USAR Top to Botton Commercial Non-Class Al-100, SPDS In Compliance (LT-577, 578, s
579)
- 2. Rad. Gas Holdup R.C.
3 0-150% D.P.
N.S.P.
N.S.P.
N/R On Demand Tank OPIO 3
USAR 0-150t* D.P.
NO Non-Class AI-100, SIDS See 5.4.6 and 6.2.2
[j (PT-517, 518, 519, 5201 II VENT 1tATIN SYSTDIS
- 1. Emergency R.G.
2 Open/ Closed CAT.2 No Provision No Provision Highly Reliable N/R On Demand Ventilation Damper Position CPPD 2
USAR Open/ Closed 10CTR50.49 IEEE-344-75+
YES Non-Class CR,S10S In Compliance (HCV-724 A/B HCV-725 A/B)
MDTE 1 - Contatraent Ventilation Systems were considered only.
- - Proposed range modification.
N/R - Not Required
- On requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
- - The ectire loop is not qualified to IEII-344-1975, only the sensors are qualifted.
- - It is located in mild environment and is exempt fras 10CFT50.49 as discussed in Sections 2.3.3.A.1 and 2.3.3.B.1. This device will perform its intended function prior to it's environment bieng considered a harsh environment.
e* - Reg. Guide 1.97 Pev. 3.
i 2.S.P. = No Sgecific Provision Rev. I
-21 Date 10/2/86
TABLE 1
_ COMPARISON OF PORT CAIJmN STATTON TWIT NO. I
- nesmo, u.. ATICW NITH REGUtA10RT CUIDE 1.97 REV. 2 RFCtTTRINYWrS TYPE "D" VARIAHLIS PONER CA RANCE ENV QUAL.
SEIS QUAL.
RIDUND.
SUPPLY RECORDING DISPIAT tDCATION C0fstENTS Jg INSTRtBIENT XII IONrp SUPPLTIS
- 1. Stitus of Standby R.G.
2 Plant Specific CAT.2 N.S.P.
N.S.P.
Highly Reliable N/R On Demand Power
- t. 4kVAC buses OPIO 2
USAR Volts, amps, Note 1 IE N/R Control Room In Comp!!ance watts a
- b. 480VAC buses OPIO 2
DSAR Volts, amps, Note 1 IE N/R Control Room In Compliance c.125 VDC buses OPPD 2
USAR Volts, amps Note 1 IE N/R Control Roce In Ccep11ance d.120VAC busses OPPD 2
USAR Tolts (alarm Note 1 IE N/R Control Room In Compliance (Vital bus only) inverters)
- e. IDG Status CPPD 2
USAR Volts, amps, Note 1 IE N/R Centrol Room In Compliance SPDS watts
- f. IDG Speed OPPD 2
USAR rpm Note 1 IE N/R Control Room In Compliance
N/R - Not Required
- DA requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
Nota 1 - This is located in a mild environment and is therefore excluded from the scope of 10CI1t50.49. The equipment, however, meets the qualification requirements as they applied at the time of issue of construction permit and therefore meets applicable requirements for a mild environment.
N.S.P.
- No Specific Provision 8
I 22-Date 10/2/96 I
TARLE 1 CIMPARISON OP FORT CALH0tN STATION tNIT ND.1 INSTRtMENTATirN NITTI RErMIA1DRT GUIDE 1.97 REV. 2 RFOUTRDENfS TTPE *E" VARIABt.ES P(NER INSTRUNINT gg RANGE INV CUAL.
SEIS ODAL.
RIDUND.
SUPPLT RFIORDING DISPfAT TKATION C005tDrfS
! CONTA!IstENT RADIATION 7
- 1. Containment Aree R.G.
1 1-10 R/hr CAT.1 R.G. 1.100 REQUIRED IE Required One Continuous Channel Radiation CPPD See Type A Variables, Ites V.1 (High Range)
!! Area Radiation
~I-10h/hr CAT.2 N.S.P.
N.S.P.
Highly Reliable Required On Demand
- 1. Radiation Exposure R.G.
3*
10 R
Rste OPIO See Type C Variables, Ites II.4
!!! AIRBDRNE RADIOACTIVE MATDIA!S RET. EASED s
A. Noble Cases 6
- 1. Noble Gases R.G.
2 10 pC1/cc CAT.2 N.S.P.
N.S.P.
Highly Reliable Required On Demand Containment
~10hi/cc OPPD See Type C Variables, item III.4
- 2. Noble Gases (PDFORMID BT INSDtMDrTS ABOVE)
Reactor Bldg.
- 6
- 3. Noble Cases Aux.
R.G.
2 10 pC1/cc CAT.2 N.S.P.
N.S.P.
Highly Reliable Required On Demand 3
-10 pC1/cc Bldg OPPD See Type C Variables, item Ilf.6
- On requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
- - Reg. Guide 1.97 Rev. 3.
N.S.P. = No Specific Provision
-23 Rev. 1 Date 10/2/06
- r TAHLE 1 COMPARISN OP FORT CA1JiotM STATION UNIT ND. I anim-w3 ATION WITH REGT'IAMRT GUIDE 1.97 REY. 2 RFOUTRDIDf?S TTPE "E" VARIABLES PONER CA RANGE DIV QUAL.
SEfS QUAL.
RIDUND.
SUPPLT RECORDING DISPLAY I K ATION C0f0fENTS Jg INSTRtMDrf
!!! ATpPOIINE RADIDACTIVE MATERIALS RELEASED (Continued)
- 4. Noble Geses (DISCHARGE EFFLUDff THROUGli C01910N PIANT VDfT, THUS NOT REQUIRE AS PER REG. GUIDE)
Condenser Air Removat 6
- 5. Noble Geses Common R.G.
2 10 pC1/cc CAT.2 N.S.P.
N.S.P.
Highly Reliable Required On Demand Vent
-103pC1/cc OPTD See Type C variables, Item 111.4
- 6. Vent for S/G Safety R.G.
2 10'IpC1/cc CAT.2 N.S.P.
N.S.P.
Highly Reliable Required On Demand Relief Valves &
-103pC1/cc Atmosphere OPPD 0737 0737 10'IpC1/cc 0737 Highly Reliable Recorded CR in Compliance Duep Valve, &
-103pC1/cc (RN064 indirectly monitors steam Peedwater Turbine released through
- (RM057) (let064) this path.)
7.
All Other (N O OTHER POINTS ARE I D E N T I P I E D) i Identified Release Points B.
PAIPr1CUtATES & HALOGENS
~
10 8 C1/cc N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required On Demand 1.
All identified R.G.
3 p
-10a egfee Plant Release p
Points CPID 0737 0737 10'3pC1/cc 0737 Recorded CR In Comp!!ance (fr050, 060, 061,
-10apC1/cc 063)
- 04 requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
N.S.P. = No Specific Provision i
' Dev. I Date 10/2/86
TART.E I CCFPARISrW OF FORT CAUtnUN STATION IBifT NO.1 INSTRGFDrtATION WITH REGUYJLTfST GUIDE 1.97 REV. 2 RECCIRDIDFFS TYPE *E" VARIAPI.FS POWER INSTRUENT CA RANCE DrW CUAL.
SE!S QUAL.
RIDUND.
SrPFt.Y RIrDRDING DISPEAT 14 CAT 10N COF9fDFTS Jg IV Envirens Radiation and Radioactivity
- 1. See Note 1
- 2. Airborne Radio R.G.
3 10 1/cc N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand Halogens and
-10 3pC1/cc Particulates OPPD 3
USAR 10 M 1/cc
~
Continuous Rea1out In Compliance (Portable)
-10'spC1/cc (Portable)
~
- 3. Plant and Environs R.G.
3 10 3R/hr N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand Radiation
-10Mr
~
(Portable)
OPIO 3
USAR 10 8R/br Continuous Readout In C ap11ance
-10f.R/hr (Portable)
- 4. Pir.nt and Environs RG 3
Radioactivity CPPD 3
Performed by aboye instruments NETEDpotrGT
- 1. Eind Direction R.G.
3 0-360*
N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand In Compliance (F0031, 0032, 15' d
0033, 0034, OPTO 3
USAR 0-360*
CR, SPDS See 5.5.1 0043, 0044, 25' 0045)
- 2. Eind Speed R.G.
3 0-67 mph N.S.P.
N. S. P.
N.S.P.
N.S.P.
N/R On Demand (F0035, 0036, OP19 3
USAR 0-80 mph CR, SPDS See 5.5.1 b
0037, 0038)
- QA requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
K/R - Not Required NUTE 1 - Reg. Outde 1.97, Rev. 3 deleted requirements for " Radiation Exposure Meters, Continuous Indication at Pined Iscation".
C.S.P. = No Specific Prow!ston i
\\ Ree. 1 Date 10/2/96
-. ~,
i
.I k
}
TAPLE I COMPARTSON OP PORT CAIJ100N STATION IN!? 10.1 INSTRUNDirATICW NITH RFCt'tK!ORY CUIDE 1.97 REV. 2 RFOUIRDENTS TYPE *E" VARIABLES PONER Ca RANr:E Div QUAL.
SEIS QUAL.
REDUND.
SUPPLY RECORDING DISPtAT 10 CATION C0ppttNTS lg INSTRtreNT V Nerloporm? (Continued) b
- 3. Estimation of R.G.
3
-5*C - 10*C N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On D eand Section 5.5.1 Atmospheric OPPD 3
-5*C - 15'C CR, SPDS Stability (P0039, 0040, 0041, 0042)
VI Accident Sampling Capability A. Primary Coolant and R.G.
3 Grab Sample N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand Sump OPfD 0737 0737 Grab Sample In Compliance s
7
- 1. Gross Activity R.G.
3 10pC1/m1 N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand (Provided by
=10C1/m1 PASS) (SL-16, 40)
OPPD 0737 0737 10pC1/m1 Readout on Panel In Compliance
-10C1/mi AI-194
- 3. Game Spectrum R.G.
3 ISOTOPIC N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required On Demand (Provided by f
PASS) (SL-17)
OPPD 0737 0737
,1$0f0PIC Recorded on Demand In Compliance
- 3. Boron Content R.G.
3 (H 400 ppe N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required on Demand OPPD See Type B Variables, Item f.3
- On requirements categories 1,2 and 3 shown in Section 2.3.3.A 5.
C/R = Not Required N.S.P. = No Specific Provision 4 Rev. 1 Date 2n/2/R6
~
, _ ~.
I TABLE I C0ftPARISf1N CP FORT CA!JiDUN STATION LWi? M.1 smou.,w. ATION NIUt REmulTOPY GUIDE 1.97 REV. 2 RECUTRDENTS TYPE *E" VAPTAPLES PONER CA RANGE DfV QUAL.
SETS 00AL.
REDU 2.
SUPPLY RECOllDING DISPfAY ti1 CATION C0pFDrfS Jg l
s m munuis 1
VI ACCIDDrf SANPLING CAPAFILITY (Continued)
A. PPIMARY CD0fMr & StBtP fconto)
- 4. Chloride Content R.G.
3 0-70 ppe N.S.P.
N.S.P.
N.S.P.
N.S.P.
Required N.S.P.
(Provided by PASS) (SL-25)
OPPD 0737 0737 0-20 ppe Recorded In Compliance
- 5. D11 solved R.G.
3 0-2000 cc/kg N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand
!!- drogen er Total Gas (Provided by OPID 0737 0737 0-2000 cc/kg Total Gas Analysis In Compliance PASS) (SL-24) per 0737
- 6. Dissolved Oxygen R.G.
3 0-20 ppu N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand District was not re-quired to provide as per 0737 II.B.3.1-2 OPPD 0737 0737 N.S.P.*
requirements, and response to require-ments.
4
- 7. Pff (Provided R.G.
3 1-13 N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand by l'AS$1 (PffE-674 2)
OPIO 0737 0737 0-14 Readout on Panel in Compliance AI-194 1
B. (T9FTAI18tDif AIR i
- 1. Nydrogen Content R.G.
3 0-10%
W.S.P.
N.S.P.
N.S.P.
N.S.P.
Required on Demand OPTO S4+ Type A variables, itse TV-I.
- No Specific P.A.S.S. C a ponent. Can Take Grab Sample and Analyse L'tillaing Cheetstry Procedures
- QA requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
N/R - Not Required N.S.P. = No Specific Provision 4 Rev. I f%to 1n/2/R6
I i
i TABLE 1
]
CtstPARTSON OF 70PT CALHDf1N STATION 19 FIT NO.1 i=w ATION NITH PEGUIATORT CUIDE 1.97 REV. 2 REQUIRDENTS TYPE *E' VARIABLIS jl IONER TNSTRtBIENT gg RANGE BRf QUAL.
SETS QUAL.
REDism.
SUPPLY REEDRDING DISP!AT IECATION C0f9tDffS VI.B CONTA! MENT AIR (Continued)
- 2. Orygen Content R.G.
3 0-30%
K.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand Not required per SER dated 1/31/83 g
i and 9/1/83 (NO SPECIFIC I N S T R U N E N T *)
- 3. Gamma Spectrum R.G.
3 IS010PIC N.S.P.
N.S.P.
N.S.P.
N.S.P.
N/R On Demand (Provided by PASS)
OPPD 0737 0737 ISor0PIC On Demand In Compliance (SL-35, 40)
- No Specific P.A.S.S. Component. Can Take Grab Sample and Analyre Ut111aing Cheelstry Procedures
- QA requirements categories 1,2 and 3 shown in Section 2.3.3.A.5.
K/R - Not Required W.S.P. = No Specific Provision i
l 4
1 i
] Rev. 1 Date 10/2/96