ML20112J923

Rev 0 to Fort Calhoun Station Reg Guide 1.97,Rev 2 Response

ML20112J923
Person / Time
Site:	Fort Calhoun
Issue date:	03/31/1985
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20112J911	List: ML20112J908 ML20112J923
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 ES-84-07, ES-84-07-R00, ES-84-7, ES-84-7-R, TAC-51091, TAC-64447, NUDOCS 8504090255
Download: ML20112J923 (61)

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4.f FORT CALHOUN t STATION REGULATORY GUIDE 1.97, Rev. 2

RESPONSE

ES-84-07 Y

MARCH 1985 Rev. 0

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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. . . . . . . . . . . . . . . 20 5.1 Type "A" Variables . . . . . . . . . . . . . . . . . . . . . 21 5.2 Type "B" Variables . . . . . . . . . . . . . . . . . . . . . 24 5.3 Type "C" Variables . . . . . . . . . . . . . . . . . . . . . 25 5.4 Type "D" Variables . . . . . . . . . . . . . . . . . . . . . 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

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 performance 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 Thc se 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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F Al D

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.

Plant safety functions are (1) reactivity control, (2) core cooling. (3) maintaining reactor coolant system integrity, and (4) maintaining containment integrity Lincluding racioactive 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

)otential for being breached or the actual breach of the

)arriers 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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a 2.3.2 Clarifications and Revisions to NRC Reg. Guide 1.97, Rev. 2 requirements.

2.3.2.1 Fort Calhoun Unit 1 was operating at the time Regulatory Guide 1.97, Rev. 2, was issued.

Accordingly Fort Calhoun is required to meet the provisions 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 to 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 D0R 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 qualified to 10 CFR 50.49 will be included in the District's EEQ program by June, 1986,

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 and Qualification requirements applicable to various categories 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.

o A. CATEGORY 1

! 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 Plants," and the methodology described in NUREG-0588,

< " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equi) ment." Qualification applies to the canplete instrumentation clannel from sensor to display where the dis) lay is a direct-indicating meter or recording device.

Where t1e 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 qualified 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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O 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 instrumentation installed per NUREG 0737 i 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 4

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 (page F-11).

Requalification 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.

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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 operators to defeat or fail to accomplish a required safety function, additional information should be provided to allow the operators to deduce the actual conditions in the plant. This may l

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2. REDUNDANCY (Continued)

Reg. Guide Requirements (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 variaole that bears a known relationshi) to the mul-tiple channels (addition of a diverse channel.) ledundant or diversa channels should be electrically independent and physi-cally separated from each other and from equipment not classified im)ortant to safety in accordance with Regulatory Guide 1.75, "P1ysical Independence of Electric Systems," up to and including any isolation device. At least one channel should be displayed on a direct-indicating or recording device. (Note: Within each redundant division of a safety system, redundant monitoring channels are not needed except for steam generator level instru-mentation 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 single 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 I 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 Safety-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 and installed in accordance with the requirements that applied at the t'ime of issuance of the construction permit (Ref. USAR Section 8) rather than those of Reg. Guide 1.32.

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4. CHANNEL AVAILABILITY Reg. Guide Requirements The instrunentation channel should be available 3rior to an accident exce)t as provided in paragraph 4.11, " Exemption", as defined in IE EE 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:

Regulatory Guide 1.28 " Quality Assurance Program Requirements (Design and Construction)"

Regulatory Guide 1.30 " 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

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Design of Nuclear Power Plants" Pegulatory 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 5Ervices for Nuclear Power Plants" Reg. Guide Requirements (Continued)

Regulatory Guide 1.144- " 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 R5 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 or instrument span should be provided, s

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 com) uter memory, and displayed on demand. Intermittent-displays suc1 as data loggers and scanning recorders may be used if no significant transient response infnrmation is likely to be lost by such devices.

DISTRICT'S POSITION Recording capabilities are noted in Table 1.

B. CATEGORY 2

1. EQUIPMENT OUALIFICATION Reg. Guide Requirements The instrumentation 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 3rovided the instrumentation is ) art of a safety-related system. dhere the channel signal is to )e )rocessed or dis) layed on demand, qualification applies from t1e sensor throug1 the isolator / in)ut buffer. The location of the isolation device should be such tlat 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.

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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 interval should be based on normal Technical Specification requirements on out of service for the system it serves where applicable 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.

WE'ere 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.

C. CATEGORY 3

1. EQUIPMENT QUALIFICATION Reg. Guide Requirements The instrumentation should be of high-quality commercial grade end should be selected to withstand the specified service envi-ronment.

DISTRICT'S POSITION The District takes no exceptions to this requirement.

2. REDUNDANCY Reg. Guide Requirements No Specific Provisions.

DISTRICT'S POSITION Same as per the Reg. Guide requirement.

3. POWER SOURCE Reg. Guide Requirements No Specific Provisions.

DISTRICT'S POSITION Same as per the Reg. Guide requirement.

4. CHANNEL AVAILABILIT*f Reg. Guide Requirements No specific provisions.

DISTRICT'S POSITION Same as per the Reg. Guide requirement.

5. QUALITY ASSURANCE Reg. Guide Requirements No Specific Provisions, j 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 d 11, 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 R_eg. Guide Requirements

1. The following criteria should apply to Categories 1 and 2:

a. Any equipment that is used for either Category 1 or Category ,

2 should be designated as part of accidentmonitoring 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 nor.-CQE portion should be iso-lated from the CQE portion through isolators.

Isolation devices meeting the requirement; as they applied at the time of issuance of the construction permit 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-fled Reg. Guide 1.97, Rev. 2 requirements outlined above.

i 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 l Categories 1 and 2 shnuld be specifically identified on l the control panels so that the operator can easily l 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 l appropriate, the instrumentation will be identified to improve i operator interface.

2. In addition to the above criteria, the following criteria should apply to Categories 1, 2 and 3:

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a. Servicing, testing and calibration programs should be specified to maintain the capability of the monitoring .

instrumentation. For those instruments where the I required interval between testing will be less than the normal time interval between generating station shut-downs, a capability for testing during power operation sE'ould 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,

e. The instrumentation should be designed to facilitate 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 sEculd be made only when it can be shown by analysis to provide unambiguous information.

D. ADDITIONAL CRITERIA FOR CATEGORIES 1, 2, and 3 l

Reg. Guide Requireinents

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

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 i 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.

3.0 METHODOLOGY FOR REVIEW 3.1 Type A Variables The District reviewed Reg. Guide 1.97, Rev. 2 to evaluate whether the Fort Calhoun Accident Monitoring Instrumentation complied with the specified requirements. The District's first step in evaluation of the Reg. Guide was to identify all systems which could provide the 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 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 Fort Calhoun Station designated Type A variables are:

Safety Functions FC Type "A" Variables I Reactivity Control Neutron Flux 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 2 Concentration 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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SUMMARY

OF DISTRICT'S REVIEW 4.1 After a thorough review of the Reg. Guide and tabulation of the data sheets, a brief summary 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 P,ange

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 documentation.

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-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 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 levels, this indication is referred to the actual instrument taps rather than 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:

AI-100. -

Radwaste Panel AI-194 -

Post Accident Sampling System (PASS) Panel Aux. Bldg.- Auxiliary Building CAT. -

Category from Reg. Guide 1.97, Rev.2 i CCW - -Component Cooling Water Cont. -

Containment CET -- Core Exit Thermocouple CSS - Containment Spray System DP(F) - Design Pressure (Flow) e

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SUMMARY

OF DISTRICT'S POSITION 4.1 (Continued)

CR -

Control Room EDG -

Emergency Diesel Generator EOF -

Emergency Operation Facility EP -

Emergency Procedure ERF - Emergency Respcnse Facility HJTC - Heated Junction Themocouple HPSI - High Pressure Safety Injection HX -

Heat Exchanger LPSI -

Low Pressure Safety Injection NPSH -

Net Positive Suction Head N/R - Not Required PASS -

Post Accident Sampling System QT -

Quench Tank RCS -

Reactor Coolant System RG -

Regulatory Guide RV -

Reactor Vessel SCHX -

Shutdown Cooling Heat Exchanger SCMM -

Subcooled Margin Monitor S/G -

Steam Generator SI -

Safety Injection SIRWT' -

Safety Injection Refueling Water Ta ik SIT Safety Injection Tank SPDS  ! Safety Parameter Display System TS -

Technical Specifications USAR -

Updated Safety Analysis Report 5.0 EXCEPTIONS TO REGULATORY GUIDE 1.97 REV. 2 General Table 1 provides a comparison of the Reg. Guide requirements with the 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-tiun 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 l systems in the accident situation, is met in all cases. The analyses have been segregated into sections covering the. specific variable types.

l s

+

r 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 monitors (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.1 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. These loops are_in compliance'with the requirements of Reg. Guide 1.97 except as noted herein:

Range - The existing range of the Fort Calhoun RCS pressure

. measurement is 0-2500 psig (design _ pressure). Reg. Guide 1.97 specifies that, for Combustion Engineering plants, the range should be 0-4000 psig.

Seismic - Certain portions of these instrument loops have been upgraded to-IEEE-344-1975. However, the entire loops are not qualified to IEEE-344-1975. The sensors are quali-fied. Other comp]nents of the loop are qualified' to the seismic requirements which were applied at the time the construction permit was-issued.

e DISTRICT POSITION The District believes that these above deviations from the requirements are justified based on the following: The indication provided is adequate to monitor all anticipated pressure events currently analyzed in the USAR. For those analyses the pressure will not exceed the 2500 psig end point. The District will upgrade the existing equipment, if required, to provide a range which is consistent with the resolution of the ATWS issue. The upgrade is proposed to be performed during the 1987 refueling outage.

For further discussion with regards to seismic qualifica-tion, see Section 2.3.3.A.1.

Sumary Position The proposed upgrade will resolve the ATWS issue.

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 NUREG-0578. These SMMs 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 Both subcooled margin monitors, and instrument loops which t provide inputs into the SMM's', are in compliance with the Reg. Guide requirements with the following exceptions:

Temperature Loops - These are in compliance except for the ranges. The existing loops are narrow range. These in-strument loops will be upgraded or new instrumentation will be added to meet an earlier commitment (Ref. 7.11) to.-

provide wide range inputs into the SMM's.

Pressure Loops - Deviation 1in the pressure loops are dis-

~

l cussed in Section 5.1.2 above. L L

l i

^

q DISTRICT'S POSITION: ,

In addition to the above-described Subcooled Margin Monitor  :

with the narrow hot and cold leg temperature input ranges, '

additional subcooled-margin indications are available as part of the Safety Parameter Display System (SPDS). The SPDS performs two additional subcooled margin. calculations.

These additional calculations are based on representative .i

' Core Exit Thermocouple.(CET) temperature, and upper head temperature as sensed by the reactor vessel level Heated 1

~

Junction Thermocouple (HJTC) probes.

Both of the above mentioned temperature input.(CET and HJTC):

loops when operable, will be 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  ;

Sm 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

There are three SMM. indications ~available. .With.the-excep- -

tion of portions of the pressure loops, (as discussed .in - '

section 5.1.2) and portions of the temperature loops (as discussed in section 5.1.3),-SMM indication meets the ' .

requirements of Reg. Guide 1.97, Rev. 2.- Those portions that.are located in mild environments. meet, at a minimum, the seismic and QA requirements-which were applicable at the time of issuance of the construction permit. They wi,ll not -

be. upgraded. The range' deficiency will be corrected by^the installation of new temperature instrumentation in accord-ance with our previous.(see Ref. 7.11) commitment.

Thus,bythemodificaNonproposed.above,theDistrict believes that adegaate in trumentation will be provided to perform the intended Accident Monitoring Function.

5.1.4. Vessel Level Monitoring (CAT. 1)-

.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 Systemi(SPDS). The displays _are provided in the' control room, TSC and EOF through the.SPDS portion of the'ERF~ computer.

=- -, .. . - - . . - - ,;-.-.-..,_,.- -

,l t 5.1.4 Vessel Level Monitoring (CAT.1) (Continued)

These loops have been designed to be in full compliance with i

- the requirements of Reg. Guide 1.97.  ;

Summary Position A commitment to provide a system for monitoring the reactor vessel level as per Reg. Guide 1.97, Rev. 2 requirements has  ;

- previously been made. The' completion schedule for this modification was provided in Ref 7.11.

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, 11mit switches'provided on the fc110w-ing valves are environmentally qualified _to 10 CFR 50.49 (DOR Guidelines) but do not meet the Category 1 seismic requirements of Reg. Guide 1.97.

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-13888/13878_ -Aux. Bldg.

HCV-1559A/15598 Aux. Bldg.-

- HCV-1560A/1560B -Aux. Bldg.

HCV-2603A/2603B Aux. Bldg.

ACV-2983- Aux. Bldg.

Wi-f v v-p-,tef 7wg- '*er-e **,b'd> f j* * **v - y a <*'avv e w'Be 7 91I yv4v-T -- m +- -+ $

5.2.1 Containment Isolation Valve Position (CAT.1) (Continued)

Containment Isolation Valve Location HCV-400C/401C/402C/403C Aux. Bldg.

HCV-438 B/D Aux. Bldg.

'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-1385, 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.1.

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 Tyne C Variables ,

! No exceptions taken.

5.4 Type "D" Variables 5.4.1 Safety Injection Tank Level (CAT. 2)

The SIT level monitoring system is utilized for normal operation and performs no useful purpose for accident monitoring. These tanks are required to automatically discharge in the event of a LOCA. Other means of monitoring SIT performance are provided by the RV Level Monitoring System. The RV level indicators will provide the operators-with information on core coverage. The RV Level Monitoring System is a fully qualified, independent means for monitor-ing the post accident performance of the long term-or emergency core cooling systems.-

5.4.1 Safety Injection Tank Level (CAT. 2) (Continued)

_ Summary Positicn The existing instrumentation is not required for Post Accident monitoring, and the accident monitoring function is fulfilled by use of the RV level monitoring system.

5.4.2 Safety Injection Tank Pressure (CAT.2)

Safety Injection Tank pressure indication provides no useful information under accident conditions. The pressure indica-tion is necessary to monitor technical specification require-ments under normal operating conditions. No modifications or upgrades are, therefore, proposed.

Summary Position On the basis of the above justification, the District believes that no instrumentation is required for this post accident monitoring function, and that the existing instru-mentation loops are adequate to perform the intended Moni-toring Functions. Therefore, no modifications are proposed.

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).

The quench tank pressure loop is currently 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 neasurement shnuld 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.

Sumary Position This pressure transmitter will be modified to be consistent with Reg. Guide 1.97 requirements. The proposed modifica-tion 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 below:

5.4.4 Quench Tank Temperature (CAT. 3) (Continued)

Range: The temperature sensor is a 2000 duel-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 2000 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)

The function specified above is performed by the containment atmosphere temperature instrument loops (I.D. No. T-714, 716,.718,720) located in containment on the HVAC system.

These loops are in compliance with the requirements of Reg.

Guide 1.97 except as noted herein:

Environmental Qualification: The Reg. Guide _1.97, Rev. 2 specifies that the instrument loops are to be environmental-

~

ly qualified to IEEE-323-1974. The existing loops are not qualified to this standard.

Summary Position The District will upgrade the temperature transmitters to be qualified in accordance with 10 CFR 50.49. All other components are located in a mild environment and are ade-quate to perform their intended functions. See 3ection 6.2.4 for schedule.

5.4.6 -Containment Sump Temperature (CAT.2)

The function of this variable measurement is to provide information on the operability of the Containment Cooling Systems.

DISTRICT'S POSITION The Fort Calhoun Station currently does not have any pro-vision for measuring the containment sump water temperature.

The District believes this measurement is not required based on the following justification.

w T

5.4.6 Containment Sump Temperature (CAT.2) (Continued)

Sump water temperature indication is only critical in the case where water temperature was not assumed.to be saturated in calculating the NPSH for the Safety Injection and Con-tainment Spray pumps' in the recirculation mode. The calcu-lations performed for NPSH in the recirculation mode were conservative and assumed that the water was saturated. It was proven that the NPSH available from the pumps was adequate. The emergency core cooling and containment spray systems have been designed assuming no increase in contain-ment pressure from the initial atmosphere pressure present prior to the postulated loss of coolant accident. The NPSH values calculated are based on this assumption and do not sinclude the NPSH that is available due to the containment water being less than 212 F (Ref. USAR Section 6.2.5) On this basis we do not believe it necessary,to provide instru-mentation on the temperature of the sump water. The core cooling measurements can be used to infer containment cooling.

5.4.7 Radioactive Gas Decay Tank Pr' essure (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 6.2.3 for schedule of modification.

+

+ ~

-3

~

5.4.8 RCS Letdown Flow (CAT.2)

The: variable listed above is to provide operator information

^

with the status of RC letdown flow.

~ w- The function specified above'is performed during normal >

operation by the Letdown flow transmitter loop-(F-212).

DISTRICT'S POSITION:

i

'During an. accident situation the letdown system is. isolated,

' and thos readout of letdown flow would be meaningless.

Thus this parameter is not required for accident monitoring.

Sumary Position

~

No upgrades are proposed for this instrumentation loop.

5.4.9 Volume Control Tank-Level (CAT.2)

-- The variable listed above is to provide operator information with the status of the VCT level, s

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; Y 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 y* injection 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.

b Summary Position 3

. Thus, the District will'not upgrade the currently; installed-R level transmitters to meet the 50.49 ruling.

~

l 5.4.10- Residual Heat Removal .

1' '

The Fort Calhoun Station Residual He'at RemovalE(kHR).is

^

accomplished in_ a post-accident. situation by. either the - ,

q steam generators and shutdown coding or the Long Term Core .

i 3 Cooling System'and' shutdown cooling depending on the type of_ '

m Design Basis Event being censidered. ' e 1

T. ,

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V 1 ,

29- 7-o

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e -e..--v y e .ma g5 - 9 J- -m e - v n # v h -, W r----y+-He e~ , + + y 4 w -

5.4.10 Residual Heat Removal (Continued)

The Steam Generators (defined as intact generator, Auxiliary Feedwater, and Main Steam Power Operated Safety Valves) are used to cool down for all DBEs including the class of LOCA (breach of the the RCS) in which the primary system remains 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.

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 PORVs as a flow path if both steam generators are not available is used. This is con-sidered c backup. The District believes that the perfor-mance of RHR can be monitored by the use of the CETs 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 Vlv on RCS Position Indication

~SDC Flow

• SDCHX Outlet Temp.*

RCS Information RCS Pressure RCS Hot Leg Temp.

'RCS Cold Leg Temp.-

'CCT HJTC - Vessel Level

• Require Upgrade g w w r , -

5.4.10 Residual Heat Removal (Continued)

DISTRICT'S POSITION The District will upgrade the two noted items as described in 6.2.4 and 6.2.5.

-5.5 Type E Variables No exceptions taken.

6.0 DESIGN DESCRIPTION AND SCHEDULE FOR IMPLEMENTATION OF IDENTIFIED UPGRADES 6.1 Type A Variables 6.1.1 The existing equipment described below, and in 6.1.2, does not meet Reg. Guide 1.97, Rev. 2 requirements. In order to be in compliance, the RTD's will be replaced. A commitment was previously made to the Commission (Ref.

7.11) The modification is to be completed by the end of the 1985 refueling outage.

RCS Hot Leg Temperature The existing equipment is not in compliance with Reg. Guidt:

1.97 range' requirements. In crder to be in compliance a total of four RTD's used for_RCS Hot Leg Temperature will have to be replaced along with their respective transmit-ters, signal conditioners, power supplies, and indication meters. The RTD's will be qualified per 10 CFR 50.49.

Two of the five RTD's used on each of the two Hot Leg loops will be replaced with Class IE RTD's. The transmitters, conditioners and power supplies will be installed in a mild environment.

6.1.2 RCS Cold Leg Temperature The existing equipment is not in compliance with Reg. Guide 1.97 range requirements. In order to be in compliance a total of six RTD's used for RCS Cold Leg temperature will have to be replaced along with their respective transmit-ters, signal conditioners, power supplies and-indication

, meters. Three of the six RTD's used on each colo loop off the steam generators will be replaced with Class 1E RTD's.

This modification is scheduled for completion during the 1985 refueling outage.

6.1. 3 - Reactor Vessel Level Monitoring A commitment to provide a system for monitoring the reactor

vessel level as per Reg. Guide 1.97, Rev.-2 requirements was made. The completion schedule for this modification is provided in Ref. 7.11.

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 in compliance the existing pressure transmitter and meter

--relay will have to be replaced. The pressure trar.smitter is required to be qualified for its service environment and therefore, will be qualified to 10 CFR 50.49. The meter relay, power supply and other equipment located in mild environment will meet Reg. Guide 1.97 Category 3 qualifi-cation requirements.

The meterexisting (transmitter relay located (locatedment) in mild enviror, in containment) and the will be upgraded-replaced 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 The temperature transmitters on the centainment air cooling lines (T-714,716,718,720) will.be replaced with environ-mentally qualified components. . This modification will be performed 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.

6.2.5 Shutdown Cooling Heat Exchanger Outlet Tempeiature' The transmitters fcr Shutdowi. 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.

7.0 REFERENCED DOCUMENTS 7.1 Supplement 1 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).

7.0 REFERENCED DOCUMENTS (Continued) 7.3 . Combustion Engineering Emergency Procedures Guidelines, Rev. 2.

7.4 Fort Calheun Emergency Procedures 7.5 Fort Cainoun 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 (J. R. Miller) dated September 28, 1984 (LIC-84-323) f k

T 9

L

. ... _m _ s _ .. _. _ _ . . . .. _ ._

'h9

.e e

^

1 TABLE 1 CCMPARISON OF PORT CA!JIOUN STATION UNIT NO.1 INSTBtNENTATION WITH REGUIM0ltf GUIDE 1.97 PEV. 2 RECCIREMDrfS TYPE 'A' VARIARI2S PONE

INSTRUNDr? CA QA, J ' RANGE

. INV ODAL. SE!S QUAL. REDUIS. SUPPLY RRCOICING DISPIAT 14 CATION C0femf7S 1 REACTIVITY CONTROL

- 1.'IIeutron Flus 'R.G. 1- - 10 4-100% CAT.1, R.G. 1.100 REQUIRED 1E Required One t h anal Continuous In compliance with.

(art-001, 002,  ;OPPD 1 USAR. 10' t-1256 10CFR50.49 IEEE-344-75** . TIS 1E SPDS CR, SPOS exceptions noted in 003, 004) . Section 5.1.1

'11.~RCS INVDrT1RT/ PRESSURE CONTRDL

1. Pressuriser 1mel R.G. '1 = 0-100% , CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous (LT-1013/T) OPPD 1 USAR 0-100% 10CFB50.49 IEEE-344-75+. TES 1E . Recorded CR, SPDS In Compliance

~ 2. RCS R.G. 1 - 0-4000 peig CAT.1 R.G. 1.100 haQUIRED - . 1E .. Required . One Cnennel Continuous

. Pressure . OPPD 0737 0737 0-2500 psig 10CFR50.49 IEEE-344-75* ' YES 1E Recorded CR, SPDS See Sectica 5.1.2 (PT-105, 115)

..3. Degrees of Subcooling R.G. .1 - . 200*F to 35*F CAT.1 R.G. 1.100 . REQUIPED 1E Pequired One Channel Continuous A-Monitor OPPD 0737 0737 200*r to 35*F 10CTR50.49 IEEE-344-75 ' TES 1E ..SPDS CR, SPDS See Section 5.1.3, R-Nonttor : See Section 6.1.1

See Section 6.1.2 N C - Not required. . . . ,

e

• The entire loop is pet qualified to IEEE-344-1975, only portions, including the sensors are quellfied.

• = The transmitters located in the harsh enviroreent were replaced per 10CFR50.49. The new transeitters are qualtfled per IEEE344-1975 and 10CFR$0.49. All other components of the loop are qualif ted per the seismic requirements which applied at the time the constructica permit was issued. (Reference Appendia F of the t1SAR).

• • - The entire laap is not quellfled to IEEE-344-1975, only the encore detectors an4 amplifiers are quellfled. The '.elance of equigaent is qualified to original seismic quellfication.

• QA requirements for categories 1,2, and 3 are shown in Section 2A.3.A.5.

R.% - Regulatory Guide 1.97, Rev. 2 requirements.'

-1 Rev. S

.Date 4/1/85

.2 - -, _ _

. ,,- ,. ~- , - , , . . _

A 9 +

TABLE I COMPARIS(Bf 0F PORT CAIJ40f3f STATICal WTT NO.1 IISTR'AIDITATIQs N!TH REGUIATORT GUIDE 1.97 REV. 2 REQUIRDENTS TTPE *A" VARIAMJS PONER

' IISTMBerr gg RAlmE BfV ODAL. SEIS CUAL. REDING. StfPPLT RECORDING DISPtAY thCATION CGGGITS III CORE & RCS NEA* RDIDVAL

1. Cold leg 3.G. 1 - 50-700*F** CAT.1 R.G. 1.100 REQUIRED 1E - Required One Channel Continuous See Section 5.1.3 Temperature ,

OPPD 0737 0737 0-750*F* 10CTR50.49 IEEE-344-75+ TIS 1E SPDG CR, SPDS, RPS To be installed (Tag mi.abers to be 1985 Outage,

' identified at a Section 6.1.1 lit r datel

2. Not lag R.G. 1 - 50*F-700*F** CAT.1 R.C. 1.100 REQUIRED 1E Required One Channel Continuous See Section 5.1.3 Temperature CPIO 0737 .0737 . 0-750*F* 10CFR50.49 IEEE-344-75+ . TES It SPDS CR, SPDS To be upgraded T!*112N A,8 .1985 Outage,

.TI*122H A,8 Section 6.1.1

3. Core Esit  : R.G. 1 = 200-1650*F - CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous ' See Ref. 7.11

. Temperature OPPD 0737 0737 32-2300*F 10CFR50.49 IEEE-344-75 TES', 7 per quad. 12 . SPDS ' SPDS To be upgraded

RC-7D (1 24) 1985 Outage, Section 6.1.1

4. Degrees of R.G. 1 - 200*F to 35'F CAT.1 R.G. l.100 REQUIRED 1E Required One Channel Continuous

'Simcooltag OPPD ' See Type A Variables, Item !!!.3

+ - U.s ar. tire laap is not qualif ted to IEEE-344-1975, only the sensors are qualitted.

- 04 requiremsets for c.tegories 1,2 and 3 are shown to Section 2.3.3.A.5

• Proposed gange

• Reg. (hilde 1.97, Rev. 3 a

o

. Rev. 8 Date 4/1/95

]

.. . ._ _ _ . ,,. _ _ ._ m. . . _ . _s a.

+

. TABLE 1 COMPARIStaf CF PORT CAIJ100N STATION (BITT NO.1 IISTRtBEENTATION WITH REGUIATORY GUIDE 1.97 REV. 2 REQUIRDENTS f

TYPE *A* VARIAPI.ES PONER SEIS QUAL. REUIC. SUPPLY RITORDING DISPtAY EDCAffatt . C0fBtDffs i IISTRIBE3ff  ; CAJ'g RANGEk INV QtlAL.

. 111000tE & RCS MEAT RINov4L -

IContinusel.

R.G. 1.100 1E REQUIRED One Channel Continuous

5. RV level - R.G. 1m' - Rottom of Hot

• CAT.1 REQUIRED lag to top of (Y-116A/R)

.. Vessel l N111 be in YES 1E SPDS SPDS compliance.

' OPPD 0737 0737 Top of Core 10CFR50.49 !EEE-344-75 Systen Not to top of declared Pully

.. Vessel Operational until 1986 See Section 5.1.4 and 6.1.2 R.G. 1.100 REQUIRED 1E REQUIRED One Channel Continuous R.G. Tube Sheet'to - CAT.1

' 4. S/G Invol 1 -

.(LT-911 A!W Separator (1T-917 A/B1 1E SPDS SPDS, CR In Compliance OPPD 0737 0737' - Tube Sheet to 10CFR50.49 IEEE-344-75 ' YES Separator

'- (0-1001) 1 CAT.1 R.G. 1.100 ' REQUIRED 1E REQUIRED One Channel Continuous

. 7. S/G Pressure R.G. 1 - A1M to 20%

(IT-913 A/R) above lowest (PT-914 A/R) safety valve setting.

1E SPDS CR, SPDS In Compliance CPPD 0737 0737 ATM to 204 10CFR50.49 IEEE-344-75 TES 0-1200 pste 8.- Reg. Guide 1.97 Rev. 3 requirement.

- DA requiressets for categottee 1,2 and 3 are sheen la Sectica 2.3.3.A.S Rev. f Date 4/1/95

s 4

.. e:

e TABLE 1

@gIPARISON OF P03T CA!Jf0tBI STATION 1RI!T NO.1 INSTRIBerrATICK WITH REGU!ATORY GUIDE 1.97 REY. 2 REQUIRBENTS TYPE *A" VARIABLES PONER SEIS CUAL. RIDERS. SUPPLY RECORDING DISPTAT TRATION CODWelTS INSTuteerr A3 C . RANGE ENV QUAL.

TV CntrrADDeff COMUSTTSLE GAS CONTBDL -

1. Cont:1 ament 9.G. 1 - 0-104 CAT.1 R.G. 1.100 REQUIRED 1E Deguired one Channel Continuous

.R Concentration .CPPD G737 0737 0-104 10tFR50.49 IEEE-344-75 YES 1E Recorded - SPOS, C3t Is Compliance

'(VA-81A/3)

V 00NFADSWff RADIATICBI

1. C4mtliament Righ .3.G. 'l = 1-107R/HR CAT.1 .- R.G. 1.100 REQUIRED 1E pequired . One Channel Continuous

- Sange Radiettee (WI-091A, Int @ 181 OPPD 0737 -0737- 1-10~7R/W 10 CFR 50.49 IEEE-344-75 TES 1E Decorded CR, SPDS in Compliance i

1

= 0 requirements for categories 1,2 .ad 3 are shown la Section 2.3.3.A.5

+

.. Dev. S Date 4/1/8%

F.

N1 P x 4

h-

+

f.

TABLE 1 Ct31 PARI 9 Cal OP PORT CALH0tRI STATION tRIIT No.1 IWTRtBENTATI(31 MITH REGUIATORY GUIDE 1.97 PEV. 2 REQUIRDIDrfs TYPE 4" VAntaanvt

. 70NI3t INSTRtNeff Jg CA _ RANGE FMV QUAL2 SEIS QUAL. REDtas. SUPPLY RECORDING . DISPfAT IACATION C000fENTS

- REACfrvrTT CONrBor.

1. Neutros Plus R.G. 1 - 10 kloot CAT.1 R.G. 1.100 REQUIRID 1E Required one Channel continuous OPPD . See Type A Variables, Ites !.1'

3. Centret Dod 9.G. 3' =

Full la er Not ' N.S.P. . N.S.P. N.S.P. N.S.P. M/R On Dunand Peettien .

Nighly peliable (CEDet'd OPPD 3 USAR Pull la er Not CB, SPDS It Compliance

3. DCS Soluble Beren D.G. 3 - 0-6000 pon . W.S.P. N.S.P. N.S.P. N.S.P. Dequired On Demand Concentratten (SLa25) OPPD 0737 0737 0-60uo ppe ' Backup by Recorded Chart Recorder In Compliance Crab Sample See Note 1

. . . .{;

4. RCS Cald tag - 3.G. 50-400*P . N.S.P. N.S.P. N.S.P. N.S.P. Required 3 - on Demand Noter Temperature (TT-113 OPPD 3- USAR 0-600'P IE pecorded CP, SPOS In Compliance TT-121)

!! _CCItE CODLING

1. RCS Not tag Temp. R.G. 1 - 50-700*P** ' CAT.1 R.G. 1.100 REQUIRED 1E Sequired One Channel Continuous OPf9 See Type A Vertables, Item III.2 Note 1

• The Ph881em chromatograph ett! be used as the primary boros concentration measurement for accidset monitoring in lieu of the terunmeter. The ton chromatograph was designed to NUREG-0737 requirements and can measure RC, LPS! and containment sump samples.

- Ok requirements for categories 1,2 and 3, Section 3.3.3.A.5 N/R

• Not Degaired

• • = Deg. Outde 1.97, Bew. 3 N.S.P. e No Specific Provision pov. 8 Date 4/1/95

., . _ _ _ . _ . _ . . ._. _ _- . . _ _ . . ._.m. _ _ , .

-e r

-a 1

e' TAatz 1 COMPARISON OF PORF CAIJ00taf STATION 198IT NO.1 ItWTRIBeffATION WITH REGUIATOPY GUIDE 1.97 REV. 2 RFQUIRDtINTS TYPE *R* VARIAB'JS POWEB INV QtRL. SFIS QDAL. REDtBC. SUPPLT RECORDING QPtAY EDCATION C0feUNfS IISTRIBeff . cal gn, RANGE II CDRE COOLING (Continued) a

2. BCS Ccid leg Temp. R.G.- 1- - ' 50-700*F** CAT.1 R.G. 1.100 REQUIRED : IE Required One Channel Continuous CFFD See Type A Variables, item III.1

3. RCS Pressere R.G. 1 - 0-4000 psig CAT.1 R.G.1.100 - REQUIRED. IE Required One Channel Continuous CPPD See Type A Variables, Ites !!.2

4. CET 3.G. 3 -# 200-1650*r N.S.P. N.S.P. N.S.P. N.S.P. Required on Demand CPPD See Type A Variables, Item III.3

5. RV level R.G. 1 ' - . Rts of Not Leq** CAT.1 3.G. 1.100 REQUIRED 12 N/R One Channel Continuous Ienesterlag , to top et Vessel CPPD . See Type A Variables, item III.5

4. Dogeoes of 3.G. 2 - 200*F - -15*F CAT.2 ' N.S.P. N.S.T. liighly Reliable Required on Demand Sunceoling OPPD See Type A Variables, Item II.3

• • = Reg. Guide 1.97, Rev. 3.

- QA requirements categories 1,2 and 3 showa la Sectica 2.3.3.A.5 N/R - Not Required N.C.P. e No Specific Provisico Rev. 8 Date 4/1/95 4 s

e.

-J TABLE 1 COMPARISON OF PORF CAIJ100N STATION tRIIT NO.1 IiWTREEWffATIN HITH RE0UtATC9Y GUIDE 1.97 REV. 2 RfTUIRDECJTS TYPt "B" VARIAB12S POWER SEIS QUAL. REDUlW. EUPPLY RECORDING DISPEAY IACATION C00stDrfs TMSTRtReff Eg ' RANGE ENV QUAL.

!!! MAINTAINING REAC103 r00tAlf? SYSTDP INTEGBITT

'0-4000 psig CAT.1 R.G. 1.100 REQUIRED 12 Required One Channel Continuous

1. RCS Pressure R.G. 1 -

OPPD See Type A variables, Itse !!.2 SusR,{0-32") CAT.2 N.S.P. N.S.P. Highly Reliable Eequired on Demand Je.Cantainment susp 3.0. 3 -

CD, $108 In Comp?1ance 0737 10CFR50.49 IEEE-344-75 TES It Recorded Meter level 'CFPD 0737 5 - 37 in.

- (Narroel (LT-599, 600) 0-600,000 Gal. CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous 2b. containment sump 3.G. 1 -

In Compliance IEEE-344-75 YES 1E Recorded CR, SPDS Water Imvel (N1Je) OPPD 0737 0737 0-600,000 Gal. 10CFR50.49 (LT-347 A/8/C/D (0-27.5 ft.)

LT-380 A/B/C/D).

R.G. 1.100 REQUIRED IE Required One Channel Continuous In Compliance

3. Containment R.C. 1 - 0-D.P. CAT.1 195 psig 10CFR50.49 IEEE-344-75+ YES 1E Recorded CR, Sits Pressure OPPD 1 USAR (PT-783, 704)

IV MafirrAINING CONTAIIserf INTErAITV R.G. 1.100 REQUIRED lt N/R On Demand See Sectico 5.2.1

1. Containment -' 3.G. 1 - Cisd/ Mot C1sd CAT.1 Isolation Valve See list belows those Conta1 ament Isolation Valves which close upon Poettien receipt of CIAS (Tontainment Isolation Actuatico Signal")

~

• = The entire loop is not qualifted te IEEE-344-1975, only the sensors are qualifted.

- QA reparemente categories 1,2 and 3 shown la Section 2.3.3.A.5

. W/R - Not Required N.S.P. e No Specific Provision Rev. 9 Date 4/1/R5

(-

e l

TAB 121 COMPARISW OF PnNT CAIJf00N STATIM UNIT NO. I g

INTRIEWrfATION MI'of REGUIATORT GUIDE 1.97 REV. 2 REQUIRDENTS TYPE *B" VARIAE!2S PWER ,

INSTRO Wff CAT g g RANGE ENV ODAL. SEIS '41A1 REDue. SUPPLY RECORDING DISPtAT IACAff0N . C0f0G3rTS IV e rprArutNo CourArmeNr garrer3!TT (Coettause)

A. PCV-742 A/C/E/G 1 USAR Cisd/Not C1sd 10CFR50.49 IEEE-144-75 TES* IE N/R CD, SPOS In Compliance 5.' PCV-742 B/D 1 USAR Cind/Not Cisd 10CPR50.49 IEEE-344-75 TES* lt N/R O ,SPDS In Compliance C. PCV-742 F/M. 1 CSAR Cisd/ Mot C1sd 10CFR50.49 Original Plant TES* IE N/R O , SPOS See 5.2.1 D. NCV-7M A 1 DSAR Clad / Mot C1sd' 10CFR50.49 IEEE-344-75 TES* IE N/R O ,SPDS In Compliance E. NCV-7M S 1 USAR C1sd/ Mot C1s4 10CFR50.49 Original Flent TES* 1E N/R O. S106 See 5.2.1

~

F. NCV-425 A/C '1 USAR C1sd/ Mot C1sd 10CFR50.49 IEI2-344-75 TES* 1E N/R O , SPDS In Compliance C. MCV-425 3/D . 'l USAR Cisd/Not C1sd 10CFR50.49 Oristaal Plant TES* .1E N/R O , SPDS See 5.2.1 C". NCV-467 A/C 1 USAR- C1sd/ Net Cind 10CFR50.49 IEEE-344-75 TIS * . 1E N/R O , SPDS In Ceay11ance 9 = Nith the exception of theos penetrettees which are esempt from the requireamet of doete isoletten (Ref. USAR Sectica 5.9.51 all mechanical penetrations are provided with two leelettoa valves.,

N/R - Not Required '

' Rev. 8 Date 4/1/85

.e TABLE 1 CragrARISCN OF PORT CAIJI0tEs STATION UNIT No.1 INSTRIBGarrATICEI WITH REGUIATORY GUIDE 1.97 REV. 2 REQUIRIBEENTS TYPE *B* VARIAR!JR 1NSTRis.3387 . Eg Rh 1 238V QUAL. SEIS ODAL. REDUle. SUPPt,Y EilCOf0TNG DTSPEAY IDCATIch Om IV MAfMTAINING CONTATIser?

, INTEGRITY (Continued)

!. IeCV-447 R/D 1 'USAR C1sd/Not C1sd 10CFR50.49 Or19 anal Pl=et YES* lt N/R CR, SPDS See 5.2.1 l

.: J. NCV-500 A/8 1 USAR . lad /Not Cisd 10CFR50.49 Original Plant YES* IE N/R CR, SPDS See $.2.1 L

F ' HCV-506 A/B 1 USAR C1sd/Not Cisd 10CFR50.49 Original Plant YES* IE N/R CR, $105 . See 5.2.1

- L. ; HCV-507 A/S 1 USAR C1sd/ Mot Clad 10CFR50.49 Original Plant YES* IE - N/R CR, SPDS See 5.2.1 C. HCV-50S A/B 1 USAR Cisd/Not Cisd 10CFR50.49 ;alginal Plant YES* IE N/R CR, 530S See 5.2.1 N. MCV-509 A/B 1 USAR Clod /Not Clad 10CFR50.49' original Plant YEE* IE N/R CB, SPDS See 5.2.1 C. TCV-202 1 'USAR Cisd/Not C1sd 10CFR50.49 IEEE-344-75 'YES* 1E N/R CR, SPDS la Compliance P. HCV-204' i ffSMt risd/Not C1sd 10CFR50.49 Griginal Plant YI58 1E N/R CB, SPDS See 5.2.1 1 USAR ' C11d/Not C1sd .. 10CFR50.49 IEEE-344-75 YES* 1E N/R CR, SICS la Compliance Q.'HCV-241 l

eL Nath the exceptico of those penetrations which are exempt from the requirement of double isolation (Ref. USAR Section 5.9.5) all mechanical penetrations are provided eith two isol: tion valves.

'N/R - Met Pequired

- Rev. 8 Date 4/1/05

4

)

I TABLE 1 '

COMPARISCIf 0F F0WT CAUE0tNI STATION 3877 NO.1 LIEITIltBIDrtATICN WITH REULATJRY GUIDE.1.97 RLY. 2 REQUIRDerTS trPE n vARrAst.ES POMB CosequerS IMBTRtSIDff gg CA RANGE INV QlRL. . SEIS QUAL. PIDUID, S'fPPLY RecokDING CTSPtAT tKAf t0N IV HAINTATWING CCBffATIAIENT lhikTmITY (Continuedi R. MCV-2tn 1 USAR C1sd/ Mot C1sd 10CFR50.49 Original Plant YES* IE N/R O , SPDS See 5.2.1 S. ' HCV-13a7A,1380A 1 .USAR Cisd/Not Cisd 10CFR50.49 IZEE-144-75 YES* IE N/R CB, SPDS la Compliance

- T. 'IICV-1387B,13888 1 USAR C1so/Not C1sd 10CFR50.49 Original Plant YES* IE N/R CR, SPDS See 5.2.1 l

. U. MCV-1385, 1386, 1 USAR C1sd/Not C1sd 10CFit50.49 ottginal Plant 10 0

• It h/R O ,SPDS See 5.2.1 NCV-1749, PCV-1849 V. NCV-1559 A/S 1 USAR Closed /Open 10CFR50.49 ' Original Plant' YES* IE N/R O ,SPDS See 5.2.1 NCV-1560 A/8

t. HCV-2603A, 2604A 1 USAR ~ Closed /Open 10CFR50.4? Original Plant 713

• IE N/R CR, SPDS w e 5.2.1 HCV-26038, 26048 - Closed /Open 10CFR50.49 IEEE-344-75 YES* IE N/R CR, SICS In Ccumpliance X. 1 USAR

. Y. NCV-25044, 2506A 1. USAR - Closed /Open 10CFR50.49 IEEE-344-75 YI5* IE N/R CR, SPDS In Corp 11ance HCV-2507A Closed /Open.- 10CFR50.49 IEEE-344-75 TES* 1E N/R G , SPCS In Compliance

3. HCV-25048, 25068 1 USAR HCV-25078

- ? ::ith t!.e exceptius .I ' -

ruu=issilena ='a ida ese esempi ison the seguisemeni ei einuble inviolium (Lei. UStin 5=dian 5.5.5, all med =iwi y is ii e. . y. id=4 .iin i==

1so1Ltion valves N/R = Not Required Rev. 8

• Date 4/1/85

e w s e

4

'?

L TABLE 1 CtBIPARISCBf OF 70RF CA!JtotBr STA?!(3f IMIT NO.1 IIETRLBIENTATICII WI118 REQUIA1t*Y GUIDE 1.97 REY. 2 REQtTIRBIENTS 4

TYPE "B" VARIABIJS POWER 1 lamTiiiiiiDi? ' Eg ' RANGE ENV ODAL. SEIS QUAL. REDERO. SUFitY RECOECING DISPEAT 14 CAT 10N - COBSGNr$

IV _ NArNrArNzMG CONrAnanNr f

, INTEGRITY (Continued) .

AA. NCV-0204, 821A 1 USAR Closed /Open 10CFR50.49 IEEE-344-75 YES* IE N/R O , SFOS la Compliance RB. NCV-8208, 8218 1 USAR Closed /Open 10CFR50.49 I M -344-75 YES* IE N/R O ,SPDS In Compliance CC. NCV-881, 802 1, USAR Closed /Open 10r7p50.49 IEEE-344-75 ND* IE N/R CR, SPDS la Compliance

- DD. NCV-40(A/B/D ' 1 USAR , Closed /Open 10CFR50.49 IEEE-344-75 M* 1E N/R CR, SPDS fa Compliance NCV-401A/8/D NCV-402A/S/D NCV-403A/9/D 'E l

. EE. NCV-400C _1 USAR Closed /Open 10CFR50.49 Original YEB* IE N/R C), SPDS See 5.2.1 I

, NCV-401C . Plant NCV-f.02C NCV-403C FF. NCV-438 A/C 1 USAR Closed /Opeo .10CFR50.49 IEEE-344-75 YES* 1E N/R CR, SPOS In Compliance OG. NCV-438 B/D - 1 USAR ~ Closed /Open 10CFR50.49 Original Plant YES* IE N/R CR, SPDS See 5.2.1 T

e - Nith the exceptica of those penetrations shids are cuenyt from the requirement of doele isolettee (Ref. USAR Sect. 5.9.5) all mechanical penetrations are provided eith redundant 1 sol:tlen eelves

- C/R - Not Required (

/'

L f

l Rev. 9 i Date 4/1/85

f '

i

+

w

{

e

=

TABLE 1 COMPARISON OF FORT CAtJI0t38 STATION IRIIT NO.1 IlWTRIBIDffATIQt MIT1f RENLATORT GUIDE 1.97 REV. 2 REQUIRDIENTS TYPE *B" VARIABLIS PON13t TMSTRIBWlf Jg CA RANGE - ENV CUAL. SE!S QUAL. REDOIO. SUPPLY RECCIIDING DISPEAT IDCATIost COB 9tDffS IV HA!NTAINIIIG C(3f?ATIBIDff INTEGt!TY (Continued)

Iss. IICV-883A 1 USAR Closed /Open 10CFR50.49 IEEE-344-75 TES* IE N/R CR, Sits Fe compliance HCV-984A

.II. IfCV-8838 1 USAR Closed /Open 10CFR50.49 trFE-344-75 TES* IE N/R CR, Sits la Compliance NCV-8848 JJ. NCV-1107A 1 USAR Closed /Open 10CFR50.49 IEEE-344-75 TIS

• IE N/R CR, SICS In Compliance IICV-1108A EA, isCY-11Q)3 1 USAR Closed /Open '10CFR50.49 IEEE-344-75 TES* IE N/R CR, SICS In Compliance

. MCV-11004 LL. IICV-2903 1 USAR Closed /Open 10CFR50.49 ORIGINAL N0* 1E N/R CR, SICS See 5.2.1 PtANT set. leCV-741 1 USAR Closed /Open 10CFR50.49 IEEE-344-75 N0* IE N/R CR, SPDS In Compliance A/8/C/D

'2.L Cont?inment R.G. 1 - 10 psta-D.P. CAT.1 R.G. I.100 REQUIRED RE Itequired One Continuous Channel

i. Pressure OPPD See Type B variables, Ites III.3 e

• utth the euroption of those penetrations which are esempt from the requirement of double isolation (Ref. USAR Sect. 5.9.5) all mechanteel penetrations are provided with redundant

.1 sol:tico valves

- QA requirements categories 1,2 and 3 shown in Section 2.3.3.A 5.

N/R - Ilot Required Rev. 8 Date 4/a/85 a

y e

'?

TABLE 1 COMPAR190N OF PORT CAIEOUN STATION t! NIT NO.1 INS 11t3GNTATIGi MITH REGUIATORY GUIDE 1.97 REV. 2 REQUIRDtENTS TYPE 'C" VARIABLES PONER -

1 INSTRIBEINT gg RANGE INV QUAL. SEIS QUAL. RIpotD. SUPPLY RK:0RDINf3 DISPIAY LOCA?!ON ColetDrTS rUtr. ctAreING

1. CET 3.G. 1 - 200-1650*P CAT.1 R.G. 1.100 REQUIRID IE N/R One Continuous Channel OPIO See Type A Variables, Iten III.3

2. RadioactivitF R G. I *- T.S.-100 T.S. CAT. 1 R.G. 1.100 REQUIRED IE N/R One Channel Continuous- See Note 1 Concentration - OPPD 0737 0737 %7.5.-100 T.S. 0737 Not Applicable None Non-Class AI-194 L2 primary coolant (.5pC1/cc-100y (SL-16,401 C1/cc)

3. Analysis of R.G. 3 - 10pC1/st-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/al-10C1/m1** AI-194 (Gamma Spectrie)

(SL-17 Grab Samples)

II REACTOR COO! ANT PRESEURE ter4sDARY

f. IICS Pressure R.G. 1 - 0-4000 psig CAT.1 ' R.G. 1.100 REQUIRED IE Eequired One Channel Continuous OPPD See Type A Variables, Ites II.2

2. Contr.inment Pressure R.G. 1. - 10-DP psia CAT.1 R.G. 1.100 REQUIRED 1E Required One Channel Continuous OPPD See Type B Variables, Iten III.3 3a.C a t:1 ament Se p R.G. 2 - Sump, 0-32 in. CAT.2 N.S.P. N.S.P. Highly Reliable . Required Cn Demared Natir Level OPPD (Narrow) See Type B Variables, Itse III.2a Mot 31 - The PASS gross gamma detectors will be used as en line monitors for radioactivity and gamma spectrum analysis of RC samples in lieu of the Rad. Moottor en the letdown 11ae.

This monitor cannot be used since the letdown line is isolated in an accident. The gross gamma detectors are fully que11fied to NURIG-0737 and can measure RC, LPSI and sump.

- QA requirements categories 1, 2 and 3 shown in Section 2.3.3.A.5.

N/R - Not Required

• e'- Reg. Guide 1.97, Rev. 3 Requirement C.S.P. = No Specific Provision Rev. 8 Date 4/1/85

c.

.e L

f w

~. .3

^

TAM.E 1 Ct39RB1bOIf GP FORT CAIJI0tst STATIM UNIT NO.1 TNATIC01 ti1TH RE,2TIATORT CEIDE 1.97 REY. 2 PEQUIREBIENTS TTFE V VARI)BLIS

• POWER INSTREDIENT . CAJg RANGE INV QUAL. Sets Qt!AL. REDERS. SUPf'LT RECORDIN3 D!$PtAY IDCAf?00f ColetDrFS II REACTOR C00 TANT PRESSURE Rneram? (Continued) ,

3b.Coetziament Sump 3.G. 1 - 0-600,000 ga!. CAT.1 R.G. 1.100 FEQOIRED 1E Required One Channel Continuous Noter lavel CF'D ' See Type 8 Variables, item III.2b (Tidal

4. Cantalement R.G. 3 - IR/le-10$/MR N.S.P. N.S.P. N.S.P. N.S.P. Required Continuous In Compliance Area Radiatice OFFD 3 USAR .1mR/HR-107 aR/M Recorded CR (150-010 thru 075)

5. Efflueet 1.G. E' = 10*6p C1/cc= N.S.P. N.S.P. N.S.P. N.S.P. Required on Demand la Comp 11aw.e Radioactivity 10 8p C1/cc Hob 13 Gas , OPPD 3 USAR . 10[6p C1/cc- Recorded CR

.(310-057) 10 ap C1/cc 4

COISENSER OPP GAS -

!!! C0ertATIBIENT

1. RCS Pressure R.G. 1 = 0-4000 peig CAT.1 R.G. 1.100 REQUIRED 1E Required Continuous OPPD See Type A Variables, item !!.2

2. Contalemen*. R.G. 1 - 0-10%' CAT.1 R.G. 1.100 REQUIRED IE Required One Channel Coatinuous'

'C Concentration OPPD ' See Type A Vertables, Item IV.1

= Q requirements categories 1, 2 and 3 sheen to Section 2.P.3.A.5.

N.S.P.

• No Specific Provision Rev f Date 4/1/85 g -

I ,

i

.e TABLE 1 COMPARIS(310F PORT CAIJt00N STATION UNIT No.1 ItWTRESSITATION WITK REGutATORT GUIDE 1.97 REV. 2 REQUIRDIDffS g,

TYPE *C" VARIARIJS POWER IlWTRtself . Eg . RAst;E ENV QUA',. StiS GIAL. REDtam, SUFPLY RECORDI M DISPfAT I4 CATION COISIENTS III CONTAttReff (Continued)

. 3. Cont:1 ament R.G. 1 - 10-3sD.P. pela CAT.1 R.G. 1.100 REQUIRED 1E Required (me than-1 Continuous in Compliance Pressure OPPD 0737 0737 195 peig' 10Cf1t$0.49 IEEE-344-75+ TES 1E Recorded CR, SPDS

.(PT-783, 764)

4. Containment R.G. 2 -

10M1/cc- CAT.2 N.S.P. N.S.P. Highly Reliable Required On Desand .

10 apegfee

' Effluent Radio- '

. activity (Noble OPPD 0737 - 0737 10*6pC1/cc- 0737 Non-Class Recorded ~ CR In Compliance Gases) 105pC1/cc (III-063)

5. See Not3 1

6. Effluent Radio- R.G. 2: - 10~6 pC1/cc- CAT,2 N.S.P. N.S.P, Highly Reliable Required on Demand activity (Auz. '

10hC1/cc Bldg.) - OPPO 0737 0737 10~6p egfee. 0737 Non-Class Recorded CR !a Compliance (MI-063) 105pegfee L

6 - The entire loop is not qualitted to IEEE-344-1975, only the sensors are que11f te3.

- p requirements categories 1, 2 and 3 shown la Section 2.3.3.A.5.

. Isote la Reg. Outdo 1.97, Rev. 3 deleted requirement for " Radiation Exposure Rates (1aside buildings or areas la direct contact with containment penetrations

. er hatchwers)*

C.S.P. e No Specific Provision

- Rev. 5 Date 4/1/85

- ' _._.n____ - - . . -

e-e TABLE 1 CtslPARISON OP FOIrf CA!J000K STATICII tBlf? MO.1 INSTRIBEDrrATIOtf MITH REGURAKIRT GUIDE 1.97 REV. 2 FEQUTpperfS TYPE "D" VARIABIJS PONER DV QUAL. SEIS QoAL. Isotac. SUPPLY RECORDING DISPEA7 IDCATION C0petDrr$

lassTRtser? CA g J- ,R_ANGE 1 RESIDUAL MEAT RDIDVAL SYST55 1,RHR Systee R.G. 2 -

0-110% D.P. CAT.2 W.S.P. N.S.P. Highly peliable N/R On Cesand See Section 5.4.10, 1 S,2.4

- Vla w 'OPpD -l

2. Esot Systee 3.4. 2 - 40-350*F+ CAT. 2 N.S.P. N.S.P. Nighly Deliable N/R On Demand See Section S.4.10,  !

- NI outlet Tem p. 6.2.5 l II SAFFTY INJECT!tal SYSTBIS

, la.S. I. Tank tavel , R.G. 2 .- 10 b904 CAT.2 N.S.P. N.S.P. Nighly Deliable N/R . On Demand I - (LT-2904, 2924, OPPD 2 USAR 0-100% Commercial Non-Class CR, SPDS See Section 5.4.1 2944, 2964) Grade 4 8.1. Tank Pressure R.G. '2 - 0-750 poig CAT.2 N.S.P. N.S.P. Nighly peliable N/R On Demand (PT-2901, 2921, OPPD 2 USAR 0-300 pelg Commercial' Non-Class CB, SICS . See Section S.4.2 mi, m1, Grade 1

2. S.I. Tank Isolstica R.G. ~2 - Open/ Closed CAT.2 N.S.P. N.S.P. . Highly peliebte N/R On Demand in Compliance

- Valve Poettloo OPPD. 2 .USAR Open/ Closed 10CFR50.49 Class 1E CD, SPDS See Section 2.3.3.8 (NCV-2914, 2934 2954,2974)

. 3. Seric Acid R.G. 2 - 110% D.F. CAT.2 N.S.P. N.S.P. Nighly Deliable N/R On Dreand Charging Flow OPpc 2 USAR 0-140 gpa Commercial Non-Class CR, SPDS In Comp!!ance (PT-236) 0-117% D.F. Grade *

• - Dog. Guide 1.97, Dev. 3

-N/R - Not Dogstred

- On requirassets categories 1,2 and 3 shown in Table 2.

.* It is located la a114 environment and is esemot from 10CFR50.49 as discussed la Sectiers 2.3.3.A.1 and 2.3.3.8.1.

% S,P. m No Specific Provistco

+16- Dev. S Data 4/ t /815 =g

__ _ _ _ _ . _ _ _ _ _ _ = . _ . - - -

F 1

l e

(. - 8

, ' ,e TABLE 1 CUNPARI.90N OF PORT CAIJer438 STATION 1Rf!? MO. I fl5TRt94NTATI0tt Mf'4 REGUIA70RY GUIDE 1.97 REV. 2 REQUIRUENTS TTPE "D" VARIABLES PONER INETRWIBff lg CA RANGE INV QUAL. SETS QUAL. REDel@. _SUP]PL REC 090fMG DISPLAY ICCATI0tt COISEDrFS III SAFETY Ytk1ETICII SYSTBtS (Continued)

4. Floe I3 NPSI R.G. 2 - 0-110% D. F CAT.2 N.S.F. N.S.P. Highly Reliable N/R On Demar.d (FT-313, 116, OPPD - 2 USAR 0-300 gpa 10CFR50.49 IEEE-344-75+ II CR, SPDS In Comp 11an e 31.), 322) (0-11M)

5. Flee 12 LPSI R.G. 2 - 1104 CAT.2 N.S.F. N.S.P. Nighly Reliable N/R On Demand (PT-328, 330, OPPD 2 USAR 0-1500 gpe ' 10CTR50.49 IEEE-344-75+ 12 CR, SPOS Ia Compliance 332, 334) (0-11 % I

4. SIRMT Level R.G. 2- - Top to Botton CAT.2 M.S.P. N.S.F. Eighly Reliante N/R On Demand (LT-L*1, 1823 Orm 2 USAR Top to Botton 10CFR50.49 Non-Class CR, SPDS In Compliance (LT-382 Not On 5105) .

IV PRIIIART C00tAlff SYSTDI

1. RC Pump Status R.G. 3 - Meter Current .N.S.F. N.S.F. N.S.F. N.S.P. N/R On Demand (Y-3268, 3269, .OPPD 3 USAR 0-4200EN CR, SPDS In Compliance 3270,3271)-

2. Primary System R.G. 2 .- Closed /Not, CAT.2 N.S.F. N.S.F. Nighly Rentable N/R On Desand Relief Valve Positica Closed (PORV) or Floe OPPD 2 0737 Flow Through 10CFR50.49 IEEE-344-75+ YES CR, SPDS In Compliance Through (FT-141, (accousttel 142) (F102-1, 102-23

3. Pressurtser level R.C. 1 - Rottom to Top CAT.2 R.G. 1.100 REQUIRED 1E Required One Channel Continuous OPPD See Type A Variables, 1(em II.1 N/R - Not Required o

• The entire loop is not gia11f ted to IEEE-344-1975, only the sensors are qualified.

- C1 requirements categories 1,2 and 3 shown in Sectica 2.3.3.A.5.

C.S.P. e Ito Specific Provision Rev. 8 Date 4/1/85 j

. . _ _ ,m . __ _ _ _ . . _ . . . . ._ _. . _. . , . _ ._ . , _ . ...4 - .

. g.

+

Q w

-s _

TAat2 1 CtseARISON OF PORT CAIJ10tEl STATION E3117 NO.1

. IISTMBeffATION WITN REGULATORY GUIDE 1.97 REV. 2 RE0tTIRBENTS TTPE "D" VARIABLES POND SEIS COAL. REDEND. SUPPLY RECORDING DISPLAY 1DCATI0er ColetENTS 4

INBTRuimff Eg RANGE ENV OIRL.

IV PRtesARY C00tAlff SYSTM (Comtlausd)

- Electric Current CAT 2 N.S.P. N.S.P. Nighly Reliable N/R On Demand

4. Pressurtser Noeter . R.G. 2 4.

TES Non-Class CR, SPOS in Compliance ,

Status OPPD 2 USAR 0-900KW Commercial ,

(T-32721 Grade **

Top to Bottom N.S.P. N.S.P. N.$.P. N.S.P. N/R On Desand

5. thench Tant Invel R.G. "3 -

CR, DP, S7OS la Compliance

- (LT-132) OPPD 3 USAR Top to Botton 50-750*P N.S.P. N.S.P. N.S.P. N.S.P. N/R on Demand See Sec. 5.4.3 and i 6 9mench Tank Twp- R.C. 3 -

0-300*FICR)

CR,' SICS Sec. 6.2.1 ature OPPD 3 USAR (TE-133) 50-750*P(SPDS)

O to D.P. N.S.P. N.S.P. N.S.P. N.S.P. N/R On Demand See Sec. 5.4.4

7. (hench Tagg 3.G. 3 -

la Compliance CR, SPDS '

Pressure CPIV ' ,3 USAR 0-25 peig ,

(PT-131) (0-100 psig)*

SKOISARY SYSTDI R.G. 1.100 REQUIRB lt N/R One Cbannel Continuous

1. Steam Gomerator R.G. 1 - Tube Sheet to CAT.1 tevel Separators OPPD See Type A Variables, item III.6 N.S.P. N.S.P. Righly Reliable N/R On Demand

2. Steam Gomerator R.G. 2 - 2C4 Above Imuset CAT.2 Pressure Valve Setting OPPD See Type A Variables, Itas 11I.7 N/R - Not Required

- G requirements categories 1,2 and 3 shows la Sectice 2.3.3.A.S.

8 Proposed Range

• • - It is located is allo environment and is esempt from 10CPR50.49 as 'iscussed in Sections 2.3.3.A.1 and 2.3.3.3.1.

' O.S.P.

• No Specific Provision Re.. .

Data 4/1/M

e ,

- m y

e.

. ' ,^

_ *anLE 1 ORIFRRISGI 0F 70NF CAUIDIRB STAT!GB tudIT NO. I -

INSTRWEDr!ATIai NITH REGCIATCRT GUIDE 1.97 REY. 2 REQUIRINulTS TTPE '9" linRIABLES 7GIER

{WTREWff E g- haAAme EfW QUAL. SEIS M . RBERS. SUPPLY RECO SING DISP 1AV IDCATICII d)esqENTS

.- 7. SKOISARY STSTIdt (Centtamed)

3. Relief Velve R.G. 2' -

Clod /Isot Clod CAT.2 N.E.P. REQUIR E P4ghly Reliable N/R On Dunand

. Posities ,,

135-291,292) 0FFD <2 DEAR Clad /Not Clod 10GR90.at IEEE-344-75 NO 1E CR in Cey11ance

4. Mn12 Paedenter -3.G. 3 -

, 0-110% 0.P. N.S.P. N.S.P. N.S.P. N.S.P. Required On Demand Flee to Compliance

' (PT-1101, 1102) .OrrD s WEAR 0-11M g.P. Recorded CR, SPDS (0-4s10 lbe/hr)

VI AtlI PEW S TER

1. Aus resenter .R.G. 2 - 0-1106 D.P. CAT.2 N.S.P. N.S.P. Nighly Reliable N/R on Demand Flee . OPPD 2 WEAR 110% D.P. . 10CFR50.49 .IEEE-344-75+ YES Nighly peliable CR, SPDS In Compliance l IPT-1109, 1110) (0-300 gpol

' 2s.Camdensate Storage R.G. 3' - Plant Specific ' N.S.P. N.S.P. .N.S.P. N.S.P. N/R On Demand la Comp!!ance i Tank IInter Insel LOrrD 3 IISAR Top-Rotton Commercial Grade. CR (LT-11:13 4 .

an.Restgency Pend- 3.G. 1- .- Plant Specific CRT.1- R.G. 1.100 REODIRB - 1E poquired One Contanuous t h amel ester Tank tevel OffD 1 , WAR 0-160* 10CF350.49 , IEEE-344-75+ YES 1E SPDS CR, SPDS In Compliance

, (LT-1183, 11083 -(0-2004)

.. VII CEufrAIIONET COOLING Sisres I 1. Com*ai====t Spray . R.G. 2 -

0-1104 D.P. . CAT.2 N.S.P. N.S.P. Nighly Reliable N/R On n==aaA

. Ploe . OPPD 2. ESAR 5000 gas' Comercial YES Nighly Reliable CE, SICS In Compliance (PT-342,343) (0-110% D.P.) Grade

• N/R - Not Required

• = The sottre toep is met goalified to IEEE-344 1975, only the eensers are goalif ted.

l - @ requirements estegories 1,2 and 3 sheen to Secties 2.3.3.A.S.

• = It is located to a114 envircommet and is esempt from 10CFR50.49 as 41oceased to Sectices 2.3.3.A.1 and 2.3.3.R.1. This device otti perform its intended function

,. prior to its entiremment betag const hred a har

h envircuacat.

5".S.P.

• IIe Specific Provistem i - _Rn. .g. , ,

p --

e

!4 l

i h

TARLE 1 CIBIPARIS(BI OP PORT CALHOUN staff 0N 1RITT NO. I DWTRERWITAff0N MITH RECUTJTORY GUIDE 1.97 REV. 2 ItEQtTTRENDFFS

_TTFT "D" VAAtABLES PONER

'llSTRIBerr CAT

_g g RANGE BfW QUAL. SETS QUAL. REDU 2 SUPPLT RECORDYNG CISPtAT 14 CAT 10N C0ghtDirS VII CONTA!WIDrr COOLING SYSTDes (Continued) -

2. Reet Removal ty, the R.G. 2 - Plant Specific CAT.2 . N.S.P. N.S.P. Highly Reliable N/R On Demand In Compliance Contatament Fan' OPPD 2 USAR 0-2500 gge 10CPR50.49 IEEE-344-1975 Class IE EPDS, CR (FT-416, 417, 418, 4193

3. Containment R.G. 2 - 40-400*F CAT.2 N.S.P. N.S.P. Righly Reliable N/R on Demand See 5.4.5, 6.2.3 Atmosphere OPPD 2 USAR 0-430*F Commercial Non-Class SPOS Temperature Grade ITE-714, 716, 718,7203

4. Centainment Sump B.G. 2 - 50-250*F CAT.2 N.S.P. N.S.P. Righly Reliable N/R on Demand See 5.4.6 Nater Temperature OPPD (N O I N S T R U N E N 7)

VIII CNDefrAL Age 90Lipst CONTROL

1. Nakeup Flow R.G. 2 -

0-110% D.F CAT.2 N.S.P. N.S.P. Highly Reliable N/R On Demand OPPD See Type D Wariables, Item !!.3

2. Letdown Floe P.G. 2 - U-1104 p.F. CAT.2 N.S.P. N.S.P. M;gity Reliable N/R Co Demand (PT-212) OPPD 2 USAR 0-1104 D.F. Commercial Non-Class CR, SPDS See 5.4.8 Grade

3. Volume Centrol R.G. 2 - Top to Botton CAT.2 N.S.P. N.S.P. Righly Reliable N/R On Demand Tank h vel OPPD 2 USAR 0-100% Commercial Non< lass CR, SPDS See 5.4.9 (LT-2193 Grade N/R - Not Required a Ch requirensets categories 1,2 and 3 shown la Sectice 2.3.3.A.5 N.".P.

• F.o *witis Fessestatica Rev f teate 4/1/85

t j

TABLE 1 COMPARISON OP PORT CAIROUN STATION 381T NO.1

(

flSTRWWITATICBf MITH REGULATCRT GUIDE 1.97 REV. 2 REQUIRENENTS TYPE *t" VARIABLIS 4

POWER IISTRtssur 'CAJg . RANGE BfV QtRL. SEIS QUAL. REDSS. SUPPLT RKORDING DISPtAT (ACATION CoggsgrTS EV . CODLING NhTER SYSTEN 40-200*P++. CAT.2 W.S.P. N.S.P. Highly Reliable N/R On h====A

1. Campement Coeltag R.G. 2 -

2 OSAR 0-300*P Commercial Non-Class CR, SPDS la Comp 11ance

. tenter Temperature , OPPD

. (TE-2000) Grade **

r

2. Cet Coottog R.C. 2 - 0-110% D.P. ' CAT.2 - N.S.P. N.S.P. Nighly Reliable N/R Ca Desand 0-110% D.P. Commercial Non-Class CR, SIVS In Ccap11ance Mater Ploe ' OPPD 2 USAR (FT-494) (0-10,000 gun) Grade **

i I RADWASTE SYSTSE

1. Nigh Level Rad. R.G. 3 - Top to Bottom N.t P: N.S.P. N.S.P. 16. S. P. N/R On Demand i

Ligs14 Teak level 0FFD 3 USAR Top to Botton Commercial Non-Class A1-100, SPDS la Compliance l

(LT-577, 578, 579)

2. Red. Gas leolor:p R.G. 3 - 0-1504 D.P. N. S. P N.S.P. N.S.P. N/R On Demand Tank OPPD 3- DSAR 0-1504* D.P. NO Non-Class AI-100, SPDS See 5.4.7 and 6.2.2 (Py-517,518, 519, 520)

II VENrt1ATIN SYSTEMS

1. Emergency . R.G. '2 - Open/ Closed CtT.2 N. F.P. N. S. R Highly Reliable N/R On Demand

! Vent 11atten Open/ Closed 10CPR50.49 IEEE-344-75+ 7ES Iloo-Class CR, SPDS In Cay 11ance l

Damper Positten OPPD 2 USAR l- ' NCV*724 A/B

- IICV-723 A/B NDTE 1 - Castainment Vesttaation Systems were cameldered caly.

• - Proposed range modificattoa.

l C/R - Isot Required l . - O requirements categories 1,2 and 3 shoue la Section 2.3.3.A.5.

l + = The sottre Imp is not qualified to IEEE-344-1975, caly the sensors are qualified.

! ** - It is located in a114 environment and is exempt from 10CFR50.49 as discussed in Sections 2.3.3.A.1 and 2.3.3.3.1. This device will perform its intended function prior to it's environment blong considered a harsh environment.

++ - Reg. Guide 1.97 Rev. 3.

N.S.P. e No Specific Provision '

.Rev. 6.

~ . . . ~ . .- .. . . - . _. -- . - . . ~ _ . ~ . _ ~ . - - , - - - . n. , . .

'i h  !

l

• TRALE 1

. MISCII 0F 70pr rarmnig gTAff0N WIT NO.1

- INA?!M 51111 RRW1ATORY GlIDE 1.97 IIEV. 2 RE(NIIM TYPE "D" VAP! ABLES POWER [

IISTRERWIF CAT g RAIIGE . ERf QuL. . SEIS QUAL. REDIRC. SUFFt? RECCISING DISF1AT 14 CAT 1011 CCIONNFS III 70N B SUFFLIEE

1. Status of Staaey . B.G. 2 - Plant Specific CAT.2 N.S.P. . N.S.P. Nighly Reliable N/R on Demand feuer. l OrfD 2 USAR- Volts, sups, _Ilote 1 1E N/R Castrol Room la Compliance.

.c. 4kUAC buses watts CPfD 2 , USAR . . Volts, amps, Note 1 1E N/R Control Room In Compliance +

b. 400VAC 1mses

~

USAR- Volts, amps Note 1 1E N/R Control Room In Camp 11aace

c.125 VDC buses 0FFD 2 OrfD ' 2 - USAR - Volts (alare Ilote 1 1E N/R Control Room la Compliance

4. 120URC h =

(Vits! bus only) leverters)

.OrrD Volts, amps, . Note 1 1E N/R Control Room in Compliance

e. B G Statua 2 USAR watts SPDS

f. S G speed 0FFD 2 - USAR. rye - Note 1 1E N/R Control Room in Compliance

, ' g. 2;n 13 UFS (W 0 INDICATION I$ PR0VIDEDI t

9

' N/R = Ilot Respaired -

. - @ requireemets categories 1,2 and 3 shous t's Secties 2.3.3.h.$.

IIste 1 - This is lacated la a alid easireement and is therefore escluded from the scope of 10CFRSO.49. .The equipment, however, oests the quellfication requiremente as they applied at the q

. time of 1ssue of construction permit and therefore seets applicable requirements for a elld environment.

> C.S.P. e IIe Specific Provistan Rev. 8 Date 4/1/85

g~.

e' e

ThMZ 1 CGIPARISCBI 0F 7037 CA!Jotaf STATTON UNYT NO.1 INSTRIBIBffATIOd Milit REGutAlt*T GUIDE I.97 REV. 2 wi-._.s TYPE "E" 11hBTW on POWER IIRTRIBBFF namp SUPPLT RgrERDING 3g CA WV QDEL. SEIS QDEL. REDERO. DISP 1AT IACATTCet C0f0EDffS I Courrallece? RADIAffter

1. Centstament Aree . R.G. 1 - 1-107 B N CAT.1 R.G. 1.100 REgtrIRED 11 Dequired coe Coottonous channel Radietten CPPD S e Type A Vertables, Item V.1 Ut{"A hkpl 11 Aree Radiation

1. Dediation Imposure R.G. 3* - 10"I2 -10 N CAT.2 N.S.P. N.S.P. Righly Bettable Dequired on Demand hate CFPD ' See Type C Variables, Item II.4 III A! WOSIE RADICACTIVE IET OIALS Ref n m A. Bloble Casee ,

1. Ilebte Gesee 3.G. 2 - , 30 *E WC1/cc CAT.2 .N.S.P. .N.S.P. Righly beliable Required On Demand

~

Costu nseet 103pC1/cc_

CPfD See Type C Vartables, Item 111.4 2.' Noble Genes (PERF0EdED BT IN ABOVE)

Doector Bldg.

3. Iemble Gemen Aes. R.G. 2 -

10 M 1/cc . CAT.2 N.S.P. N.S.P. Eighly De11able Sequired on w 31de -10hC1/cc GPPD Sea Type C Variables, Item III.6

- Oh requirements cateversee 1,2 and 3 abene ta Section 2.3.3.A.S. ~

• - Seg. Guide 1.97 Sev. 3.

5.S.P. = Ito Spect!!c Provisica

=23- Rev. 8 Date 4/1/85 15 m

J '.;

9 ..

a a

e' TAK E 1 Ct3ShBIStut CF PORT CAIJIDERI STA?!QIf IRITT ND 1 INTI(NI WITH REfR11A10BY GUIDE 1.e7 MV. 3 PtQt:fkDtBfTS TYPE "E" ilhBIAM25 70MER 1m J.g CA MIE3r BN GRL. SEIS GRL. REDIRS. SUPft.Y RKORDING DISFtAT EDCATICII COIBIDrP3 III ATM ON E thDionCTIVE IlhTERIAIA m ' N R fCent M )

4. liable Gesee (DISCIlhBGE IFFtJWff TMDWEEE tmw P1AIIT VBff, TINIS WDF DEQUIRED AS PER BEG. GUIDE) t Condseeer Air Demove!

~

5. Weble Geese Caususs - R.G. ' 2 -

10 91/cc C17.3 N.S.P. N.S.P. Nigh1F De11able Dequired On Demand vest -108W1/cc ,

0r90 See Type C Variables, Item III.4

6. Vest'for S/G Safety . R.G. 2 - 10*IpC1/cc CAT.2 N.S.P. N.S.P. Nighly De11able Boquired on Demand

. he11ef Velone & -103W1/cc OffD 0737 - 0737 10'IpC1/cc .0737 Nighly Bettable Decorded ' CR la Compliance m*P

. Damp IIstve, E . -108pC1/cc (ano64 tadtreetly Poodester Turbios monitors stese (NIOS7)(NIO64) released through tbla path.)

7.' All Other Of 0 0TNER PO1NTS ABE I D E N T 1 P I E D)

Identified - s Release Potets J C. PapTICutAfgS g mar -

1. All Identitled R.G. 3 - ' 10'8pC1/cc M.S.P. N.S.P. N.S.P. N.S.P. Ilaquired On Demand Plant Delease .

• 10apC1/cc Pointa - OPFD 0737 0737 10 8pC1/cc 0737 Recorded CR in Compliance

- (30050, 060, 061, -10ayegfee

063)

- O regnareemmts categottee 1,2 and 1 sheen la sectica 2.3.3.4.5.

C.S.P. = We Specific Provistem

• 24 . Bev. 8 r

Cate 4/1/85

- e o

e-TRELE 1 messateu tw unire rauenrus stattou BNt? NO.1 IW1WMBffATIC3B UITN REGULATORT CITIDE 1.97 REY. 2 REUTTREBNNTS .,

TYPE *E* VApfABLIS PCbER IMTummer %g RMIGE INW QUkL. SETS GIAL. REDOW. SUPPLY RacnliDING CISPtAY TACATION CoggENTS IV Enytrees Radiattaa and Radioactivity

1. See note 1

2. Airterne Dedio 3.G.' 3 -

10M1/cc N.S.P. N.S.P. N.S.F. N.S.P. M/R Ca haA Nelegans and -10 8pC1/cc Particulates - 0FFD 3 USAR 10 h t/cc Continuous Deadout in Ceapliance (Partable) -10 8pC1/cc (Portable)

~

3. Plant and havirone B.G. 3 - 10 89/br N.S.F. N.S.P. W.S.F. N.S.F. N/R On Demand

. Radiation -10h/br

~

(Partable) OPPD 3 DBAR 10 8a/br coatteucus Roadout la Compliance

-10%/hr' (Portettel

4. Plant and Environs BG 3 -

Radioactivity OPPD 3 . Performed by above 1.astrummats RETE 000 TACT

1. uted Directica R.G. 3 - , 0-M0* - N.S.P. N.S.F. N.S.F. N.S.P. M/R On Demand la Ceapliance (F0031, 0032, a5*

0033, 0034, OFfD 3 USAR 0-MO* CR, SPDS 0043., 0044, e5.4*

0045)

2. uted Speed 3.G. 3 - e-47 aph . W.S.F. N.S.F. N.S.F. N.S.F. W/R Ca haA (P0035,0036, OFFD 3 USAR > SO aph CR, SPDS la Compliance 0037, 00303

- (A requireemets categories 1,2 and 3 showa la Sectica 2.3.3.A.S.

N/R - Not am paired IIDr$ 1 - Reg. Guide 1.97, Dev. 3 deleted requireemats for "Radiattom tupesure IIeters, Centlaucus !adication at Flaed Location".

__ N.S.,F. e No Specific Frevisica

-25= pov. S fW e 481/49

,L.

-(

s? m

• ~

6.

• e l

Io i

?

l o

i o i o

E N T

• U .

2 B . lj i

E II 86

}

8

}j's 8,8 8 $

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n 7 = = n m n n a a k ,a a 3-

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                                                                                                                                                              $              J
                                                                                      -             Il      23                      u a                  I"                  S a    a .!g                                        #

j3a e.t. >V3+ 3

                                                                                                                                                                             =
                                                                                                                                              -                              y 5

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                                                                                                                                     .        j          .                   j                                           -
                                                                                                   .=

5

                                                                                                           , , =

3 8 j Jl 48 4 8 & R J8 ' 8 do 48 4 8 4 8 _ 45 33 1 11 j

                                                                              ~

I i E 8e h ~ .hsl^.3 }- s,:f

                                                                                                           $2i sig E

hs 25 I

                                                                                                                                                       .a                      18 g =n: J I

3.123 joI, g.

                                                                                                           .li j-

j. , ,. ,s

s. 4 E J 4 4 4 .ad

     . _ _ _ _ _ _ _ _ _ _ . _ _ .___ _                                     _                                       _ . _ _ _                  _..             _. . _ . _ .        ._m. _ __.__ . . . _ _ _ . . _

c O d e I TABLE 1 CE394RISCW 0F Post CptJ100N STATTN 12177 NO.1 INATICIf MITH REGULA10p? CUIDE 1.97 REV. 2 REQUIRISEDFFS TYPE *E" VApramrm PONER amur:r SUPPLY pgCORDING DISPLAY IDCATION C0ggENf3 INernWWFF %g ENV QUAL. SETS 00AL. REDW O. V AccrDeur SmPLrNo CAPASILITT (Coettausd) A. PRIIIAST CODEANT & Sur (cogn

4. Chlertde Castent R.G. 3 - 0-20 ppe M.S.P. N.S.P. N.S.F. N.S.P. Required N.S.P.

(Frevided by pass) (SL-2St CPPD 0737 0737 0-20 ppe Decorded In Cem. Itance

5. Dissolved R.G. 3 - 0-2000 cc/kg W.S.P. N.S.P. N.S.F. N.S.F. M/R on Demand Nydrogen er total Gas (Provided by 0FFD 0737 0737 0-2000 cc/kg Total Gas Analysts in Compliance PASS) (SL-24) per 0737 C. Dissolved Osygen R.C. 3 - 0-20 ppe N.S.F. N.S.F. N.S.P. N.S.F. N/R On Demand District was not re-quired to provide as per 0737 II.B.3.1-2 OPIO 0737 0737 N.S.F.* requirements, and resper.se to require-meats.

7. PIs (Frevided R.G. 3 - 1-13 N.S.F. N.S.F. N.S.F. N.S.F. N/R on Demand by PASS)

OPPD 0737 0737 0-14 Deadout on Panet In Compliance

  . (PNS-4742)

AI-194

8. CONTATIBIDff AIR

1. Nydregon Centent B.G. 3~ - 0-104 N.S.P. N.S.P. ' N.S.P. .N.S.P. Sequired On Demand CPPD See Type A Variables, Ites IV.I.

e no gyseggte p.A.S.S. evt. Can Take Grab Sample and Analyre Utillstag Cheatstry Procedures - OA requirements categories 3,2 and 3 shows la Sectica 2.3.3.A.5. M/R - Not asquired C.S.F. e Me Specific Frevistem Dev. 8 Date 4/1/85

                                                                                                                                                                                             ]

m.s, .(.O'

                                                                                                                                                                                                              'O.         ,

e-o

                                                                                                                                                                                                                     .. g 1

e' TABLE 1

                                                                                       ' COMPARISW OF PORT CAIJIDWI STAT!W WI? MO.1 IIstseemuTATIN u!TR REWEATORY GUIDE 1.97 REY. 2 REQUIREIIDFFS s

TYPE *E" 4RRIAE!JS PONER IIWTesamuf Eg RANGE .. Elf WAL. Sr!S EAL. REDE C. SUFFt.T REC 00 SING DISFtAT 10CATirst (gggg3rts

 . VI.3 CONTA!1eENT AIR (Centtaued)

2. Oeygee Centent R.G. 3 ' - 0-304 N.S.P. N.S.P. N.S.P. N.S.P. N/R On h District uns t.at re=

quired te provide as per 073711.8.3.1-3 (NO SPECIPIC I N S T R 5 N E N T *) requirements and response to require-monts.

 - 3. Gamma Spectrum              R.G.         3    -   ISDIOPIC                  N.S.P.              N.S.P.            W.S.P.      N.S.P. N/R        On Desand (Provided by PASS) .                    Orp0 0737        0737 ISOKtIC                                                                                           on Demand             la Compliance (SL-35,40) o IIe Specif te F.A.S.S. re. Can Take Grab Sample and Analyse Ott11 stas Cheatstry Procedures '
   - 0A regatrements categartes 3.2 and 3 shown ta Sectice 2.3.3.A.5.

N/R - Ilot Required C.S.P.

• No Specific Provistas e

                                                                                                                 =24-                                                Rev. 8 Date 4/1/85
                                        .}}