ML20247G395

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Forwards Response to NRC Request for Addl Info Re FSAR Chapter 7 Issues & Rev 2 to Reg Guide 1.97.Proprietary WCAP-12228 & Nonproprietary WCAP-12229, Transit Time ... Encl.Proprietary WCAP-12228 Withheld (Ref 10CFR2.790)
ML20247G395
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 03/31/1989
From: William Cahill
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19297H472 List:
References
RTR-REGGD-01.097, RTR-REGGD-1.097 TXX-89151, NUDOCS 8904040214
Download: ML20247G395 (15)
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Log ( TXX-89151

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r C 907.2 (clo illELECTRIC & fCyy e l NahtO$a rrasisent u .

U. S. Nuclear Regulatory Commission -

Attn: Document Control Desk Washington, D. C. 20555 SU3 JECT: COMANCHE PEAK' STEAM' ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION PERTAINING'T0 FSAR CHAPTER 7 ISSUES AND REGULATORY GUIDE 1.97, REVISION 2 REF': 1) NRR Letter from C. I. Grimes to W. J. Cahill, Jr.

dated 02/06/89

2) CPSES FSAR Question and Response Section 032.110 Gentlemen:

On March 17 4 1989, TV Electric verbally requested a two week extension (March 31, 1989) from NRR for responding to Reference 1. The two week extensionwasgrantedbyNRR(M.Malloy). Enclosed is the response to Reference 1.

Also enclosed are:

1. One (1) copy of the Westinghouse, WCAP-12228, " Transit Time Flow Meter (TTFM) Calculations" (Proprietary)
2. One (1) copy of the Westinghouse, WCAP-12229, " Transit Time Flow Meter (TTFM) Calculations" (Non-Proprietary)  ;
3. One (1) copy of the Westinghouse authorization letter, CAU-89-47 1
4. One (1) copy of the Westinghouse Proprietary Information Notice

'5. One (1) copy of a Westinghouse Affidavit.  ;

Reference 2 contains additional information pertaining to CPSES compliance with Regulatory Guide 1.97, Revision 2 with the exception of the noted deviations, pos/t ,

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TXX-89151 March 31, 1989 Page 2 of 2 Item 1 contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

Accordingly, it is respectfully requested that the information which is pro)rietary to Westinghouse be withheld from public disclosure in accordance witi 10CFR Section 2.790 of the Commission's regulations.

Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Westinghouse Affidavit shc'1d reference .

CAW-89-047 and should be addressed to R. A. Wiesemann, Manager of Regulatory &

Legislative Affairs, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

Sincerely, l

William J. C ill, Jr. j VPC/vid Enclosures u c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) l l

l l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______._______________________.__._______--_______________________-_--___.-____-_-______._--_----_.J

l March 31, 1989 Page 1 of 4 ENCLOSURE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION COMANCHE PEAK UNITS 1 AND 2 FSAR CHAPTER 7 ISSUES AND REGULATORY GUIDE 1.97, REVISION 2 NRC QUESTION 1 The attached report, prepared by INEL and reviewed by the staff, concludes that TV Electric has provided an explicit commitment on conformance to R. G.1.97, with the exception of those items which were identified by the applicant. Further, it is concluded that the applicant's justification for exceptions to R. G. 1.97 for some items is acceptable. However, there are some items for which INEL could not conclude that adequate justification was provided and has identified those as unjustified exceptions. Please respond to the unresolved issues as identified in the attached report and provide any other comments if this re3 ort includes any incorrect assumptions or reflects a commitment which you 3elieve is beyond the intent of your previous response.

TU RESPONSE 1 As identified in the CPSES FSAR, TV Electric developed an accident monitoring design using the guidance of U. S. NRC Regulatory Guide 1.97 (R. G. 1.97) Revision 2. The design is described in detail in FSAR Section 7.5. Although not committed to R. G. 1.97 Revision 2, the CPSES design meets the intent of R. G. 1.97 Revision 2. In Generic Letter 82-33 and FSAR Question 032.110, the NRC requested that TV Electric perform a comparision to R. G.1.97 Revision 2dand identify / justify areas where the design did not comply. The comparisjon of TV Electric's assessment of the CPSES design and R. G. 1.97 Revision 2 is provided in the response to Question 032.110 in the CPSES FSAR.

Attachment 1 provides the response to the unresolved issuen identified in the Idaho National Engineering Laboratory (INEL) report titied Technical Evaluation Report: Conformance to Regulatory Guide 1.97: Comanche Peak

-1/-2.

Enclosure.to TXX-89151 March 31, 1989 Page 2 of~4 j

NRC QUESTION 2 After further review of FSAR Section 7.2.1.1.2, the staff has identified an apparent. discrepancy. The FSAR overtemperature N-16 trip signal discussion indicates the use of T-avg as an input variable for the required setpoint calculation. However, the equation provided in the FSAR

-l (Section 7.2.1.1.2.2.a) does not show T-avg to actually be included as p part of the setpoint development for this reactor trip. Provide l clarifying information to address this apparent discrepancy. '

TV RESPONSE 2 The overtemperature N-16 trip signal discussion presented in FSAR Section 7.2.1.1.2 is in error.

.o T-avg is not used as an input variable in the .;

overteoperature N-16 trip setpoint equation. The CPSES FSAR'will be updated in a future amendment to reflect the correct setpoint calculation.

NRC QUESTION 3 J

The information presented in the September 5, 1985 letter (TXX-4546) indicates that during a meeting held on October 11, 1984 between  !

representatives of Texas Utilities, Westinghouse and the NRC, it was  !

agreed that the total Transit Time Flow Meter (TTFM) uncertainty should be increased to a certain value on a single loop basis. The increase was deemed necessary by the staff to cover additional perceived uncertainties 1 in the TTFM Azimuthal Velocity Profile which is one parameter in the i overall uncertainty analysis. This resulted in the application of an "NRC l conservatism factor" for the TTFM uncertainty calculation. From review of the September 5, 1985 letter, it is not clear that the "NRC conservatism 4 factor" was appropriately incorporated into the cold leg volumetric flow uncertainty calculation prior to statistically combining with the elbow tap uncertainty. In this regard, provide clarifying information (step-by-step correlation) to describe how the required NRC conservatism value was factored into the reactor coolant system flow measurement uncertainty j analysis for generation of the Comanche Peak Technical Specifications. j TV RESPONSE 3 I

The enclosed Westinghouse documents, WCAP-12228/WCAP-12229, provide I additional information regarding consideration of the "NRC conservatism i factor" in the total Transit Time Flow Meter (TTFM) uncertainty I calculation.

_ ____ --__ 1

6 March 31, 1989.

M '

!Page 3 of 4 1..

3 NRC QUESTION 4 FSAR Section 7.3.2.2.8 indicates that control switches for ESF final actuators for pumps-are of the spring-return-to-automatic type. This FSAR section also indicates that when operating conditions necessitate, the operator can-manually override the automatic operation of individual-components. .Specifically, it is stated that the operator can stop .a safety-related pump which has received an auto-start signal from the ESF sequence by holding the control switch in the "stop" position. After the sequencer has cycled, the pump will not restart when the operator releases the control switch. However, other information in this FSAR section V indicates that the alternate operating mode-is provided with permissives or operator lockouts that prevent the operator from intervening with the automatic operation of the final actuation device when the ESF sequencer is in operation. ;i The manual override control design feature noted'above appears to allow the operator to prevent (through a single manual action) a required automatic safety action from going to completion subsequent to actual initiation of the protective function. This manual override of an automatic protective action before completion of the mitigative function i could degrade the mitigation of a design basis event even though the l initiating signals have not cleared.

In view of the above, provide a discussion which addresses each of the following:

a. Identify each ESF pump and associated system which incorporates the manual o' ~ ride control design feature.
b. Describe how the sanual override control design feature has been factored into the emergency operating procedures for responding (operator action) to each postulated design basis event analyzed in FSAR Chapter 15.
c. Describe how the manual override control design feature for pumps relates to permissives and operator lockouts that prevent the operator from intervening with automatic operation of the final actuation device. Supplement this discussion with selected attendant electrical schematics for the final actuator circuitry. 1 i

1

Enclosure to TXX-89151 March 31, 1989 Page 4 of 4 TV I'ESPONSE 4 On March 6,1989, TV Electric contacted Frank Ashe of NRR for clarification of Question 4. Based on the clarification received, the following response is provided:

a. ESF pumps with the manual override design feature are;
1. Charging pumps A&B
2. Safety injection pumps A&B
3. Residual heat removal pumps A&B
4. Station service water pumps A&B
5. Component cooling water pumps A&B 1
6. Containment spray pumps A,B,C,D
7. Auxiliary feedwater pumps A&B
b. CPSES Emergency Response Guidelines (ERGS) do not address manual override situations. The ERGS require the operator to verify that the component / system has auto-started. If i not, the ERGS require that the operator manually start the component / system. If the operator determines that an ESF component / system is no longer required, the ERGS require the operator to reset the Safety Injection (SI) signal and SI sequencer and return the component / system to standby utilizing component control switches,
c. There are two interlocks associated with the ESF pumps that prevent operator action during the auto-start sequence.

. (1) Operator lockout (refer to Figure 1, dwg El-0031 Sht. 25, contact nomenclature: OL/ SIS) prevents the )

operator from manually starting a pump during the load sequencer cycle. The interlock resets automatically at the end of the sequencer cycle.

. (2) Auto lockout (refer to Figure 1, dwg El-0031 Sht 25 contact nomenclature: AL/ SIS) is only used if auto-starts other than SI exist for a given pump and prevents these auto-starts from starting the pump during a load sequencer cycle. The interlock is manually reset by the operator. ,

{

Figure 2, dwg El-0031 Sht 26 shows the switch development I associated with Figure 1. Both figures are typical for the pumps listed in "a" above.

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Attachment to TXX-89151 March 31, 1989 Page 1 of 5 1 ATTACHMENT 1 NRC QUESTION (Item 3.3.6)

Containment isolation valve position - The licensee should either provide Category 1 position indication for the manually operated containment isolation valves or supply suitable justification for not providing this instrumentation.

TV RESPONSE (Item 3.3.6)

All local manually-operated containment isolation valves are locked closed and administrative 1y controlled. Therefore, position indication for these valves, as recommended by Regulatory Guide 1.97, Revision 2 is not required. All remote-manual containment isolation valves have position indication.

NRC QUESTION (Item 3.3.12) j Steam generator level-wide range - The licensee should verify that this instrumentation is Category 1.  !

TV RESPONSE (Item 3.3.12)

Deviations from Category 1 requirements for Steam Generator Level-Wide Range instrumentation are identified in FSAR Table 032.110-4, Sheet 3 and FSAR Table 032.110-5, Sheet 3 Note 8 and Sheet 6 Note 28. The deviation states that at CPSES, Steam Generator Water Level-Wide Range Instrumentation is used as a backup variable to the key variables Steam Generator Water Level-Narrow Range and Auxiliary Feedwater Flow, to determine loss of secondary heat sink and Steam Generator Water Level. ,

Therefore, Steam Generator Water Level-Wide Range is categorized as an D2 variable at CPSES. As an 02 variable in the CPSES design, additional information is not required to resolve ambiguity due to a channel failure.

NRC QUESTION (Item 3.3.21)

Vent from steam generator safety-relief valves - The licensee should environmentally qualify this instrumentation in accordance with Regulatory Guide 1.97, 10CFR50.49, or alternatively, identify the common plant vent instrumentation and verify that it is Category 2.

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Attachment to TXX-89151 March 31, 1989 Page 2 of 5 TV RESPONSE (Item 3.3.21)

The Main Steam Line Radiation Monitors are radiation detectors that are utilized in the assessment of radioactive releases. These monitors are required to operate only during a steam generator tube rupture event. For the time period required to make the release assessment during a Steam Generator Tube Rupture event, these monitors are in a mild environment.

FSAR Table 7.5-7, Note 3 and Table 032.110-3 will be revised to clarify the requirement. Also see the response to item 3.3.30A of this letter.

NRC QUESTION (Item 3.3.23)

All other identified release points-noble gas and vent flow - The licensee should either verify that all identified release points are monitored in accordance with Regulatory Guide 1.97 or provide additional instrumentation to bring about full compliance.

TV RESPONSE (Item 3.3.23)

All identified release points are monitored in accordance with Regulatory Guide 1.97, Revision 2. The CPSES design utilizes a common ventilation system where gaseous effluent generated in any area of the plant is directed to a common plenum and then released via two plant vent stacks.

The noble gases and vent flow rate for " Airborne Radioactive Materials Released from the Plant" as stated in Regulatory Guide 1.97, Revision 2, are monitored by the Plant Vent Stack Wide Range Gas Monitors (X-RE-5570 A,B) as stated in FSAR Table 032.110-1, Sheet 16.

NRC QUESTION (Item 3.3.24)

Particulate and halogens - The licensee should verify that the range supplied meets or exceeds the recommended range.

TV RESPONSE (Item 3.3.24)

The instrumentation used to p capability of meeting the 10 grform 3 u Ci/cconsite to 10 analysis at CPSES has the2 pCi/cc ran in Regulatory Guide 1.97, Revision 2.

NRC QUESTION (Item 3.3.25)

Airborne radiohalogens and particulate - The licensee should describe the instrumentation supplied for this variable and verify that it meets the recommendation of Regulatory Guide 1.97.

_ _ ____ A

Attachment to TXX-89151.

March 31, 1989-Page 3 of 5

.T0 RESPONSE (Item 3.3.25)

Instrumentation currently provided for this variable'at CPSES is as follows:- l A. Portable Sampling Equipment: f

. RadeCo Model H-809 V-I

. RadeCo Model H-809 B-II B. Onsite Analysis Equipment

. Canberra Germanium Detector

. Canberra Multichannel Analyzer The ons

.the 10 f teuCi/cc analysis egyipment to 10-3 pCi/cc noted rangeabove has theincapability as specified Regulatoryof meeting Guide 1.97, Revision 2. The addition of this variable will be incorporated in a future FSAR amendment.

NRC QUESTION (Item 3.3.26)

Plant'and environs radiation - The licensee should verify that the range 4 supplied meets or exceeds the range recommended by Regulatory Guide 1.97.

TU RESPONSE (Item 3.3.26)

The CPSES portable instruments which monitor this variablg meet the Regulatory Guide 1.97 Revisign 2 recommended range of 10-3 R/hr to 10'4 R/hr for photons and 10-3 rads /hr to 104 rads /hr for beta and lower energy photons.

NRC QUESTIONS (Item 3.3.27)

Plant and environs radioactivity - The' licensee should describe the instrumentation supplied for this variable and verify that it meets or exceeds the recommendation of Regulatory Guide 1.97.

TV RESPONSE (Item 3.3.27)

CPSES field monitoring teams are dispatched, as needed, to collect samples. These samples are transported to the Nuclear Operations Support i Facility or the plant Hot Lab for analysis. At either location gamma I

spectroscopy equipment is used to analyze the samples. Instrumentation provided for this capability is identified in the response to Item 3.3.25 and meets the intent of Regulatory Guide 1.97, Revision 2.

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Attachment to TXX-89151 March 31, 1989 Page 4 of 5 i

NRC QUESTIONS (Item 3.3.30A) l Environmental qualification - The licensee should verify the environmental l qualification of the Category 2 instrumentation. 1 TV RESPONSE (Item 3.3.30A)

FSAR Table 7.5-1 shows the qualification requirement for Category 2 l variables as "as appropriate" since the level of qualification is not the same for all Category 2 variables. Category 2 instrumentation that is subject to an adverse environment due to a Design Basis Accident (as described in FSAR Chapter 15) during the time it must serve its intended l function is environmentally qualified per 10CFR50.49 requirements. ,

Category 2 instrumentation that is not subject to an adverse environment '

during the time it must serve its intended function is considered to be in a mild environment and is not required to be environment. ally qualified per ;

10CFR50.49 requirements. Environmental qualification of Category 2 i variables is discussed in FSAR Section 7.5.1.3.2.2. and FSAR Table ,

032.110-6.

NRC QUESTION (Item 3.3.308)

Indication - The licensee should describe the means used to display Category 1 variables.

TV RESPONSE (Item 3.3.30B)

CPSES FSAR Section 7.5.1.1.5 defines the term "immediately accessible" as, "information that is visually available to the control room operator immediately after he has made the decision that the information is needed."

FSAR Table 032.110-1 indicates which displays are available for each Category 1 variable, in summary, Category 1 variables are displayed by one or more of the following means; recorder, indicator, LED display, radiation monitor console, or ERF computer. At a minimum, CPSES Category 1 variables are continuously displayed or available on demand as required in Regulatory Guide 1.97, Revision 2. The methods of indication are in compliance with Regulatory Guide 1.97, Revision 2 and thus no deviations are noted.

NRC QUESTIONS (Item 3.3.30C)

Recording - The licensee should describe the ERF computer including interface and isolation devices, and any other instrumentation used in recording Category 1 variables.

Attachment to TXX-89151 March 31, 1989 l

Page 5 of 5 l

1 l'

l TV RESPONSE (item 3.3.30C) l The instrumentation / computer interface devices of the ERF computer meet the recommendations of Regulatory Guide 1.97, Revision 2. Input signals to the ERF computer (non-1E) from Class 1E systems are optically isolated by qualified Class 1E isolation devices. The design of the ERF computer is consistent with the requirements of NUREG-0737 Supplement 1. See also, the response to Item 3.3.308.

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