ML20149G523: Difference between revisions

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#REDIRECT [[TXX-8815, Responds to NRC 871207 Request for Addl Info Re ATWS Mitigating Sys Actuation Circuitry Ser.Periodic Testing Will Be Performed Per Operations Instrumentation & Control Maint Procedures]]
| number = ML20149G523
| issue date = 02/16/1988
| title = Responds to NRC 871207 Request for Addl Info Re ATWS Mitigating Sys Actuation Circuitry Ser.Periodic Testing Will Be Performed Per Operations Instrumentation & Control Maint Procedures
| author name = Counsil W, Woodlan D
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name =
| addressee affiliation = NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
| docket = 05000445, 05000446
| license number =
| contact person =
| document report number = TXX-88151, NUDOCS 8802180291
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}
 
=Text=
{{#Wiki_filter:.                      ..                                                  .                    ._
M EE                            Log # TXX-88151 file # 10035 r    C                                        915.8 filELECTRIC                                                                                                      ,
February 16, 1988
              % illiam G. coundl                                                                                                                                    >
lar,wnr nur haarm U. S. Nuclear Regulatory Commission                                                                                                                    !
Attn: Document Control Desk Washington, D. C. 20555
 
==SUBJECT:==
COMAtlCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET fl05, 50-445 AND 50-446                                                                                                        :
AMSAC SER EVALUATION REPORT RESPONSE CLARiflCATION REF:    W.G. Counsil letter TXX-6769 to NRC dated October 9, 1987 i
Gentlemen:
On December 7. 1987, the NRC staff requested additional information about TV Electric's response to the AMSAC safety evaluation report, via a telephone                                                                            l conference call. CPE 1&C provides the following information or clarification pertaining to these issues.
: 1)      hRC Question: Provide the model number for Struthers-Dunn relays that are used within AMSAC.                                                                                                                            i
        .              TV Electric Response:    The model number of the Struthers-Dunn relays used withir AMSAC system is 219xDX181NE.                                                                                                            '
: 2)      NRC Question:    Provide additional details about non-lE power supply to the AMSAC cabinet. Where does the non-lC power supply tie together with IE power in the voltage ladder? Is this power independent from the Reactor Protection System (RPS) p3wer supply? Furnish reference drawings.
TV Electric Response:    The AMSAC cabinet is provided with an uninterruptible non-Class IE power supply from distribution panel IC5.
Upstream, this panel is connected to non-Class 1E 6.9kV Switchgears lAl and 1A2 which are powered from the X and Y Secondary windings of Unit Auxiliary Transformer, IUT. The RPS power supply is provided from Class lE 125V DC buses LED 1 and LED 2, which are fed from Class IE Motor Control Centers (MCC's) lEB1-1, IEB2-1, IEB3-1 and lEB4-1. These MCC's are                                                                              :
connected through Class IE load centers to the 6.9kV switchgear leal and IEA2.      Thus AMSAC and RPS power supplies do not have a common point in the voltage ladder up to the 6.9kV voltage level (see reference drawings 2323-El-0018, Sheet 3, 2323-El-001, ECE-El-0001, Sheet A).
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TXX-88151 February 16, 1988 Page 2 of 3
: 3) NRC Question: Do existing plant procedures meet and/or exceed the QA requirements of G.L. 85-067 TV Electric Response:    No. Some of the required procedures have not been written yet. In addition, existing procedures are under review to assure they meet the QA requirements of Generic Letter 85-05. The quality assurance program for design, procurement, installation, testing and maintenance will meet the requirements of Generic Letter 85-06.
: 4)  HRC Question:    In the section "Safety-Related Interface" of the SER response, what is implied by the words "all applicable" in the following sentence:
                              "These isolation devices ensure that the existing protection system continues to meet all applicable safety criteria by providing isolation at, demonstrated in Apiiendix A of {his submittal".
TV Electric Response: The words "all applicable" were used in context with separation of non-safety related AMSAC equipment from the existing safety-related Reactor Prntection System at points of interface.
Separation will be accomplished using isolation devices to ensure that AMSAC will not cause degradation of the existing Reactor Protection System. Applicable criteria for separation are IEEE standards 279, 384 and NRC Regulatory Guide 1.75. Compliance with these documents is discussed in the CPSES FSAR.
: 5) NRC Question:      Time delay of C-20 has been increased by Rev. 1 of WCAP-10858P-A. Does TV Electric intend to implement this extension? Discuss implementation of Rev. 1 in general.
TV Electric Response: At present, the CPSES design is based on WCAP-10858P-A, Rev. O. In the AMSAC Generic Design Package WCAP 10858P-A, Rev.
1, Westinghouse increased the range of C-20 arming-off-delay timer to 420 seconds and proposed an arming-off-delay time of 360 seconds.
Westinghouse advised that the range of this time is increased to 420 seconds whereas the CPSES AMSAC System default arr.:ing-off-delay time is 260 seconds. Westinghouse will revise the C-20 arming-off-delay time in the future, if required. This change i.an then be incorporated by using AMSAC software.
Revision 1 of WCAP 10858P-A, was submii.ted to the NRC on August 3, 1987.
Upon approval of the subject WCAP by the N9C and subsequent SER revision, if required, TU Electric would consider incorporation of any appropriate change as recommended by Westinghouse.
I
_            _  m______m_. _ _ _ _ _ _ - _ _ - _ . - _ _
 
l TXX-88151 February 16, 1988 Page 3 of 3
: 6) NRC Question: Testability at power - what is the test frequency while at power? Frequency while shutdown?
TV Electric Response:  At power, AMSAC will be tested quarterly. This quarterly test will consist of a self calibration of the processor and a semiautomatic test of the entire actuation logic system for AMSAC, as recommended by Westinghouse. During s,tutdown these quarterly tests will not be performed except as described in response to item #7.
: 7)  NRC Question: Will an end-to-end test be performed during each refueling outage 7 TV Electric Response: End-to-end testing of the AMSAC system will be performed during each refueling outage. However, credit will be taken    for overlapping tests, such as input sensor calibration.
: 8) NRC Question: What control document will be used for testing?
TV Electric Response: Post installation testing will bo conducted utilizing a pre-operational test. Periodic testing will be performed per Operations Instrument 6 tion and Control Maintenance procedures (calibration procedures for quality related equipment).
Very truly yours, b.(o.
W. G. Counsil l                                                        By:
D. R. Woodlan Supervisor, Docket Licensing VIP /mgt c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) l
                                                  .  . ..  - .}}

Latest revision as of 01:29, 12 July 2023