ML20099L460
| ML20099L460 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 11/27/1984 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-986, NUDOCS 8412010136 | |
| Download: ML20099L460 (5) | |
Text
{{#Wiki_filter:r das 4 LMION ELECTRIC COMPANY 1901 Grotlot Street.St. Louis Donald F.Schnelt November 27, 1984 Vice President Mr. Harold R. Denton, Director Office of Nuclear Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
ULNRC-986 DOCKET NUMBER 50-483-CALLAWAY PLANT, UNIT 1 FSAR CHAPTER 14 ABSTRACT CHANGE
Attachment:
Revised FSAR Abstract Page In accordance with the Callaway Operating License, the attached proposed change to FSAR Abstract 14.2.12 3 30, Operationa.'. Alignment of Process Temperature Instrumentation, Test Method, Item (a), is submitted for NRC review and approval prior to implementation. The change reflected in this abstract and discussed in the telecon between members of the NRC and Union Electric on November 27, 1984, does not represent a reduction of test program commitments or plant safety, but significantly improves the test flexibility and results. The overall purpose of this test is to correct initial overtemperature and overpower delta-T loop scaling with Callaway specific values. Presently these loops are scaled using predetermined conservative values providing approximately 10 percent additional trip margin. As written the test abstract would require replacement of this conservative scaling with a less restrictive Callaway specific interim scaling at approximately 75 percent power. It is our intention to delay this replacement until a higher power level is attained in order to collect a.dditional data. This permits improvement in the extrapolation methodology by providing additional data points and reducing extrapolation error. Union Electric has evaluated-this change for impact upon the FSAR and plant safety. Existing safety margins, as described in the FSAR, are maintained due to the following: 1. The existing loop scaling provides approximately an additional 10 percent margin not described in the FSAR. The new interim scaling would reduce that margin by a significant amount. Therefore, retention of this additional margin by maintaining present scaling during power _ ascension above 75 percent is conservative. "~ -8412010136 841127 PDR ADOCK 05000483 i P-PDR 60\\ s
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Mailing Address RO Box 149, St. Louis, MO 63166 s q
r' ~ ^ F 62 g . '2; The scaling process effects only.the AT inputs to the overpower and o~vertemperature delta-T loops and not to the setpoints. ;The setpoints are per Technical Specifications and;will not be modified by this change. Therefore, allisetpoint responses duelto pressure and-flux imbalance are retained, and with~the present scaling, assure _ conservative-system response. 3 Union Electric has evaluated' response of the overtemperature ano overpower delta-T loops as part of the_ test program. -This includes both system wide and sensor response time evaluations. Based upon: existing test data, loop response times are within limits speciried within the Technical Specifications; and since this change will not modify loop time constants or circuitry, sensor response. time.will not be adversely impacted. 4. To prevent any inadvertent trips, due to the conservative setpoint, Union Electric is requiring-rescaling at approximately 90 percent power. This will provide margin against inadvertent trips approximately equivalent to the margin designed into these loops, if correctly scaled and operating at 100 percent power (approximately 10 percent margin). 5. Since our intention is to-collect as much data as possible to permit a valid extrapolation, Union Electric intends to keep the data collected at 50 and 75 percent power. This will augment the data above.75 percent i power. The above provides.a detailed discussion of the change to the Test Method. In addition, Prerequisite Item (a) is revised to reflect only the test prerequisites and to exclude a repeat of descriptions given under Test Method. l In conclusion, these changes do not violate test program j
- commitments or commitments to Regulatory Guide 1.68, and do not diminish plant safety.
The revised abstract, as approved, will be formally incorporated into the next revision of the FSAR. Very truly yours, l j' Donald F. Schnell l DJW/lae t Attachment t
STATE OF MISSOURI ) ) SS CITY 0F-ST. LOUIS ) Donald F. Schnell, of lawful age, being first duly sworn .upon oath says that he is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief. l O By Donald F. Schnell Vice President Nuclear SUBSCRIBED and sworn to before me this c2 M day of b e /4/, 198M ism hk l BARBARA $PFAFk NOTARY PUBlic, STATE OF MISSOURI MY COMMISSION EXPIRES APRIL 22. !?S5 ST, LOUIS COUNTY. L l 1 l I
SNUPPS 14.2.12.3.30 Operational Alignment of Process Temperature, l Instrumentation (S-07SF06) i 14.2.12.3.30.1 Objectives To align AT and T"E8 criticality and at power process instrumentation under isothermal conditions, prior 14.2.12.3.30.2 Prerequisites This alignment will be performed prior to initial criti-a. cality.--' m n. M C' rrrcent w aar. . 11,. __ _.. .z. ri::h;0 mt 100 ;; ::M pe"^t b. All reactor coolant pumps shall be operating. 14.2.12.3.30.3 Test Method '$d r a. g a T p d tri s ba -/ o i a i e c t e pa 5 e e e v r a.N V b. At or near full power, check the alignment of the AT and T channels for agreement with the results of thermal pM8r measurement. Realign any channels, as necessary, to meet test specifications. 14.2.12.3.30.4 Acceptance Criteria The 100 percent power indications 'for AT and T channels must be within the maximum design values as specifiS89in vendor design documents. As pw ad ins trucken s, ob4J~ vah 4 AT on1 T vAer isobemak. conclikcms prio r-In I c r3ita; h. 4 av o minim wm a4 & 60 75 3 ud 90 pu ant poaue leve2s. 6 kaf od M, i c ako +o dekemine AT ecl % Values for 1.00 pu cud gowec, Al;3n AT a Tau, d L< F (0 14.2-102 2
cc:. Gerald Charnoff, Esq. ishaw, Pittman, Potts & Trowbridge 1800 M. Street, N.W. Washington, D.C. 20036 Nicholas A. Petrick i-Executive Director gp.'., SNUPPS-5 Choke Cherry Road Rockville, Maryland 20850 John H. Neisler Callaway Resident Of fice U.S. Nuclear Regulatory Commission RR$1 Steedman, Missouri 65077 'a William Forney Division of Projects and Resident Programs, Chief, Section lA U.S. Nuclear Regulatory Commission . Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Of fice U.S. Nuclear Regulatory Commissior. RRil Steedman, Missouri 65077 Ms. Jan Stevens, Callaway Project Manager ' Office of Nuclear Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l 5 h - -, e,
1901 GroHot Street St Louis Donald F.Schnell November 27, 1984 Vice Presdent .Mr. Harold R. Denton, Director ' Office of Nuclear Regulation U.S.'Huclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
ULNRC-98 6 DOCKET NUMBER 50-483 CALLAWAY PLANT, UNIT 1 PSAR CHAPTER 14 ABSTRACT CHANGE
Attachment:
Revised FSAR Abstract Page In accordance with the Callaway Operating License, the attached proposed change to FSAR Abstract.14.2.12 3 30, Operational Alignment of Process Temperature Instrumentation, Test Method, Item (a), is submitted for NRC review and approval prior to implementation. The change reflected in this abstract and discussed in the telecon between members of the NRC and Union Electric on November o 27, 1984, does not represent a reduction of test program commitments or plant safety, but significantly improves the test flexibility and results. The overall purpose of this test is to correct initial overtemperature and overpower delta-T loop scaling with Callaway specific values. Presently these loops are scaled using predetermined conservative values providing approximately 10~ percent additional trip margin. As written'the test abstract would require replacement of this conservative scaling with a less restrictive Callaway specific interim scaling at approximately 75 percent power. It is our intention to delay this replacement until a higher power level is attained in order to collect additional data. This permits improvement in the extrapolation methodology by providing additional data points and reducing extrapolation error. Union Electric has evaluated this change for impact upon the FSAR and plant safety. Existing safety margins, as described in the PSAR, are maintained due to the following: 1. The existing loop scaling.provides approximately an additional 10 percent margin not described in the FSAR. l The new interim scaling would reduce that margin by a significant amount. 'Therefore, retention of th'. additional margin by maintaining present scaling during power ascension above 75 percent is conservative. Moeng Address P.O Box 149, St Louis MO 63166
- c..
. r 2. The scaling process effects only the AT inputs-to the l: overpower and~overtemperature delta-T loops, and not to the-setpoints..The setpoints are per Technical Specifications and will not be modified'by this. change. .Therefore, all setpoint responses due to pressure and flux imbalance are retained, and with the present scaling, assure conservative system response. 3 Union Electric has evaluated response of the overtemperature and overpower delta-T loops as part of the test program. This includes both system wide.and. sensor response time evaluations. Based upon existing test data,-loop response times are within limits specified within the Technical. Specifications; tuul since this change will not modify loop time. constants or circuitry, sensor response time will not be adversely impacted. 4. To prevent any inadvertent trips, due to the conservative setpoint, Union Electric is requiring rescaling at approximately 90 percent power. This will provide margin against inadvertent trips approximately equivalent to the margin designed into these loops, if correctly scaled and operating at 100 percent power (approximately 10 percent margin). 5. Since our intention is to collect as much data as possible to permit a valid extrapolation, Union Electric intends to keep the data collected at 50 and 75 percent power. This will augment the data above 75 percent power. The above provides a detailed discussion of the change to the Test Method. In addition, Prerequisite Item (a) is revised to reflect only the test: prerequisites and to exclude a repeat of I descriptions given under Test Method. l In conclusion, these n.hanges do not violate test program commitments or. commitments to Regulatory Guide 1.68, and do not diminish plant safety. -The revised abstract, as approved, will be formally incorporated'into the'next revision of the FSAR. Very truly yours, m I Donald F. Schnell DJW/lae Attachment
STATE OF MISSOURI ) ) SS CITY OF ST. LOUIS-) Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best.of his knowledge, information and belief. 7 By Donald F. Schnell Vice President Nuclear l SUBSCRIBED and sworn to before me this OI7 day of M/198 kAL BARBARA J. PFAFF l NOTARY PUBUC, STATE OF MISSOURI I Mt COMMISSION EXPIRES APRIL 22,1985 ST, LOUIS COUNTY l 1 i
SNUPPS 14.2.12.3.30 Operational Alignment of Process Temperature. Instrumentation (S-07SF06) i 14.2.12.3.30.1 Objectives To align AT and T"E8 criticality and at powerprocess instrumentatidn under isother conditions, prior 14.2.12.3.30.2 Prerequisites This alignment will be performed prior to initial criti-a. cality ---4= " '" r r r c e n t_pm:2r. ?.lign nt x41 W - rh::h;;.t 100 ;;;:nt pr ^t b. All reactor coolant pumps shall be operating. 14.2.12.3.30.3 Test Method a. g a T a p yi s %r o 1 a a 3 1 e c t e p a 1 5 / [7 e e v y r a. b. At or near full power, check the alignment of the AT and T channels for agreement with the results of thermal p S8r measurement. Realign any channels, as necessary, to meet test specifications. 14.2.12.3.30.4 Acceptance Criteria The 100 percent power indications for AT and T channels must be within the maximum design values as specifi389in vendor design documents. As pw kd ins 6ckm s,0644~ vh 4 AT 04 T w hr iso %xmd. condikcms prio r. -{v cn'ked;h. 4% o minim wm a3 & so 75 a 3 ud 90 per cmt pouse leve2s. 6 kyou +k coAm +o de6mine AT %cl % VAlges Fo r-n [oo y cd pouas. Ali n AT a,JL % d D 3 F (0 14.2-102
m = ~- ' c c : - Gerald Charnoff, Esq.- ~, shaw, _ Pittman, Potts & Trowbridge '1800 M. Street,-N.W. i r i Washington, D.C. 20036 ,1 Nicholas A.'Petrick' Executive Director g<. -SNUPPS 5 Choke' Cherry Road Rockville, Maryland 20850 John H. Neisler' l Callaway -Resident Of fice U.S.-Nuclear' Regulatory Commission .RRil Steedman, Missouri 65077 's William Forney Division of Projects and Resident 2rograms, Chief, Section lA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Of fice U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077 Ms. Jan Stevens, Callaway Project Manager -Office of Nuclear Regulation U.S.' Nuclear Regulatory Commission Washington, D.C. 20555
p c.c c-, 1901 Grotiot Street St. Louis Donald F.Schnell November 27, 1984 Vice President Mr. Harold R. Denton, Director Office of Nuclear Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear.Mr. Denton:
ULNRC-986 DOCKET NUMBER 50-483 CALLAWAY PLANT, UNIT.1 FSAR CHAPTER 14 ABSTRACT CHANGE
Attachment:
Revised.FSAR Abstruct Page In accordance with the Callaway Operating License, the attached proposed change to FSAR Abstract 14.2.12 3 30, Operational Alignment of Process Temperature Instrumentation, Test Method, Item (a), is submitted for NRC review and approval prior to implementation. The change reflected in this abstract and discussed in the telecon between members of the NRC and Union Electric en November 27, 1984, does not represent a reduction of test program commitments or plant safety, but significantly improves the test flexibility and results. The overall purpose of this test is to correct initial overtemperature and overpower delta-T loop scaling with Callaway specific values. Presently these loops are scaled using predetermined conservative values providing approximately 10 percent additional trip margin. As written the test abstract would require replacement of this conservative scaling with a less restrictive Callaway specific interim scaling at approximately 75 percent power. It is our intention to delay this replacement until a higher power level is attained in order to collect additional data. This permits improvement in the extrapolation methodology by providing additional data points and reducing extrapolation error. Union Electric has evaluated this change for impact upon the FSAR and plant safety. Existing safety margins, as described in the FSAR, are maintained due to the following: 1. The existing loop scaling provides approximately an additional 10 percent margin not described in the FSAR. The new interim scaling would reduce that margin by a significant amount. Therefore, retention of this additional margin by maintaining present scaling during power ascension above 75 percent is conservative. Moiling Address: RO Box 149. St. Louis, MO 63166
m '2. The. scaling. process effects only the AT inputs to the overpower and overtemperature delta-T loops, and not.to L the setpoints. -The setpoints are per Technical Specifications and will not be modified by this change. Therefore, all setpoint responses due.to pressure and flux imbalance ~are retained, and with the present scaling, aasure~ conservative system response. 3. ' Union Electric has' evaluated response of the overtemperature and overpower' delta-T loops as partoof the test program.- This includes both' system wide and sensor response time evaluations. Based'upon existing test-data, loop response times are within limits specified within the. Technical-Specifications; and since this change will not modify loop time constants or-circuitry, sensor response time will not be. adversely impacted ~. 4. To prevenc any inadvertent trips, due to the conservative setpoint, Union Electric is requiring rescaling at approximately 90 percent power. This will provide margin against inadvertent trips approximately equivalent to the margin designed into.these loops, if correctly scaled and operating at 103 percent power (approximately 10 percent margin). 5. Since our intention is to collect as much data as possible to permit a valid extrapolation, Union Electric intends to keep the data collected at 50 and 75 percent power. This will augment e,he data above 73 percent power. The above provides a detailed discussion of the change to the Test Method. In addition, Prerequisite Item (a) is revised to reflect only the test prerequisites and to exclude a repeat of descriptions given under Test Method. In conclusion, these changes do not violate test program commitments or commitments to Regulatory Guide 1.68, and do not diminish plant safety. The revised abstract, as approved, will be formally incorporated into the next revisionaof the PSAR. Very truly yours, C 4 Donald F. Schnell DJW/lae Attachment.
STATE OF MISSOURI ) ) SS CITY OF ST. LOUIS ) Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the f acts therein stated are true and correct to the besu of his knowledge, information and belief. By Donald F. Schnell Vice President Nuclear SUBSCRIBED and sworn to before me this 8 7 day of d u, 198 k 0: 9 BARDARA [PFAFF [/ f(OTARY PUBLIC. S; ATE OF MISSGURI MY COMMISS!O;i EXHRES APRIL 22,1935 ST. LOUIS COUNTY 4 I
... ~. _.. _ _... SNUPPS 14.2.12.3.30 Operational. Alignment of Process Temperature, Instrumentation (S-07SF06) 14.2.12.3.30.1 Objectives To align AT and T"E8 criticality and at power process instrumentation under isothermal conditions, prior 14.2.12.3.30.2 Prerequisites This clignment will be performed prior to initial criti-a. cali ty. ^= -* " ~" - - - ^ " - - Jar. "1ig.- :nt .M N ch::'.u _t 100 ;:r r-t ;^"m-b. All reactor coolant pumps shall be operating. 14.2.12.3.30.3 Test Method s 8r pqt f $ rdc i a. g a T a s b io" o 1 ~ 8 1 1 e c t e p a 1 5 e e v f-o y r a a. b. At or near full power, check the alignment of the AT and T channels for agreement with the results of thermal p8w8r measurement. Realign any channels, as necessary, to meet test specifications. 14.2.12.3.30.4 Acceptance Criteria The 100 percent power indications 'for AT and T channels must be within the maximum design values as specifi889in vendor design documents. As pw b4 instruchms, obb vah 4 AT &T udsr isokmA condikws price -(v cclHca;k. & av s minim am ah {L 50 75 3 3 %d 90 per cent po m levees. Mafed M dak b dekcaiine AT -d % ulues fk n 1.0 0 p u ce d poaar. Ali n AT J TW ed b 3 P (0 14.2-102 2
] p-o 1 cc:. Gerald Charnoff, Esq. Shaw, Pittman, Potts & -Trowbridge 1800 M. Street, N.W. l Washington, D.C. 20036 Nicholas A. Petrick ' Executive Director it: ~ SNUPPS 'S Choke Cherry Road. Rockville, Maryland 20850 . John H. Neisler Callaway Resident Office. U.S._ Nuclear-Regulatory Commission . RR$1 Steedman, Missouri 65077 William Forney Division of Projects and Resident-Programs, Chief, Section lA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077 Ms. Jan Stevens, Callaway Project Manager Office of Nuclear Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i 4 y - - ~ ,-.v., y m
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