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BALTIMORE GAS AND ELECTRIC COMPANY P. O. BOX 1475 BA LTIM O R E, M ARYLAN D 21203 January 22, 1980 AnyHun E. LUNDVALL.JR. | BALTIMORE GAS AND ELECTRIC COMPANY P. O. BOX 1475 BA LTIM O R E, M ARYLAN D 21203 January 22, 1980 AnyHun E. LUNDVALL.JR. | ||
vice page.ocus Su pptv Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 | vice page.ocus Su pptv Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. | ||
20555 | |||
==Subject:== | ==Subject:== | ||
| Line 26: | Line 27: | ||
==References:== | ==References:== | ||
(a) NRC letter dated 11/7/79 from D. G. Eisenhut to A. E. Lundvall, Jr., NRC Requirements for Auxiliary Feedvater Systems. | (a) NRC letter dated 11/7/79 from D. G. Eisenhut to A. E. Lundvall, Jr., NRC Requirements for Auxiliary Feedvater Systems. | ||
(b) NRC letter dated 12/21/79 from R. W. Ried to A. E. Lundvall, Jr. , Automatic Initiation of Auxiliary Feedvater Systems. | (b) NRC letter dated 12/21/79 from R. W. Ried to A. E. Lundvall, Jr., Automatic Initiation of Auxiliary Feedvater Systems. | ||
(c) BG&E letter dated 12/13/79 from A. E. Lundvall, Jr. | (c) BG&E letter dated 12/13/79 from A. E. Lundvall, Jr. | ||
to D. G. Eisenhut, NRC requirements for Aux Feed System. | to D. G. Eisenhut, NRC requirements for Aux Feed System. | ||
| Line 32: | Line 33: | ||
==Dear Mr. Denton:== | ==Dear Mr. Denton:== | ||
Baltimore Gas and Electric Company hereby requests an amendment to Operating Licenses DPR-53 and DPR-69 for Calvert Cliffs Units 1 and 2, respectively, with the submittal of the following proposed changes to the Technical Specifications. All changes apply to both Units unless otherwise indicated. | Baltimore Gas and Electric Company hereby requests an amendment to Operating Licenses DPR-53 and DPR-69 for Calvert Cliffs Units 1 and 2, respectively, with the submittal of the following proposed changes to the Technical Specifications. All changes apply to both Units unless otherwise indicated. | ||
TECHNICAL SPECIFICATION CHANGES Change No. 1. | TECHNICAL SPECIFICATION CHANGES Change No. 1. | ||
(FCR 79-125) Paragraph 6.10.2, change as shown on attached page 6-20. | (FCR 79-125) Paragraph 6.10.2, change as shown on attached page 6-20. | ||
1809 332 Discussion The present wording " Records of Quality Assurance activities required by the QA Manual" could be interpreted as all records in the QA Manual. Many of the records specified in the QA Manual are interdepart-mental records which should not be retained for the lifetime of the plant. | |||
The present wording " Records of Quality Assurance activities required by the QA Manual" could be interpreted as all records in the QA Manual. Many of the records specified in the QA Manual are interdepart-mental records which should not be retained for the lifetime of the plant. | Examples of these documents are as follows: | ||
Examples of these documents are as follows: Notice of Transmittal of Procedures for Reviev, Request for Document Review, Transmittal of Records to Plant History File, Transmittal of Correction / Supplement to Records in Plant History File, etc. | Notice of Transmittal of Procedures for Reviev, Request for Document Review, Transmittal of Records to Plant History File, Transmittal of Correction / Supplement to Records in Plant History File, etc. | ||
8001250 9 2 P | 8001250 9 2 P | ||
Mr. H. R. Denton | Mr. H. R. Denton January 22, 1980 Chance No. 2 (FCR 79-130) Paragraph 4.7.11.h, Change as shown on attached page 3/h 7-73. | ||
Chance No. 2 (FCR 79-130) Paragraph 4.7.11.h, Change as shown on attached page 3/h 7-73. | |||
Discussion Present requirements dictate that each of the critical hose stations identified in table 3 7-5 be visually inspected every 31 days. | Discussion Present requirements dictate that each of the critical hose stations identified in table 3 7-5 be visually inspected every 31 days. | ||
This would require entry into the containment while the reactor is at power. Since the containment is a restricted area during this condition, it is thus not open for general use. Therefore, the probability of equip-ment tamparing or degradation is greatly reduced and containment entry for purposes of routine inspections can not be justified under the ALARA concept. | This would require entry into the containment while the reactor is at power. Since the containment is a restricted area during this condition, it is thus not open for general use. | ||
Therefore, the probability of equip-ment tamparing or degradation is greatly reduced and containment entry for purposes of routine inspections can not be justified under the ALARA concept. | |||
Change No. 3 (FCR 79-148) Paragraph 3/h.7.1.2, replace with proposed change shown on attached pages. | Change No. 3 (FCR 79-148) Paragraph 3/h.7.1.2, replace with proposed change shown on attached pages. | ||
Discussion References (a) and (b) requested that we provide certain information, including proposed technical specifications, concerning the auxiliary feedvater system and actuation circuitry at Calvert Cliffs. | Discussion References (a) and (b) requested that we provide certain information, including proposed technical specifications, concerning the auxiliary feedvater system and actuation circuitry at Calvert Cliffs. | ||
| Line 52: | Line 52: | ||
(FCR 79-88) Table 3.7-4, delete 15 snubbers as shown on attached sheets. | (FCR 79-88) Table 3.7-4, delete 15 snubbers as shown on attached sheets. | ||
Discussion The snubbers in question are supports for piping classes GB-7, HC-2 or HB-56, which are all designated as non-safety related piping. | Discussion The snubbers in question are supports for piping classes GB-7, HC-2 or HB-56, which are all designated as non-safety related piping. | ||
Therefore, the snubbers should be deleted from the safety-related snubber | Therefore, the snubbers should be deleted from the safety-related snubber 180.9 333. | ||
180.9 333. | |||
Mr. H. R. Denton | Mr. H. R. Denton January 22, 1980 Change No. 6 (DPR-53 only) | ||
(FCR 79-1037) Table 3 7-h, add snubber 1-6h-35 as shown on attached sheet. | (FCR 79-1037) Table 3 7-h, add snubber 1-6h-35 as shown on attached sheet. | ||
Discussion This snubber was added in connection with a support modification cn the letdown piping and should be added to the ?ist of safety-related cnubbers. | Discussion This snubber was added in connection with a support modification cn the letdown piping and should be added to the ?ist of safety-related cnubbers. | ||
| Line 66: | Line 65: | ||
SAFETY COMMITTEE REVIEW All of the above proposed changes have been reviewed by our Plant Operations and Safety Review Committee and Off-Site Safety and Review Committee, and they have concluded that granting of the proposed changes will not result in an undue risk to the health and safety of the public. | SAFETY COMMITTEE REVIEW All of the above proposed changes have been reviewed by our Plant Operations and Safety Review Committee and Off-Site Safety and Review Committee, and they have concluded that granting of the proposed changes will not result in an undue risk to the health and safety of the public. | ||
FEE DETERMINATION We have determined, pursuant to 10 CFR Part 170 paragraph 170.22, that this amendment request consists of Class IV and Class I amendments for Calvert Cliffs Units 1 and 2, respectively, and, accordingly, we are enclosing BG&E Check No. B056618 in the amount of $12,700.00 to cover the fee for this request. | FEE DETERMINATION We have determined, pursuant to 10 CFR Part 170 paragraph 170.22, that this amendment request consists of Class IV and Class I amendments for Calvert Cliffs Units 1 and 2, respectively, and, accordingly, we are enclosing BG&E Check No. B056618 in the amount of $12,700.00 to cover the fee for this request. | ||
BALTIMORE GAS AND ELECTRI | BALTIMORE GAS AND ELECTRI OMPANY r.>. - }^11 1 | ||
i By: | |||
m s. | |||
f Vice Pre %id6n upply [ | |||
l | l | ||
Mr. H. R. Denton | Mr. H. R. Denton 14 January 22, 1980 STATE OF MARYLAND: | ||
: TO WIT: | : TO WIT: | ||
CITY OF BALTIMORE: | CITY OF BALTIMORE: | ||
Mr. A. E. Lundvall, Jr. being duly s;orn states that he is Vice President of the Baltimore Gas and Elect.ric Company, a corporation of the State of Maryland; that he executed the foregoing Amendment for the purposes therein set forth; that the statements made in said Amendment are true and correct to the best of his knowledge, information and belief; and that he was authorized to execute the Amendment on behalf of said corporation. | Mr. A. E. Lundvall, Jr. being duly s;orn states that he is Vice President of the Baltimore Gas and Elect.ric Company, a corporation of the State of Maryland; that he executed the foregoing Amendment for the purposes therein set forth; that the statements made in said Amendment are true and correct to the best of his knowledge, information and belief; and that he was authorized to execute the Amendment on behalf of said corporation. | ||
WITNESS my hand and Notarial Seal. | WITNESS my hand and Notarial Seal. | ||
b JJ w | |||
My Commission expires: | ,/ l x ' | ||
q My Commission expires: | |||
cc: | l'7A I(/ // / | ||
/ ' | |||
() | |||
cc: | |||
J. A. Biddison, Esquire G. F. Trowbridge, Esquire Messr2. E. L. Conner, Jr. - NPC P. W. Kruse - CE J. W. Bluthers - Bechtel 1809 335 i}} | |||
Latest revision as of 18:27, 3 January 2025
| ML19257C289 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 01/22/1980 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19257C290 | List: |
| References | |
| NUDOCS 8001250522 | |
| Download: ML19257C289 (4) | |
Text
BALTIMORE GAS AND ELECTRIC COMPANY P. O. BOX 1475 BA LTIM O R E, M ARYLAN D 21203 January 22, 1980 AnyHun E. LUNDVALL.JR.
vice page.ocus Su pptv Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Calvert Cliffs Nuclear Power Plant Units Nos.1 & 2, Dockets Nos. 50-317 & 50-318 Recuest for Amendment to Operating Licenses
References:
(a) NRC letter dated 11/7/79 from D. G. Eisenhut to A. E. Lundvall, Jr., NRC Requirements for Auxiliary Feedvater Systems.
(b) NRC letter dated 12/21/79 from R. W. Ried to A. E. Lundvall, Jr., Automatic Initiation of Auxiliary Feedvater Systems.
(c) BG&E letter dated 12/13/79 from A. E. Lundvall, Jr.
to D. G. Eisenhut, NRC requirements for Aux Feed System.
(d) BG&E letter dated 1/15/80 from R. C. L. Olson to D. G. Eisenhut, NRC Requirements for Aux Feed Systems.
Dear Mr. Denton:
Baltimore Gas and Electric Company hereby requests an amendment to Operating Licenses DPR-53 and DPR-69 for Calvert Cliffs Units 1 and 2, respectively, with the submittal of the following proposed changes to the Technical Specifications. All changes apply to both Units unless otherwise indicated.
TECHNICAL SPECIFICATION CHANGES Change No. 1.
(FCR 79-125) Paragraph 6.10.2, change as shown on attached page 6-20.
1809 332 Discussion The present wording " Records of Quality Assurance activities required by the QA Manual" could be interpreted as all records in the QA Manual. Many of the records specified in the QA Manual are interdepart-mental records which should not be retained for the lifetime of the plant.
Examples of these documents are as follows:
Notice of Transmittal of Procedures for Reviev, Request for Document Review, Transmittal of Records to Plant History File, Transmittal of Correction / Supplement to Records in Plant History File, etc.
8001250 9 2 P
Mr. H. R. Denton January 22, 1980 Chance No. 2 (FCR 79-130) Paragraph 4.7.11.h, Change as shown on attached page 3/h 7-73.
Discussion Present requirements dictate that each of the critical hose stations identified in table 3 7-5 be visually inspected every 31 days.
This would require entry into the containment while the reactor is at power. Since the containment is a restricted area during this condition, it is thus not open for general use.
Therefore, the probability of equip-ment tamparing or degradation is greatly reduced and containment entry for purposes of routine inspections can not be justified under the ALARA concept.
Change No. 3 (FCR 79-148) Paragraph 3/h.7.1.2, replace with proposed change shown on attached pages.
Discussion References (a) and (b) requested that we provide certain information, including proposed technical specifications, concerning the auxiliary feedvater system and actuation circuitry at Calvert Cliffs.
References (c) and (d) prc, vide some information and stated that proposed technical specifications, as requested by NRO, would be submitted by January 23, 1980. This submittal constitutes that information.
Change No. h (FCR 80-5) Paragraph 6.h.2, change NFPA Code from 1976 to 1975 as shown on attached page 6-6.
Discussion This change is being made to correct a typographical error on the original technical specification. The NFPA Code should be 1975 Change No. 5 (DPR-53 only)
(FCR 79-88) Table 3.7-4, delete 15 snubbers as shown on attached sheets.
Discussion The snubbers in question are supports for piping classes GB-7, HC-2 or HB-56, which are all designated as non-safety related piping.
Therefore, the snubbers should be deleted from the safety-related snubber 180.9 333.
Mr. H. R. Denton January 22, 1980 Change No. 6 (DPR-53 only)
(FCR 79-1037) Table 3 7-h, add snubber 1-6h-35 as shown on attached sheet.
Discussion This snubber was added in connection with a support modification cn the letdown piping and should be added to the ?ist of safety-related cnubbers.
Change No. 7 (DPR-69 only)
(FCR 79-109) Table 3.7-4, add snubbers 2-38-1, 2-38-2, 2-63-1 and 2-63-2 to the list of safety-related snubbers as shown on the attached sheets.
Discussion The snubbers in question have been identified as supports on safety-related piping and should be included on the safety-related snubber list.
Change No. 8 (DPR-69 only)
(FCR 79-10hh El) Table 3.7 h, add snubbers 2-15-8 and 2-15-9 to the list of safety-related s abbers as shown on the attached sheet.
Discussion The snubbers in question have been identified as supports for safety-related piping and should be included on the safety-related snubber list.
SAFETY COMMITTEE REVIEW All of the above proposed changes have been reviewed by our Plant Operations and Safety Review Committee and Off-Site Safety and Review Committee, and they have concluded that granting of the proposed changes will not result in an undue risk to the health and safety of the public.
FEE DETERMINATION We have determined, pursuant to 10 CFR Part 170 paragraph 170.22, that this amendment request consists of Class IV and Class I amendments for Calvert Cliffs Units 1 and 2, respectively, and, accordingly, we are enclosing BG&E Check No. B056618 in the amount of $12,700.00 to cover the fee for this request.
BALTIMORE GAS AND ELECTRI OMPANY r.>. - }^11 1
i By:
m s.
f Vice Pre %id6n upply [
l
Mr. H. R. Denton 14 January 22, 1980 STATE OF MARYLAND:
- TO WIT:
CITY OF BALTIMORE:
Mr. A. E. Lundvall, Jr. being duly s;orn states that he is Vice President of the Baltimore Gas and Elect.ric Company, a corporation of the State of Maryland; that he executed the foregoing Amendment for the purposes therein set forth; that the statements made in said Amendment are true and correct to the best of his knowledge, information and belief; and that he was authorized to execute the Amendment on behalf of said corporation.
WITNESS my hand and Notarial Seal.
b JJ w
,/ l x '
q My Commission expires:
l'7A I(/ // /
/ '
()
cc:
J. A. Biddison, Esquire G. F. Trowbridge, Esquire Messr2. E. L. Conner, Jr. - NPC P. W. Kruse - CE J. W. Bluthers - Bechtel 1809 335 i