NRC Generic Letter 1982-20: Difference between revisions
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{{#Wiki_filter:OCT 2 6 1982 TO ALL POWER REACTOR LICENSEES/PERMIT | {{#Wiki_filter:OCT 2 6 1982 TO ALL POWER REACTOR LICENSEES/PERMIT HOLDERS, APPLICANTS FOR CONSTRUCTION | ||
HOLDERS, APPLICANTS | PERMITS | ||
FOR CONSTRUCTION | Subject: Guidance for Implementing Standard Review Plan Rule (Generic Letter No. 82-aO) | ||
PERMITS Subject: Guidance for Implementing Standard Review Plan Rule (Generic Letter No. 82-aO)Gentlemen: | Gentlemen: | ||
On March 10, 1982, the Commission approved a final rule 10 CFR 50.34(g), *Confor-mance with the Standard Review Plan (SRP)." This rule requires power reactor applications docketed after May 17, 1982, to include an evaluation of the facility against the acceptance criteria of the Standard Review Plan (NUREG-0800). | On March 10, 1982, the Commission approved a final rule 10 CFR 50.34(g), *Confor- mance with the Standard Review Plan (SRP)." This rule requires power reactor applications docketed after May 17, 1982, to include an evaluation of the facility against the acceptance criteria of the Standard Review Plan (NUREG-0800). | ||
The staff has prepared for public comment the enclosed guidance (NUREG-0906) | The staff has prepared for public comment the enclosed guidance (NUREG-0906) for licensees to assist in complying with the rule. The guidance document Is intended as an interim measure until the *Standard Content and Format Guide for Safety Analysis Reports, Regulatory Guide 1.70," is revised to reflect the requirements of the new rule, at which time the guidance in NUREG-0906 would be incorporated into Regulatory Guide 1.70. | ||
for licensees to assist in complying with the rule. The guidance document Is intended as an interim measure until the *Standard Content and Format Guide for Safety Analysis Reports, Regulatory Guide 1.70," is revised to reflect the requirements of the new rule, at which time the guidance in NUREG-0906 would be incorporated into Regulatory Guide 1.70 | |||
( | The guidance document has the following major features: | ||
(1) It identifies the locations in the Safety Analysis Report (SAR) | |||
for providing the evaluation required by the SRP rule and pro- vides a suggested tabular format for identifying the specific areas of design, analysis, and procedure that are different from the Standard Review Plan. The table includes an identifi- cation and summary description of the differences, and a refer- ence to the specific sections of the SAR in which the differ- ences are discussed and evaluated. | |||
( | (2) For applicants subject to the rule, It modifies the present guidance contained in Regulatory Guide 1.70 that they should provide a discussion in the SAR of their conformance with all applicable Regulatory Guides (SAR Chapter 1.8). The appro- priate Regulatory Guides are cited in the acceptance criteria for each individual section of the SRP. Thus, this section (Chapter 1.8) of the SAR would be redundant to the evaluation now required by the SRP rule and an unnecessary burden on applicants. | ||
However, the guid- 32 ance documents notes that in some instances the SRP acceptance criteria are identical to the requirements of the regulations. | (3) It reaffirms that conformance with the SRP, per se, is not a regulatory requirement, but that the specific acceptance criteria of the SRP define methods acceptable to the staff for satisfying the relevant regulations. However, the guid- 32 ance documents notes that in some instances the SRP acceptance criteria are identical to the requirements of the regulations. | ||
Guidance on how to handle this type of difference from the SRP accrp-Ca W ille | Guidance on how to handle this type of difference from the SRP | ||
accrp-Ca W ille l. lalrtu w OFFICEIP z .= 6 8.................. ...... ........................ ....... ............................ ............................ ............................ ..................... | |||
...... ........................ | 21U08..... | ||
....... ..................... | SURNAAMEb ....... ................. ....... ................ ........................ ............... ......... ... ........................ ........................ ............... ................. | ||
....... ..................... | ........................ | ||
....... ..................... | DATEt............. . ................................ ........................................ ........................ ............ ............... ......... ............... ........................ | ||
....... ..................... | NRC FORM 318 (10-80) NRCM 0240 O FFICIA L R EC O RD C OP Y USGPO: 1981-335-960 | ||
SURNAAMEb | |||
....... ................. | - 2 - | ||
....... ................ | (4) It provides examples of evaluations of differences from the SRP | ||
........................ | that the staff considers to be acceptable in technical scope and detail. | ||
............... | |||
......... | Comments on NUREG-0906 are due by December 20, 1982. | ||
... ........................ | |||
........................ | Sincerely, pFtriginal signed by Darrell G. Eisenhut Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Enclosure:-4 As stated OFFICESI....... D B .. . LL1 .. ........................ . .............. | ||
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......................... | DATE) 29..1.8.. 2... _9&L | ||
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........................................ | .................. ........................ ........................ | ||
........................ | NRC FORM 318 (10-80) NRCM 0240 RECORD COPY USGPO:1981-83"9}} | ||
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NRC FORM 318 (10-80) NRCM 0240 O FFICIA L R EC O RD C OP Y USGPO: 1981-335-960 | |||
-2 -(4) It provides examples of evaluations of differences from the SRP that the staff considers to be acceptable in technical scope and detail.Comments on NUREG-0906 are due by December 20, 1982.Sincerely, pFtriginal signed by Darrell G. Eisenhut Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Enclosure:-4 As stated | |||
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RECORD COPY USGPO:1981-83"9}} | |||
{{GL-Nav}} | {{GL-Nav}} | ||
Latest revision as of 03:16, 24 November 2019
OCT 2 6 1982 TO ALL POWER REACTOR LICENSEES/PERMIT HOLDERS, APPLICANTS FOR CONSTRUCTION
PERMITS
Subject: Guidance for Implementing Standard Review Plan Rule (Generic Letter No. 82-aO)
Gentlemen:
On March 10, 1982, the Commission approved a final rule 10 CFR 50.34(g), *Confor- mance with the Standard Review Plan (SRP)." This rule requires power reactor applications docketed after May 17, 1982, to include an evaluation of the facility against the acceptance criteria of the Standard Review Plan (NUREG-0800).
The staff has prepared for public comment the enclosed guidance (NUREG-0906) for licensees to assist in complying with the rule. The guidance document Is intended as an interim measure until the *Standard Content and Format Guide for Safety Analysis Reports, Regulatory Guide 1.70," is revised to reflect the requirements of the new rule, at which time the guidance in NUREG-0906 would be incorporated into Regulatory Guide 1.70.
The guidance document has the following major features:
(1) It identifies the locations in the Safety Analysis Report (SAR)
for providing the evaluation required by the SRP rule and pro- vides a suggested tabular format for identifying the specific areas of design, analysis, and procedure that are different from the Standard Review Plan. The table includes an identifi- cation and summary description of the differences, and a refer- ence to the specific sections of the SAR in which the differ- ences are discussed and evaluated.
(2) For applicants subject to the rule, It modifies the present guidance contained in Regulatory Guide 1.70 that they should provide a discussion in the SAR of their conformance with all applicable Regulatory Guides (SAR Chapter 1.8). The appro- priate Regulatory Guides are cited in the acceptance criteria for each individual section of the SRP. Thus, this section (Chapter 1.8) of the SAR would be redundant to the evaluation now required by the SRP rule and an unnecessary burden on applicants.
(3) It reaffirms that conformance with the SRP, per se, is not a regulatory requirement, but that the specific acceptance criteria of the SRP define methods acceptable to the staff for satisfying the relevant regulations. However, the guid- 32 ance documents notes that in some instances the SRP acceptance criteria are identical to the requirements of the regulations.
Guidance on how to handle this type of difference from the SRP
accrp-Ca W ille l. lalrtu w OFFICEIP z .= 6 8.................. ...... ........................ ....... ............................ ............................ ............................ .....................
21U08.....
SURNAAMEb ....... ................. ....... ................ ........................ ............... ......... ... ........................ ........................ ............... .................
........................
DATEt............. . ................................ ........................................ ........................ ............ ............... ......... ............... ........................
NRC FORM 318 (10-80) NRCM 0240 O FFICIA L R EC O RD C OP Y USGPO: 1981-335-960
- 2 -
(4) It provides examples of evaluations of differences from the SRP
that the staff considers to be acceptable in technical scope and detail.
Comments on NUREG-0906 are due by December 20, 1982.
Sincerely, pFtriginal signed by Darrell G. Eisenhut Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Enclosure:-4 As stated OFFICESI....... D B .. . LL1 .. ........................ . ..............
........................ .......
an:hmc Adl Asent "
SURNAME ................ . . ....... ; ........... .............. .................. ........................ ......................
DATE) 29..1.8.. 2... _9&L
2..... ,
.................. ........................ ........................
NRC FORM 318 (10-80) NRCM 0240 RECORD COPY USGPO:1981-83"9