ML16341D803
| ML16341D803 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/26/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML16341D802 | List: |
| References | |
| GL-83-28, NUDOCS 8607090452 | |
| Download: ML16341D803 (6) | |
Text
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>*+~ UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION REPORT GENERIC LETTER 83-28, ITEMS 3.1.3 AND 3.2.3 POST-MAINTENANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS) DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-275 .Generic Letter 83-28 (Ref.
- 1) describes intermediate term actions to be taken by licensees and applicants to address the generic issues raised by the two ATWS events that occurred at Unit 1 of the Salem Nuclear Power Plant.
This report is the NRC staff evaluation of Unit 1 responses for Items 3. 1.3 and 3'.3 of the Generic Letter, submitted by Pacific Gas and Electric Company (PG8E), the licensee for the Diablo Canyon Nuclear Power Plant, Units 1 and 2. The documents reviewed as part of this evaluation are listed as references at the end of this report. In its evaluation of the submittals, the staff was assisted by its consultant, the Idaho National Engineering Laboratory (EGEG Idaho), who prepared the attached report (Attachment A). The staff concurs with the conclusions stated in the report but notes that the report applies only to Diablo Canyon Unit l. A separate evaluation will be prepared for Unit 2. The requirements for Items 3. 1.3 and 3.2.3 are identical with the exception that Item 3. 1.3 applies these requirements to the Reactor Trip System components and Item 3.2.3 applies them to all other safety-related components. Because of this similarity, the responses to both items were evaluated together. In accordance with Generic Letter 83-28, licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which can be demonstrated to degrade rather than enhance safety. Appropriate changes to these test requirements, with supporting justification, shall be submitted for staff approval. PGEE responded to these requirements regarding Diablo Canyon Unit 1 with submittals dated November 7, 1983 (Ref. 2), January 2, 1985 (Ref. 3) January 24, 1985 (Ref. 4), and March 20, 1986 (Ref. 5). The licensee stated in these submittals that there were no post-maintenance testing requirements in the Technical Specifications for either the reactor trip system or other safety-8607090452 860b26 PDR ADOCK 05000275 I P PDR ~ ~ related components which degraded safety. The staff and its consultant have reviewed the information provided by PGSE and conclude, based on the licensee's statement that no post-maintenance test requirements that degrade safety are in Technical Specifications, the licensee's responses are acceptable for Items
- 3. 1.3 and 3.2.3 of Generic Letter 83-28.
A separate evaluation will be issued for Unit 2. e Isa ~ ~ i
REFERENCES:
1.
NRC Letter, D..G ~ Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, "Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
a,4a 2.
Letter, J. 0. Schuyler, Pacific Gas and Electric Co., to D.
G. Eisenhut, NRC, "Diablo Canyon Units 1 and 2, Generic Letter 83-28, Required Actions Based on Generic Implications of ATWS Event,"
November 7, 1983.
3.
Letter DCL-85-002, J.
D. Shiffer, Pacific Gas and Electric Co., to G.
W.
- Knighton, NRC, "Diablq Canyon Unit 1, Generic Letter 83-28, Item 3. 1-Post Maintenance Testing," January 2,
1985.
4.
Letter DCL-85-025, J.
D. Shiffer, Pacific Gas and Electric Co., to G.
W.
- Knighton, NRC, "Diablo Canyon Units 1 and 2,'Updated Status and Schedule for Response to Generic Letter 83-28 and Additional Information,"
January 24, 1985.
5.
Letter DCL-86-074, J.
D. Shiffer, Pacific Gas and Electric Co., to S.
A.
- Varga, NRC, "Diablo Canyon Unit 1, Generic Letter 83-28, Item 3.2,"
March 20, 1986.
4 ~