IR 05000206/1986033

Insp Rept 50-206/86-33 on 860618-19.No Violation Noted. Major Areas Inspected:App R Fire Protection Program

ML20202G811
Person / Time
Site:	San Onofre
Issue date:	06/25/1986
From:	Qualls P, Ramsey C, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20202G798	List: IR 05000206/1986033 ML20202G793
References
50-206-86-33, TAC-54880, NUDOCS 8607160109
Download: ML20202G811 (6)

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l U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Report N /86-33

_ . Docket N .

License N DPR--23 Licensee

Southern California Edison Company P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770'

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Facility Name: San Onofre Nuclear Generating Station Unit 1

Inspection at

San Clemente, California Inspection conducted: June 18-19, 1986

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Inspectors:

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P. Qualls, Reactor Inspector Date Signed Nw  % Us. vZrt C. Ramsey, ReactorlInspector Date Signed

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Approved by: -

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T. Young Jr., Ch

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f- Date-Signed Engineering Sect n Inspection During the Period June 18-19, 1986 (Report No. 50-206/86-33)

Areas Inspected: An unannounced inspection of the Unit 1, 10 CFR 50, Appendix R. Fire Protection Program. This inspection was to follow-up on items left open in IR 50-206/86-24. The inspection involved IE Manual Chapter TI 2515/62, Revision Results: In the areas inspected, no violations of NRC requirements were identifie >

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8607160109 860701 PDR O ADOCK 05000206 '

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DETAILS

. Persons Contacted Southern California Edison Company

• M. D. Wharton, Deputy Station Manager

• E. Nunn, Manager of NGS

• H. Peacor, Station Emergency Preparedness Manager

• A. Couser, Compliance Engineer

• J. Schramn, Coordination Supervisor G. Engman, Electrical Engineer

• D. Barreres, Supervising Engineer

• R. Ornelas, Licensing Engineer

• D. A. Dack, Quality Assurance Engineer

• R. K. Richter, E.P. Engineer K. Milas, Mechanical Engineer

• T. A. Mackey, IR Compliance Supervisor M. P. Short, Project Manager M. lR. Williams, Station Technical J. Huey, Construction Superintendent

• R. L. Erickson SDG&E Senior Engineer Impell Corporation

• K. Scown, Manager Fire Protection

• P. Hypner, Supervising Engineer

• Denotes those attending NRC exit meeting on 6/11/198 . Clarification to Inspection Report No. 50-206/86-24 The inspectors identified several minor inaccurate statements that were made in Inspection Report No. 50-206/86-24 due to typographical error, et These statements have no significant impact on the results of the NRC's assessment of_the licensee's compliance with Appendix R to -

10 CFR 5 However, the following clarifications are provided: Paragraph 2.B(1)(a) incorrectly identified Zone 1-AB-(-3)-2A as Area 1-AB-(-3)-2A. Also, the last sentence in this paragraph states in part, "This method of achieving reactor coolant makeup involves a blowdcwn into the suppression pool..." The reference to suppression pool is incorrect. The correct words should be " Pressurizer relief tank". <

Paragraph 2.B(1)(b) incoErectly identified Zone 1-YD-(-14)-4D as

~ ' Area 1-YD-(-14)-4 C? -Paragraph 2.B(1)(C) incorrectly identified Zone 1-YD-(-7)-4E as area 1-YD-(-7)-4E and omitte'd a discussion on the potential loss of equipment and component required for hot shutdown due to a fire in this zone. 'The' details of this discussion are provided on page 4 of supplemental SER No. r- ,

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, 2 Paragraph 2.B(1)(d) incorrectly identified Zone 1-TB-35-9B as Area 1-TB-35-9 Paragrap'h 2.B.(2) incorrectly identified east and west penetration areas 1-YD-20-4A and 1-YD-20-4B as areas 1-CO-(-10)-4A and 1-CO-(-10)-4B respectivel Paragraph 3 states in part "these analyses were not submitted to the NRC for prior review and approval. This statement is incorrec The licensee did submit these analyses to the NRC for review and i approval by letter dated December 1985 and April 198 Paragraph 3.B indicates that the licensee submitted an exemption

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request to the NRC for area 1-PB-14-25 prior to the inspection. This is incorrect. The licensee decided that an exemption request was not needed for this area based on a compliance evaluation completed

, for the area, therefore, the request was not submitte Paragraph 3.A indicate that the licensee was to revise compliance evaluations for fire areas 1-AB-14-35; 1-FH-14-7; 1-PB-14-8 and 1-PB-14-26. However, upon re-analysis, the licensee elected to withdraw compliance evaluations for these areas based on their compliance with sections III.G.2 and'Ill.G.3 of Appendix . Licensee Actions on Previous Inspection Findings -

To follow-up on previously identified. inspection concerns the inspectors verified the appropriateness of licensee actions on the>following

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inspection finding . (Closed) Open Item 206/85-11-0 ,

ProcedureNo.S0-123-XIII-13specifiesinddequate'controlof combustible , During the inspection, the licensee agreed to revise this procedure-by June 27,.1986. However,.the acceptability of.the revised procedure is interrelated to the acceptability of the licensee's Appendix R complielpe evaluations that are discussed in Open Item No. 50-206/86-24-Os (paragraph 3 of this report). Subsequent to the inspection, the licensee contacted Region V by phone on

June 30, 1986 to discuss the procedure. 1 Region V received the i revised procedure on July 1, 1986 and found it acceptable. This item is closed based on the licensee's. corrective action (Closed) Information Notice No. 85-09, Isolation Transfer Switches The licensee conducted an evaluation to determine if a problem j existed similar.to the problem identified in Information-Notice 85-09. Their conclusion is documented in an internal document SCE ISEG evaluation, Log Numbar 85-ISEG-04 The NRC Appendix R inspection team also inspected this. area in the May 1986 audit. Neither evaluation found any discrepancies. This ;

item is closed based on the licensee's corrective actions take '

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. (Closed) Part 21 Report No. 86-14, Automatic Sprinkler Model "C" Deluge Valve Failure Certain 6 inch Model "C" deluge. valves were reported to be vulnerable to repeated failures by Automatic Sprinkler Corporation. This Part 21 report'was issued to apprise licensee of continuing problems with.the Model "C" deluge value The licensee, identified'that the Mo'd'el "C" automatic sprinkler deluge valves utilized:at SONGS are, included in the serial numbers identified in.the Automatic' Sprinkler Corporation notic Therefore, the licensee implemented the recommended lubricant maintenance program'for the valves and according to the licensee's Independent Safety Engineering Group Document No. IEN 84-16, dated April 16, 1984, no failure of the valves to actuate has been observed during biannual surveillance tests. This item is closed based on the licensee's corrective actions take (Closed) Open Item 206/86-24-01, Functional Testing of the Dedicated Shutdown System The inspectors inspected, in detail, five of the nineteen procedures which tested the dedicated shutdown systems. The inspectors verified technical adequacy, quality assurance, approvals, reviews and test equipment adequacy. Procedures listed below were inspected:

S01-PE-3009.05-4 DSD Diesel Gen., Swgear Encl Fire Pro S01-PE-3009.06-1 DSD Diesel Generator Mcchanical 501-PE-3009.10-1 N Chrgng PMP VCC-G-8A M/N/FLW Recire Line S01-PE-3050.01-1 3rd Aux Feedwater Pump S01-PE-3341.15-1 Appendix R, Reactor Cooling System Sampling Mo The licensee had indicated that all 19 procedures were complete with the exception of S01-PE-3341.15-1 which would be completed in Mode The four procedures which the licensee had indicated were couplete was verified. The last procedure was verified to be complete with the exception of the testing which needed to be done with the reactor at operating pressure. This item is closed based on the licensee's corrective actions take (Closed) Open Item 206/86-24-02, Incomplete Modifications The inspector verified the completion of a randomly selected number of the modifications which were outstanding at the time of inspection 86-24. The modifications were complete with proper acceptances signed off. The licensee identified that four radios which they intend to install to improve communications had not yet been received. The Appendix R team found that the existing plant communications were adequate and that the additional radios were only for operator convenience. All other modifications were complete. This item is closed based on the licensee's corrective actions take . _ _ _

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. (Closed) Open Item 206/86-24-03, Supplement Procedures The inspectors verified by direct observation that the procedures identified by the Appendix R team were-complete and issued. The

" recipe" procedures which augment the normal shutdown procedures are in place. 1This item is closed based on the licensee's corrective actions take (Closed) Open Item 206/86-24-04, Operator Training The NRC training staff reviewed the operator training for the Appendix R procedures. 'Their conclusions are documented in Inspection Report 50-206/86-28. .The_ training is scheduled to be complete on 6/25/86. This item is closed based on the licensee's corrective actions take (Closed) Open Item 206/86-24-05, Revised Compliance Evaluations Performed to Demonstrate Compliance With Section III.G.1 of Appendix R.;

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The inspectors received.the licensee's-revised compliance .

evaluations in the Region V office on June, 13,,1986.(forwarded'by letter dated June 6,1986 - H. E.~ Morgan, :S' CEC to J.' B. Martin-NRC) .

The inspector's in-office-review of the evaluations began on-June 16, 1986 and concluded at the site.during this inspection. The adequacy of the evaluations for all eight fire zone / areas (1-TB-8-9A; 1-TB-35-9B; 1-PB-20-11's 1-PB-20-12; 1-PB-20-13; ,

1-PB-14-25; 1-PB-56-33 and 1-AB-11-34)4was_ questioned by_the inepectors.- By memorandum dated June,18,,1986, Region V gave review responsibility for the evaluations to NRR. Subsequent to -

the on site inspection, the compliance evaluations were reviewed and approved by the NRR staff in' a. letter dated' June 27,+198 This item is closed, s (Closed) Open Item 206/86-24-06, Required Exemption Request This item was referred to NRR for resolution in Inspection Report No. 206/86-24. Subsequent to the on site inspection, the exemption requests were reviewed and approved by the NRR staff in a letter to the licensee dated June 27, 1986. This item'is close (Closed) Open Item 206/86-24-07, Breaker Coordination and High-Impedance Fault Analyses The licensee modified the protective device settings for breaker numbers 12CO3, 11C03, 1118, 1218, 1203, 1129, 1229 and 1310 to satisfy this concern. This item is closed based on the licensee's corrective actions take c-- , _ _

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' (Closed) Open Item 206/86-24-08,MiIlabeledRaceways Thelicenseeconducteda32%walkdownofhis'Un4E1racewayswhich are included in the Appendix R data base. Two. additional tray segments were found mislabeled. 'The licensee's Electrical Citeuit Schedule.(ECS) which shows cable routings through the different raceway segments make the possibility remote that a cable would be in the wrong tray due to the number of correctly labeled segments that a cable must pass through before entering and after leaving a mislabeled segment. The licensee's response is documented in a letter to Region V dated June 11, 1986. This item is closed based on the licensee's corrective actions ~take (0 pen) 206/86-24-09, Procedure Revisions These procedures, S0123-V-5 and QA procedure E&C 24-10-5 are scheduled to have the revision completed by October 1, 1986, which incorporates changes to insure Appendix R is considered when making plant modifi-cations. This item remains open pending further Region V verificatio . Emergency Lighting During the team inspection conducted May 19-23, 1986 the inspectors acknowledged that the required 8-hour battery power supply emergency lighting units were installed in areas needed for operation of safe shutdown equipment and in access and aggress routes thereto. However, pre-operational testing of the units and determination of acceptable illumination level was incomplete at that tim During this inspection, the licensee indicated that pre-operational testing was complete and additional lighting was installed at the dedicated shutdown panel to increase illumination levels at the pane The licensee stated that based on a visual walkdown of lighting, adequate illumination was provided to safely shutdown the plan . Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involve some action on the part of the NRC or licensee or both. Open items disclosed during the inspection are discussed in Paragraphs 3.A. 3.1 and . Exit Interview The inspectors met with the licensee representatives at the conclusion of the inspection on June 19, 1986, and summarized the scope and findings of the inspection. The licensee acknowledged the statements made by the inspector ,

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