IR 05000206/1985002
| ML13323A947 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/06/1985 |
| From: | Sherman C, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323A946 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 50-206-85-02, 50-206-85-2, NUDOCS 8502260586 | |
| Download: ML13323A947 (5) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report N /85-02 Docket N License N DPR-13 Licensee:
Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Unit 1 Inspection at:
San Onofre Nuclear Generating Station Inspection conducted:
January 28-31, 1985 Inspector: & u 4 Z't4 t4'
/ :Z 4/
C. I. Sherman, Radiation Specialist Date Signed Approved By:
2/6
__
G. P. '
s, Chief Date Signed Facilit Radiological Protection Section Summary:
Inspection on January 28-31, 1985 (Report No. 50-206/85-02)
Areas Inspected: A special inspection was conducted to review the licensee's action in implementation of ThI Action Plan item II. Results:
Of the areas inspected, no violations or deviations were identifie PDR ADOCK 05000206 G
PDR-
DETAILS Persons Contacted
- J. Haynes, Station Manager J. Albers, Units 2/3 Health Physics Supervisor
- E. Bennett, Quality Assurance Engineer
- D. Brevig, Station Chemistry Manager P. Knapp, Station Health Physics Manager
- J. Reilly, Station Technical Manager
- R. Reiss, Quality Assurance Engineer
- D. Schone, Site Quality Assurance Manager
- M. Short, Unit 1 Project Manager
- M. Speer, Station Compliance Engineer
- T. Mackey, Jr., Compliance Supervisor
- W. Marsh, Plant Superintendent, Unit 2/3
- A. Abusamra, Chemistry Engineer
- J. Wambold, Training Manager
- D. Herbst, ISEG Manager
- P. King, QA Supervisor
- P. Croy, Manager, Compliance
- H. Morgan, Operations Manager
- J. Kelley, Radwaste Supervisor F. Lyons, CE F. Dati, Volt
- Denotes those present at the exit interview on January 31, 198 In addition to the individuals identified above, the inspector met and held discussions with other members of the licensee's and contractors staf.
Licensee Action on Previous Inspection Findings NRC Inspection Report 50-206/84-16 described the status of the licensee's post accident sampling system (PASS) and the proposed alternate methods which would be utilized until the PASS is complete The licensee, in response to NRC Inspection Report 50-206/84-16 (by letter dated October 9, 1984), stated that, an undiluted grab sample capability would be provided by January 7, 1985, that this capability would be augmented with an alternate PASS methods procedure and that procedures associated with the grab sample would be completed by mid-November 198 The licensee also indicated that this information was provided (letter dated August 14, 1984, M. Medford (SCE) to W. Paulson) to NR NRR's response incorporated the licensee's commitments into Amendment No. 85 which conditioned Operating Licensee DPR-13 (Paragraph 3.k) as follows:
-2 Post Accident Sampling System (PASS), NUREG-0737, Item II. (1) By July 1, 1986 or startup from the Cycle IX refueling outage, whichever is earlier, SCE shall install a PASS and implement a post-accident sampling program at San Onofre Unit (2) Prior to the date in (1) above or until the PASS is operable, SCE shall maintain in effect those compensatory measures described in the SCE letter dated August 14, 198 The basis for this amendment was a series of submittals by the licensee dated May 1, 1984, June 28, 1984 and August 14, 1984 providing information and justification to support the delay in completing the PASS. As stated in the Safety Evaluation Report supporting amendment No. 85, "the key to the compensatory measures is completion of the undiluted grab sample capability...."
This SER provides a supporting basis for the above amendment. This basis describes the licensee's proposed alternate methods for rapid assessment of core damage. These methods include use of the two containment high range radiation detectors installed to meet TMI action plan item II.F.1.3 for monitoring containment atmosphere radioactivity and the hydrogen monitors installed to meet TMI action plan item II.F.1.6. Item II.F.1.3 has been inspected (inspection report 50-206/84-16) and is considered close This inspection was conducted to verify implementation of license condition 3.k(2), namely that compensatory measures described in the SCE letter dated August 14, 1984 are maintained in effect. The August 14 letter identified the following compensatory measure o Completion of undiluted grab sample capability by January 7, 198 o Procedures to support sampling and offsite shipment of an undiluted grab sampl o Core damage assessment procedur o Alternate methods of Post Accident Parameter Sampling when necessar Accordingly, this inspection verification focused on the above area The installation was verified by examination of construction completion and test documents, verification of system operability and verification of equipment, training and procedures to support sampling. Shipment capability was verified by review of the shipping procedures, shipping containers and discussion with personne Documents that were examined included a
San Onofre Commitment Register System;
-3 Chemistry Procedures SO-123-III 8.0, 'Post Accident Sampling Program and Analytical Requirements'
8.3.1, 'Unit 1 Sampling.
.
.
for the PASS 8.8, ' Alternate Methods.
.
.';
General Station Order SO 123-G-19, 'PASS Program';
o Health Physics Procedures SO-123-VII 8.1.3, 'Handling and Storage of Radioactive Waste Packages'
8.11, ' Movement of Emergency Samples at SONGS'
8.11.1, 'Handling and Storage of undiluted PASS Samples'
o Memo to file from R. Krieger, dated January 9, 1984;
Field Surveillance Report, No. CH-006-85, dated January 3, 1985; o
Emergency Support Organization Program Manual, Appendix B, Table 15 Attachment 5 & 6, 'San Onofre Unit 1 Procedure for Core Damage Assessment Using Radiological Samples, Revision 7, dated October 10, 1984; o
Radiological Exposure Permit No. 00050; o
Startup Test Package SO1-AC-84-094, 'Obtaining an undiluted grab sample with the PASS';
NRC Certificate of Compliance Dated March 29, 1984 No. 9181; o
0 & M Manual for the NUPAC PAS-2 container; o
Training outline RW-002, 'PASS Overview and Preparing PAS-2 Cask and.
.
.
for Offsite Shipment';
o SCE Engineering Drawing (P&ID) Nos. 5159580-0, 5178601-2, 5178621-2, 5178150-1, 5180768-0; o
Training records for 25 HP and 9 Chemistry Personne Based on observation, discussion with licensee and other personnel and review of documents, the above areas are considered acceptabl In addition, the licensee's provisions for obtaining analysis of grab samples of Unit 1 reactor coolant and containment atmosphere were examined to verify that the criteria of NUREG-0737 item II.B.3 could be met in the interim period until the PASS is finishe Specifically, the following items were examined or verified:
o Shielding Envelope for Sample Carrier (GDC 19);
Time for shipment, preparation, transport and analyses;
-4 o
Quantification of dissolved gases in unpressurized reactor coolant samples; o
Equipment for backup sampling to meet the 1 per day/7 day-1/week criteria; o
Sample system purge capability, return lines and representative sample capability; With respect to the above criteria, the following were note Time for shipment will be evaluated in a drill involving transport of a simulated sample in the PAS-2 cask to the General Atomic Company. This drill will be conducted at a future dat The minimum time estimated by the.inspector for sampling, transport and analysis will be greater than 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Dissolved gas quantification will not be possible for PAS until the final PASS system is complete The licensee is procuring a second PAS-2 cask which will be positioned on site. Any additional samples necessary will have to be taken as diluted samples in order to meet the one per day for seven day criteri The licensee is working a design change to improve system purge capability. PASS uses the same sample lines as the normal sample syste The areas described above related to NUREG-0737 were considered by the inspector as acceptabl Based on review of records, discussion with personnel and observation of the PASS system the inspector concluded that the requirements of licensee condition 3.k were met and that the licensee's programs provided an acceptable level of confidence that the intent of NUREG-0737 item II.B.3, to provide information on core damage could be me Inspection of the In line PASS will be performed as part of the routine inspection program program following return from the cycle IX refueling outage. This matter is considered close No violations or deviations are identifie.
Exit Interview The inspector conducted an exit interview on January 31, 1985 at the conclusion of the inspection with the individuals denoted in paragraph 1 of this report. The inspector summarized the scope and findings of the inspection at that time.