ML20215L304

Summary of Meeting W/Util & NUS on 870611 in Bethesda,Md Re Adequacy of Tech Specs.List of Attendees,Viewgraphs & Candidate Tech Specs for Consideration During Finalization of Program Encl

ML20215L304
Person / Time
Site:	Rancho Seco
Issue date:	06/22/1987
From:	Knighton G Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-65256, NUDOCS 8706260007
Download: ML20215L304 (25)

Text

{{#Wiki_filter:__ JUN 2 21987 Docket No. 50-312 LICENSEE: Sacramento Municipal Uti7ity I FACILITY: Rancho Seco Nuclear Generating Station

SUBJECT:

MEETING WITH SACRAMENTO MUNICIPAL UTILITY DISTRICT.- (SMUD) ADEQUACY OF TECHNICAL SPECIFICATIONS FOR RANCHO SECO The' subject meeting was requested by NRC in order to understand SMUD's plans witn respect to the NRC's Consultant's critical evaluation of Rancho Seco's Technical Specificaticn (tech specs). The meeting was held in Bethesda, Maryland, at 8:30 a.m., on June 11, 1987. The meeting notice and list of attendee's is attached as Enclosure 1. Slides used by the licensee represen-tatives are attached as Enclosure 2, an NRC staff list of candidate technical specification for consideration during the licensee's finalization of their inprovement program is Enclosure 3, and a set of pages with marginal ) notes marked " proposal" of technical specification currently under NRC staff ) review is Enclosure 4. G. Kalman opened the meeting, noting that the meeting had been requested by NRC to discuss the adequacy of the Rancho Seco tech specs, particularly in light of a recent contractor's report on this subject. He said that, because of the age of the plant and the custom tech specs, Rancho Seco operated under a different set of Tech Specs from those used at later plants, although these j differences had not been a safety concern in the past. Kalman said that the contractor's report did not identify any individual items with major safety significance, but because of the number of potential problems identified, it 1 seemed prudent to take a hard look at the tech specs for safety-significant i issues that might need to be remedied in the near term. He added that there would be substantial problems in adopting the standard tech specs--more problems than one might expect at first glance. Kalman said the purpose of the meeting was to exchange ideas on what could be done to improve the tech specs, and then to ask SMUD to come back at some future date with a proposal i and schedule for r. ear-term tech spec improvements. j l' Mr. John Yinquist described the Rancho Seco Technical Specification Evaluation process. The subject meeting is identified on the flow chart as " Proposed Acceptable Resolution." Mr. Vinquist pointed out that Rancho Seco has had a Technical' Specification-(tech spec) Verification Program in place since February 2,1987 as a result of a 1986 Notice of Violation. The program was designed to assure each line item in the tech specs are implemented, determine tech spec improvements needed and assure tech specs resulting from present outage are made. As of early June, 900 out of 1113 line items in the tech specs had been reviewed for proper procedural support, and all line items were scheduled to be completed by the end of June. J. Miller asked how many line 8706260007 h h 2 PDR ADOCK PDR P

j o items had been found to date without procedural support. R. Colombo responded that about 25 of the 900 line items examined to date had been found to lack explicit procedural support. In response to a question from G. Knighton, Mr. Vinquist said that, where procedures do not exist to support tech spec requirements, new or revised procedures are being prepared. Most of these are now completed..but some are still in progress. When the NRC' consultant report was forwarded to SMUD they included its review under the Technical Specification improvement Task Force. Mr. Vinquist reported that many of the findings in the NRC Contractor report had already been identified by the Technical Specification Improvement Task Force. Mr. Ron Colombo discussed the results of their efforts to date concerning Technical Specification improvements. He presented the 17 improvements shown in the slides in Enclosure 2. They all reflect significant { technical specification concerns and the staff supports'the licensee j addressing them prior to restart. In addition Mr. Colombo indicated that an j additional 15 technical specifications identified by the task force and/or the .I contractor report are currently in the NRC review process for license amendments to revise the Technical Specifications. These are identified by the marginal note " proposed" in enclosure 4. Mr. Colombo said 25 to 30 percent of the contractor's comments currently could be resolved by looking elsewhere in the RSNGS specs. About 80 proposed amendments to tech specs have been submitted to NRC, but have not yet been approved. It was noted also by.Mr. Colombo that the RSNGS operators know these tech specs, and major changes would require a major effort in re-training the operators. It was agreed that the improved B&W J 1 tech specs providing all information in one place is eventually the way to go. The staff found the identified technical specification changes being addressed prior to restart as a very positive response to the identified concerns. The staff provided a working list of hRC Contractor identified findings that they had selected as candidates for early revision. This list was provided to the licensee for his use in arriving at his final Technical Specification Improvement Program resolution. Mr. Vinquist pointed out that the list of.17 technical specification improvements will be addressed prior to restart. Action items were defined as follows: j 1 1. SMUD should prepare a schedule.for implementation of the 17 items on the list presented by R. Colombo and any items from the staff working I list specifically noting which of the items would be implemented prior to restart. i l l l

r . 2. SMUD should described the nature of any interim implementation plans that would be applicable to those items where final implementation is not planned until after restart. 3. SMUD should formally document their commitment to adopt the improved 1 tech specs now being drafted by B&W Owners Group. i 4. All post restart tech spec changes scheduled for dates subsequent to the licensee's submittal of the living schedule amendment will be included in that living schedule. Mr. Vinquist stated that SMUD plans to implement the B&W Owners Group Improved Standard Technical Specifications when they are available. That commitment will also be included in the living schedule amendment. Originalsignid byfA George W. Knighton 1 George Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated cc: See Next Page DISTRIBUTION DocketsFile, ACRS (10) R. Barrett NRC & Local PDR HBClayton(RI) A. Thadani PDf5 Reading T0 Martin -ED0 E. Butler FMiraglia D. Crutchfield C. Rossi G. Holahan D. Kirsch (V) R. Starostecki GKalman ECyellias S. Newberry-E00 GKnighton OGC-Bethesda D. Tondi EJordan JMiller F. Hebdon Echow SMDavis KCampe CTMyers JTrotter FStetson JVinquist RColombo

• See Previous concurrence
• NRR/0TFB
• DRSP/D:PDV JRMiller:ts GWKnighton 6/17/87 6/17/87 0FFICIAL RECORD COPY

1 ] i Mr. Vinquist pointed out that the list of 17 technical specification improvements will be addressed prior to restart. Action items were defined as follows: 1. SMUD should prepare a schedule for implementation of the 17 items on i the 1 sit presented by R. Colombo, specifically noting which of the 1 items would be impelented prior to restart. 2. SMUD should described the nature of any interim implementation plans that would be applicable to those items where final implementation is I not planned until after restart. l 3. SMUD should formally document their commitment to adopt the improved tech specs now being drafted by B&W Owners Group. 4. All scheduled T.S. changes post restart for dates subsequent to the licensee's submittal of the living schedule amendment will be included in that living schedule. Mr. Vinquist stated that SMUD plans to implement the B&W Owners Group Improved Standard Technical Specifications when they are available. That commitment will also be included in the living schedule amendment. George Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated cc: See Next Page DISTRIBUTION Docket File ACRS(10) NRC & Local PDR HBClayton(RI) PD#5 Reading T0 Martin -ED0 GKalman ECyellias GKnighton 0GC-Bethesda EJordan JMiller EChow SMDavis KCampe CTMyers JTrotter FStetson JVinquist RColombo NRR TFB DR

PDV JP, Filler:ts GW i hton 6/

l/87 6/ (/}87 i p} OFFICIAL RECORD COPY \\

, 2..SMUD should described the nature of any interim implementation plans that would be applicable to thoce items where final implementation'is i not planned until after restart.

3. ' SMUD should formally document their commitment to adopt the improved tech specs now being drafted by B&W Owners Group.

4. All post restart. tech spec changes scheduled for dates subsequent to the licensee's submittal of the living sche &J1e amendment will be included in that living schedule. Mr. Vinquist stated that SMUD plans to implement the B&W Owners Group Improved Standard Technical Specifications when they are available. That commitment will also be included in the living schedule amendment. Io,*jj George Knighton, Director i fpt#$ Project Directorate V l cy g-Division of Reactor Projects - III, b stA( IV, Y and Special Projects (a.. y 9.-

Enclosures:

As stated cc: See Next Page DISTRIBUTION Docket File ACRS(10) NRC & Local PDR HBClayton(RI) PD#5 Reading T0 Martin -EDO

g. Me f Kalman ECyellias GKnighton 0GC-Bethesda A TAes/ad,'

EJordan JMiller E.S M ee EChow SMDavis KCampe CTMyers b 0##' [, Jia/oJYDCbi JTrotter FStetson JVinquist RColombo 3,gg,g,gy_ggo NRR/0TFB. DRSP/D:PDV M bd8 JRMiller:ts GWKnighton 6 Me/pe/eq 6/' /87 6/ /87 0FFICIAL RECORD COPY

1 1 Docket No. 50-312 LICENSEE: Sacramento Municipal Utility FACILITY: Rancho Seco Nuclear Generating Station

SUBJECT:

MEETING WITH SACRAMENTO MUNICIPAL UTILITY DISTRICT - (SMUD) ADEQUACY OF TECHNICAL SPECIFICATIONS FOR RANCHO SEC0 j The subject meeting was requested by NRC in order to understand SMUD's plans with respect to the NRC's Consultant's Critical evaluation of Rancho Seco's Technical Specification. The meeting was held in Bethesda, Maryland, at 8:30 a.m., on June 11, 1987. The meeting notice and list of attendee's is attached as Enclosure 1. Slides used by the licensee representatives are attached as Enclosure 2, and an NRC staff list of candidate technical specification for consideration during the licensee's finalization of their improvement program is Enclosure 3, a set of pages with marginal notes " proposal" of technical specification currently under NRC staff review is G. Kalman opened the meeting, noting that the meeting had been requested by NRC to discuss the adequacy of the Rancho Seco tech specs, particularly in i light of a recent contractor's report on this subject. He said that, because of the age of the plant and the custom tech specs, Rancho Seco operated under a different set of rules from those used at later plants, although these differences had not been a safety concern in the past. Kalman said that the contractor's report did not identify any individual items with major safety significance, but because of the number of potential problems identified, it seemed prudent to take a hard look at the tech specs for safety-significant issues that might need to be remedied in the near term. He added that there would be substantial problems in adopting the standard tech specs--more problems than one might expect at first glance. Kalman said the purpose of the meeting was to exchange ideas on what could be done to improve the tech specs, and then to ask SMUD to come back at some future date with a proposal and schedule for near-term tech spec improvements. Mr. John Vinquist described the Rancho Seco Technical Specification Evaluation process. The subject meeting is identified on the flow chart as " Proposed Acceptable Resolution." Mr. Vinquist pointed out that Rancho Seco has had a Technical Specification (T.S.) Verification Program in place since February 2, 1987 as a result of 1986 notice of violations. The program was designed to assure each line item in the T.S. is implemented, determine T.S. improvements needed and assure T.S. resulting from present outage are made. As of early June, 900 out of 113 line items in the tech specs had been reviewed for proper procedural support, and all line items were scheduled to be completed by the end of June. J. Miller asked how many line items had been found to date without procedural support. R. Colombo responded that about 25 of the 900 line items examined to date had been found to lack explicit procedural support. In response to a question from Knighton, 'linquist said that, where procedures do not exist to support tech spec requirements, new or revised procedures are being prepared. Most of these are now completed, but some are still in progress. When the NRC consultant report was forwarded to SMUD they included its review under the Technical Specification Improvement Task Force. i

1. 'd Mr. G. Carl Andognini Rancho Seco Nuclear Generating Chief Executive Officer, Nuclear Station Sacramento Municipal Utility District CC: Mr. David S. Kaplan, Secretary Mr. John Bartus and General Counsel Ms. JoAnne Scott Sacramento Municipal' Utility Federal Energy Regulatory Commission District 825 North' Capitol. Street, N. E. 3 6201 S Street Washington, D.C. 20426 P.-0. Box'15830 Sacramento, California 95813 l Thomas A. Baxter, Esq. . j Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W. Washington, D.C. 20037 Mr. John V. Vinguist Acting Manager, Nuclear Licensing s Sacramento. Municipal Utility District-j Rancho Seco-Nuclear Generating Station 14440 Twin Cities Road i Herald, California 95638-9799 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Mar 3'and 20814 Resident Inspector / Rancho Seco c/o U. S. N. R. C. 14440 Twin Cities Road I Herald, California 95638 Regional Administrator, Region V i U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 I Mr. Joseph 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814 Sacramento County: Board of Supervisors 827 7th Street, Room 424 l Sacramento, California 95814 Ms. Helen Hubbard P. O. Box 63 Sunni, California 94586 ...a

S c p yJ!? W37 Docket No.: 50-312 MEMORANDUM FOR: George W. Knighton, Director i Project Directorate V Division of Reactor Projects - III/IV/V i & Special Projects FROM: George Kalman, Project Manager Project Directorate V Division of Reactor Projects - III/IV/V & Special Projects ]

SUBJECT:

FORTHCOMING MEETING WITH THE SACRAMENTO MUNICIPAL UTILITY DISTRICT DATE & TIME: 8:30 a.m. to 1:00 p.m. June II, 1987 LOCATION: B&W Conference Room, Room 220 Landow Building 7910 Woodmont Avenue Bethesda, Maryland PURPOSE: To discuss adequacy of the Rancho Seco Technical Specifications ~ PARTICIPANTS: NRC (Utility) l G. Knighton J. Vinquist, et. al. J. Miller G. Kalman ori fnel signed by f George Kalman, Project Manager Project Directorate V Division of Reactor Projects - III/IV/V & Special Projects Enclosure (s): As stated cc: See next page DR PDV PDV GKa nian:cd ighton 6/)/87 6/ /87

• Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy",

43 Federal Register 28058,6/28/78.

RANCHO SECO MEETING. ATTENDANCE LIST-j .a .j NAME-ORGANIZATION .J George W. Knighton .NRC/NRR/PDV. Jim Miller NRC/NRR/TSB-Ed Chow NRC/NRR/DREP/PRAB Sarah M.. Davis NRC/NRR/PRAB-Kaz Campe NRC/NRR/PRAB E. Cyellias' NRC/RES U 1 C. T. Myers-RV/ Resident Inspector J. 0. Trotter NUS F. T. Stetson NUS . John Vinquist SMUD/ Mgr. Nuclear Licensing Ron Colombo SMUD/ Reg Compliance Supt. l 1

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O N C C OA T T S R F O E LE E RR I P V K R J EG R L S 3 R O MO I U E A 1O R UR 1 P D T C P NP 1 a E 5 E a a ( N

l .c s. Specific Technical Specification Improvements Included:

1) Add _a shutdown requirement if the Reactor Coolant System activity exceeds 43/E.

(RSTS 3.1.4).

2) Add a new Technical Specification to address " Ultimate Heat Sink". (STS 3/4.7.5).

3) Rewrite the RCS Leakage Specification to include time and action criteria for each. statement.

(RSTS 3.1.6).

4) Add a time limit for inoperable control rod limits to reduce power to specification.

(60% RSTS 3.5.2).

5) Add statement for restoration / evaluation if heatup/cooldown' limits' are exceeded.

(RSTS 3.1.2).

6) Add specific values and tolerances and acceptance criteria for battery testing.

(RSTS 4.6.4.d)

7) Add a' requirement to close the EH0V block valve if the EMOV becomes inoperable.

(RSTS 3.1.1.4).

8) Add a requirement that a RCP be in operation during operation greater than 280*F.

(RSTS 3.'1.1.1).

9) Add a requirement that a decay heat pump be in operation continuously when RCP's are not running.

(1 hour action) (STS 3.4.1.2).

10) Add to definitions " Policy" statements i.t., change of modes to be completed within specified time limits ani LCO restrictions to a mode where Technical Specification does not_ apply.

(STS 3.0.1, STS 3.0.2, STS 3.0.3, STS 3.0.4),

11) Decrease shutdown criteria for " Secondary System Activity" from 12 hours to HSD to HSB in 6 hours and cold shutdown in the following 30 hours.

(RSTS 3.10).

12) Add a surveillance requirement for testing the EMOV block valve additional to Table ~4.1-2 item 15.

~

13) Add a s'urveillance requirement for logging RCS temperature at 30' minute intervals'during hettup and cooldown transitions.- (STS)

14) Add a surveillance requirement that valves outside the containment be-checked once per 31 days.

(STS 4.6.1.1).

15) Add a surveillance to verify shutdown xnargin within 1 hour and every 12 hours thereafter:upon loss of all source range instrumentation.

(STS-Table 3.3-1)'.

16) Add a specification for chlorine detectors on CRHVAC. --(STS 3/4.3.3.7).

17) Add an LCO to go to decay heat cooling 'if both. pressurizer code safeties become inoperable.

(STS 3/4.4.2).

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