IR 05000312/1985009

Insp Rept 50-312/85-09 on 850327-0403.No Violation or Deviation Noted.Major Areas Inspected:Implementation of Selected TMI Action Items

ML20128D271
Person / Time
Site:	Rancho Seco
Issue date:	04/26/1985
From:	Ivey K, Kanow L, Miller L, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20128D240	List: IR 05000312/1985009 ML20128D234
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.F.1, TASK-TM 50-312-85-09, 50-312-85-9, GL-82-33, NUDOCS 8505280549
Download: ML20128D271 (7)

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U. S. NUCLEAR REGULATORY COMMISSION ~

REGION V

' Report N '50-312/85-09

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-Docket N . License N DPR-54 +

Licensee: Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 a Facility Name: Rancho Seco Unit 1 Inspection at: Herald, California (Rancho Seco dite)

Inspection conducted: March 27 - April 3 1985

. Inspectors: a ]$ 2ff K. D. Ivey', Jr. , Reactor Ins c orN D6te Aigned s

L. R. Kanow, Reactor Inspe tor '

b V Date/ Signed Approved By: D T. Yo 'ng, 'Jr. , f 'ef , Engin r Sh: tion Da'te 41gned eI L. Y.' Miller, Chie'f, Reactor Projects Section 2

% s-Date Signed Summary:

. Inspection between March 27 - April 3, 1985 (Report 50-312/85-09)

Areas Inspected: Routine inspection of the implementation of selected THI

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Action Items. .This inspection effort required 89.5 inspector-hours onsite and

, eight inspector-hours in the Region V office by two regional inspector Results: No violations or deviations were identified, i

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. DETAILS

~ ~ Persons Contacte'd1

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V Licensee Personnel

• G.1 Coward, Plant Superintenden *N. Brock,~ Electrical /I&C Maintenance Supervisor q

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_* H. Canter,-QA' Engineer

• R. Colombo, Regulatory Compliance Supervisor J

• S. Crunk,-Associate Nuclear Engineer 4

'*J. Field,-' Engineering and Quality Control ~ Superintendent l

• R. Lawrence, Mechanical Maintenance Supervisor

• L. Keilman, Manager, Nuclear Engineering

-*J. Delezinski, Licensing

• J. Williams, Instrumentation and Controls, Nuclear Engineering -

.*J. McColligan,_ Principle Project Engineer

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'kR. Dieterich,. Licensing Supervisor

• M. Nickerson, Shift Technical Advisor J. Mau, Training Supervisor L. Conklin, Senior Electrical Engineer M.'Ross, Engineer Contract Personnel (BBC Brown Boveri)

M. Hakao, Licensing, Becatel D. Prosch, Senior Engineer,.Bechtel

'The inspectors also talked with other licensee personnel during the

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inspection. These included plant staff engineers, administrative assistants, and document control personne * Denotes personnel present during the exit interview on April 3, 198 . TMI Action Plan Requirements _(Open) Item I.D.2 " Plant Safety Parameter Display Console" Summary: NUREG-0737 -requires the addition of a Safety Parameter Display System'(SPDS) in' the control room to display for' operating personnel a minimum set of plant parameters which define the. safety

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status of the plant. Additional guidance and' clarification is given in NUREG-0696 and generic letter 82-3 '

' Conclusion: At the time of the inspection the SPDS was installed and was in the final stages of review before implementatio L The inspectors spoke with licensee personnel and reviewed a sample i

of licensee personnel training' records. Training on the SPDS has

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been developed and is being taught in a three part lesson plan by

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Babcock and Wilcox.

i The inspectors also performed a visual inspection of the electrical portion on the SPDS beginning at the signal conversion cabinet H4SCA I

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'and H4SCB in the Auxiliary Building to the two CRT display channels

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and two operating control panels located on the control room panel H2SP and HISS, respectively. The inspectors reviewed plant-

. operations procedure A.76 " Safety Parameter Display System,"

Engineering Change Notice (ECN) 3907A'through 3907M " Safet ~

Parameter Display System," and QA/QC documentation relating to the installation of the SPDS. Based on this review the inspectors verified the following:

Installation of the SPD *'

Components are correctly identified and locate *

Adequate QC involvement during installatio *

QA and QC documentation properly reviewed and signe *

An adequate procedure exists which provides instruction for the operat. ion of the SPD The inspector noted that although ECN No. 3907 has been closed out, the basis for completion and acceptance of STP 636 " Safety Parameter Display System Acceptance Test" is for training purposes onl The system has not been turned over to operations. This item will remain open pending examination of the final turn over package of the SPDS to operations, and review of procedure and Technical Specification changes due to this modification, (Closed) Item II.E.4.1 " Dedicated Hydrogen Penetrations" Summary: NUREG-0737 requires that plants using external recombiners or purge systems for post-accident combustible gas control of the containment atmosphere should provide containment penetration systems for external recombiner or purge systems that are dedicated to that service only, that meet the redundancy and single-failure requirements of General Design Criteria 54 and 56 of Appendix A to 10 CFR 50, and that are sized to satisfy the flow requirements of the recombiner or purge syste Conclusions: The inspection of this TMI item was continued as a followup to Inspection Report 50-312/84-19 for the inspection period July 19 - August 29, 198 The inspectors performed a visual inspection of dedicated hydrogen penetrations 60 and 67 located in the East and West Decay Heat Cooler Rooms of the Auxiliary Building. The locations of these two penetrations were not visibly marked, but were identified through-location of valves HS53623 and HS53622 (which are part of the dedicated hydrogen system) and Drawing No. M-118, Rev. 6

" Penetration Pipe Spool Table of Dimensions." The inspectors reviewed turnover package No.83-143 and Engineering Change Notice No. 3917. They also reviewed a sample of changes to plant procedures, changes to as-built drawings located in the control

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room, and.QA and QC: documentation relating to.the installa't'on i and

,g ' acceptance of the. hydrogen-penetratio ~

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Based on this inspection and review, the inspectors.verifie'd the following:

- . Components are' correctly identified and locate ,

• -There.is physical indcpendence between redundant instrument

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. components and actuating device '

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Changes have.been incorporated into various plant procedures to e . reference the dedicated hydrogen penetration or associated

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Changes have been incorporated into various as'-built drawing a

.QC involvement during installatio *

QA and QC documentation was properly reviewed and signed. -

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The installation of the dedicated hydrogen penetrations has been

' completed ~and turned over to operation This item'is considered close ' Item'II.E.4.2"Containm$ntIsolation: Dependability" L

Sub-item 5.B (Closed) - Containment Pressure Setpoint

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Summary: NUREG-0737 requires that the containment setpoint pressure that initiates containment isolation for nonessential penetrations be reduced to the minimum compatible with normal operating conditions.-

Findings and C5nclusions: SMUD stated, in a January 16,' 1981 letter to NRR, that the.present setpoint limit of 4'psig is adequate to meet the 0737. requiremen In a subsequent letter to SNUD dated

. July 14, 1981,'NRR agreed.that the present setpoint limit is~

satisfactory and the item is closed ou ;This item is close Sub-item 7 (Closed) - Radiation Signal on Purge Valves Summary: NUREG-0737, requires that containment purge and vent-isolation valves ^close on a high radiation signa

Findings and Conclusions: The modification (No. 5) was made in accordance with.sub-ECN A-3683C and has been completed. The L modification involved adding interlocks to close the Reactor i' Building purge valves (if open) on detection of high radiation levels during post LOCA conditions, using a signal from radiation monitors installed per TMI Action Item No. II.F. ,

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lThe. inspectors reviewed design and_ modification documents to ensure

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'that the changes _'were made in_accordance.with procedures and

' reflected in the current as-built drawings and operating procedure :The inspectors discussed training for modifications with a training

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- supervisorc and reviewed training. records to verify that appropriate personnel-were trained on this modificatio ' Revision 5;to System Operating Procedure. A.67, " Area Radiation .

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. Monitoring System," dated December 29, 1983, and Section 3.6.1 of

. Enclosure 5.25.to Administrative Procedure 305-33, " Radiation-

~ : Monitoring System," Rev.' 5, dated October 25, 1984, demonstrate that

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. containment purge valves'close on a h gh radiation signa . Technical Specifications were changed in Amendment _No. 40 to Facility Operating License No. DPR-54'for the Rancho Seco Nuclear-

- Generating Station to reflect -the changes made per THI 0737 '

' Requirement'II.E.4.2.7.

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'This item is close Item II.F.1 " Accident Monitoring" The. inspectors verified the licensee's actions taken in response to the following NUREG-0737 sub-items are as documented in

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correspondence between-the licensee and the NR '

Areas of inspection included:

Review of design changes to ensure that modifications wer reviewed, approved, inspected.and tested.in accordance with-established procedure *

Review of as-built drawings and procedures to ensure that

, revisions were incorporated to reflect modifications made to the system *

' Discussions with training personnel and review'of' training-records to ensure that applicable personnel received training on the modification ..

Visual verification of the installation of accessible modification _ ,

In'a September.8,il982 letter,.the NRC found the designs for these sub-items to be acceptable. In a February 17, 1983~1etter, SMUD submitted proposed technical specification changes to NRR fo approval. The technical _ specification changes are still under revie .Sub-item 4 (Closed) Containment Pressure Monitor Summary: NUREG-0737 requires.that a continuous indication of

, containment pressure be provided in the control room of each l operating reactor. Measurement and indication capability shall

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include three times the_ design pressure _of-the containment for concrete, four times the design pressure for steel, and -5 psig for

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all containment ;

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l Findings and Conclusions: The modification l(No' 55) was made in-

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accordance with Engineering Change Notice (ECN) A-2936 and completed -

October 28,-11983. The modification involved upgrading the existing containment-pressure measurement'to provide a continuous. indicatio Control room indication'was. verified by the inspectors. This

. indication -includes a strip' . chart recorder on the' control panel' and will-provide, computer indication on the Interim Data Acquisition and Display _ System-(IDADS) and the Safety Parameter Display System (SPDS),upon their turnover to operations (due at the end of the 1985

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refueling outage). The inspectors also verified. installation of the system by a visual inspection of the' monitors at the penetrations

.into the containment building. The modification appears to satisfy the requirements of NUREG-073 . This item is close .

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Sub-item 5 (Closed) - Containment Water Level Monitor Summary: -NUREG-0737 requires that a continuous indication of containment water level be provided in the control room for all plants. A narrow range instrument shall be provided 'for-PWRs an cover the range from the bottom to the top of the co tainment sum A wide range instrument shall also be provided for PWRs and shall cover the range from the-bottom of the containment to the elevation equivalent to a 600,000 gallon capacit Findings'and Conclusions: -The modification (No. 12) was made in accordance with ECN A-2940 and completed October 28, 1983. The modification involved adding Class IE equipment to the existing-

--containment sump monitors and installing new flood level sensors in the containment building. Control room indication was verified by the inspectors. ' Narrow range indication is by status lights on the H2SF control panel. Wide range indication is by a strip chart recorder on the H1CO control panel and computer indication by the IDADS and _ SPDS computer ' systems (upon- turn over to operations). The modification appears to satisfy the 0737 requirement This item is close Sub-item 6 (0 pen) - Containment Hydrogen Monitor Summary: NUREG-0737 requires that a continuous indication of L'- hydrogen concentration in the containment atmosphere be provided in-the: control room. Measurement capability shall be provided over the range'of 0 to 10% hydrogen concentration under both positive and negative ambient pressur <

Findings and Conclusions: The modification (No. 21) is being made n .

in accordance with ECN A-2938 and is awaiting closure of sub-ECN

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A-2938E (which changes instrument tag numbers) for completion. All '

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c k Ihardware hasibeen installed and accepted per ECN's A-2938A thru

[ x :A-2938D.~ .The modification utilizes two existing containment

[( penetrations. -The: analysis system is a sample withdrawal type that

-receives, conditions ~ for pressure, temperature and flow, analyzes

.and: returns.the~ sample to its source. In operation,.the system will

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. form part of-the containment pressure boundary and contains redundant solenoid operated isolation valves to meet the isolation

, requirements'of'10 CFR 5 ' Control room indication for hydrogen concentration is provided by a dedicated strip chart recorder located on the~H1CO control panel and

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, _ .also on the IDADS and SPDS computer systems' (upon turnover to .

operations). Solenoid valve position is indicated on the local ^

control panels. (in the auxiliary. building) and in the control room

.via the IDADS computer system. Since the IDADS computer system has

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"not been turned over to operations, there. is no qualified control .

room-indication for solenoid valve position at this tim This item-is open until the turnover'of the IDADS computer system to operations to provide control room indication of solenoid valve position (for containment isolation indication) and pending the closeout of ECN's A-2938E and A-2938 for completion of the modification (No. 21).

e. . Exit Meeting On' April 3,;1985, an exit meeting was conducted with licensee

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, representatives identified in paragraph 1. 'The inspectors summarized the scope of the inspection and findings as described in this repor .

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