IA-97-177, Sixth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App I.Documents Listed in App J Already Available in PDR

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Sixth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App I.Documents Listed in App J Already Available in PDR
ML20151K323
Person / Time
Issue date: 08/04/1997
From: Racquel Powell
NRC OFFICE OF ADMINISTRATION (ADM)
To: Fowler C
AFFILIATION NOT ASSIGNED
References
FOIA-97-177 NUDOCS 9708060056
Download: ML20151K323 (3)
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U.S. NUCLEAR REGULATORY COMMISSION NRC FOIA hEQUEST NUMBEn(S) e FOIA 177

[g i NA Jg RESPONSE TYPE

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t, RESPONSE TO FREEDOM OF l FINAL l A l PARTIAL (den}

.ee .. j' INFORMATION ACT (FOIA) REQUEST o^TE JWG 0 4 W97 DOCKET NUMBE R(S) f/f spp/ cable) nEQUESTE R Catherine Fowler PART 1.-AGENCY RECORDS RELEASED OR NOT LOCATED (See checked boxes /

No agency rec'ords subject to the request have been located.

No additional agency records subject to the request have been located.

Requested records are available through another public distribution program. See Comments section.

Agency records subject to the request that are identified in Append;x(es) d are already available for public inspection and copying at the X NRC Public Document Room,2120 L Street, N.W., Washington, DC.

Agency records subject to the request that are identified in Appendix (es) I are being made available for public inspection and copying i X ct the NRC Public Document Room,2120 L Street, N.W., Washington, DC,in a folder under this FOIA number.

l The nonproprietary version of the proposal (s) that you agreed to accept in a telephone conversation with a member of my staff is now being made available for public inspection and copying at the N RC Public Document Room,2120 L Street, N.W., Washington, DC, in a folder under this FOI A number, ,

Agency records subject to the request that are identified in Appendix (es) may be inspected and copied at the NRC Local Public Document l Room identified in the Comments section.

l Enclosed is information on how you may obtain access to and the charges for copying records located at the NRC Public Document Room,2120 L Street, l 4

N.W., Washington, DC.

l ,

X Agency records subject to the request are enclosed.

  • i RIcords subject to the request have been referred to another Federal agency (ies) for review and direct response to you.

i Fees 1 You will ta billed by the N RC for fees totaling $

i l

You will receive a refund from the NRC in the amount of $

In view of N R C's response to this request, no further action is being taken on appeal letter dated , No.

PART 11. A-INFORMATION WITHHELD FROM PUBLIC DISCLOSURE l Certiin information in the requested records is being withheld from public disclosure pursuant to the exemptions described in and for the reasons stated  ;

in Pvt 11, B, C, and D. Any released portions of the documents for which only part of the record is being withheld are being made available for public j inspection and copying in the NRC Public Document Room,2120 L Street, N.W., Washington, DC in a folder under this FOl A number.

COMMENTS f

  • A copy of the record identified cn Appendix I is enclosed.

In addition, you may purchase a copy of NUREG-1190, " Loss of Power and Water Hammer Event at San Onofre, Unit 1, 11/21/85" from the Government Printing Office at the below address:

Superintendent of Documents U.S. Government Printing Office P.O. Box 37082

, Washington, DC 20402-9328

Phone
202-512-2249

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RE,DtRE DIVISI OF F OF INFORMATION AND PUBLICATIONS SERVICES

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FOIA-97-177 l l

APPENDIX I l RECORDS BEING RELEASED IN THEIR ENTIRETY  !

. EQ,. DATE DESCRIPTION /(PAGE COUNT)

~ 1. 3/6/86- Memorandum for V Stello from H Denton,

Subject:

I

Status of Staff and Licensee Actions in Response }

to San Onofre Nuclear Generating Station Unit 1  !

Event (31 pages) ,

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4 FOIA-97-177 APPENDIX J RECORDS ALREADY AVAILABLE IN THE PDR ACCESSION NO. DATE NUMBER DESCRIPT.70N/PAGE COUNT)

1. 7/28/86 8608120350 NRC Inspection Report 50-206/86-34 (34 pages)
2. 6/6/86 8606120694 Memorandum from J Taylor to J Martin

" Staff Actions Resulting from the November 21, 1985 San Onofre Unit 1 Water Hammer Event" (6 pages)

3. 4/3/89 8903300105 NRC Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs" (70 pages)
4. 7/7/86 8607160399 Memorandur.i from H Denton to V Stello

" Review and Assessment of Waterhammer Occurrences Since CY 1981" (2 pages)

5. 11/12/86 8612010470 Letter from T Novak to K Baskin,

" Technical Evaluation of Issues from the NRC Staff Action Plan in Response to the 11/21/85 Event at San Onofre Unit 1" (3 pages)

6. 12/8/89 8912030449 Letter from C. Trammell to H Ray, "Long-Term Electrical Cable Monitoring Program -

San Onofre Nuclear Generating Station, Unit 1 (4 pages)

7. 6/9/86 8606240488 NRC Inspection Report No. 50-206/86-20 (18 pages)
8. 6/9/86 8606250009 NRC Inspection Report No. 50-206/86-22 (27 pages)
9. 6/2/86 8606190592 NRC Inspection Report No. 50-206/86-16 (16 pages)
10. 4/28/86 8605050034 Memorandum from H Denton to V Stello l " San Onofre Nuclear Generating ,

! Station, Unit 1 (SONGS-1) Inservice i Testing (IST) Review" (5 pages) l 1 l

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1 SCOTT, HULSE, MARSHALL, FEUILLE, FINGER, & TIIURMOND, P.C. l ATTORNEYS AT LAW TEXAS COMMERCE BANK BLDO. 4 Cathertne L Fowest, CLA 11TH FLOOR LOUIS A. SCOTT Certified Le9si Aseistant EL PASO, TEXAS 79901 (1896-1974)

TELEPHONE (9151533 2493 JAMES F. HULSE TELECOPIER 1915) 546-6333 (1905-1989)

PLEASE ADDRESS FIRM ,

May 6,1997 ATTw: wRrrER WRITER'S DIRECT TELEPHONE:

(915) 546-8316 U.S. MAIL ME Nuclear Regulatory Commission h Nm 97-/77 Public Document Room DateRecht 5-/#- P 7 _  !

2120 L Street, N.W.

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AcdonOft: #nn/ -

i Lower Level  % Wxt0 m _

l Washington, D.C., 20555-001 RE: OPEN RECORDS REQUEST I

Dear Sirs:

Pursuant to the Freedom of Information Act,5 U.S.C.1552 et. seq., this is to request the following records:

1

1. All notices provided to the Nuclear Regulatory Commission (NRC) pursuant to 10 C.F.R. part 21, et seq. concerning any defects in swing l or tilt check valves.

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2. Correspondence to and from the NRC and internal NRC memoranda pertaining to any failure of a Crane Co. check valve.

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3. Any NRC bulletins, circulars, information notices or inspection and investigation notices pertaining or referring to any check valve failures.
4. Any licensee event reports, vendor reports and correspondence, relating to or pertaining to any check valve failure.

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5. Any NRC papers or papers commissioned by the NRC pertaining to check valve failures.

1126-?/8~^ N S/%

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Nuclear Regulatory Commission -

Public Document Room 2120 L Street, N.W.

Lower level ,

Washington, D.C., 20555-001 i May 6,1997 '

) Page 2 l 6. Any documents, including investigative reports, correspondence to or' from Southern California Edison, and correspondence to and from any check valve vendor pertaining to the 1985 check valve failure at the San Onofre nuclear power plant. ,

Please let me know if there is a charge for copies of these items and forward the above materials to:  ;

i Catherine L. Fowler, C.L.A. ,

Scott & Hulse, P.C. i 11th Floor, Texas Commerce Bank Bldg.

, 201 East Main St.

El Paso, Texas 79901 I

) Should you need any further information, please call me at (915) 546-8316. [

! Your help in this matter is greatly appreciated.

Sincerely, ,

i M[&&  !

Catherine L. Fowler l Certified Legal Assistant

[ to Benjamin .A. Escobar ,

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l MAR 6 BB6 j MEMORANDUM FOR: Victor Stello, Jr.

Acting Executive Director for Operations q FROM: Harold R. Denton, Director l Office of Nuclear Reactor Regulation

SUBJECT:

STATUS OF STAFF AND LICENSEE ACTIONS IN RESPONSE TO SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 EVENT In accordance with your memorandum of February 4, 1986, this memorandum provides a sunnary of the NRC action plan in response to the San Onofre Nuclear Generating Station (SONGS) Unit 1 event that occurred on November 21, 1985. The NRC action plan has been developed through the cooperative efforts of IE, Region V and NRR with Region V taking the lead per your memorandum. The staff has used your memo, the Incident Investigation Team (IIT) report (NUREG-1190),

the February 7 Staff Requirements Memo (SRM), the January 31 Palladino memo, and the staff's cumulative knowledge to develop a comprehensive action plan.

Development of this plan has involved the following coordination efforts:

o The three offices have had numerous, almost daily, conference calls to develop the NRC action plan. -

o There have been extensive conference calls with the licensee to establish an understanding of actions required for SONGS Unit I restart, o A meeting was held with the licensee on February 19 in Region V to review the status of the licensee activities and identify licensee i

- evaluations and related schedules required by the staff. I Follow-up activities include a meeting on March 5 in Bethesda with the licensee to address specific technical concerns'on the analysis of the check valve problems and on diesel generator loading design. Also planned on March 5 is a  ;

, separate informal discussion on the action plan between AE00 and Region V  !

- personnel, and IE and NRR personnel.as.available. AEOD and Region V understand l that this meeting is not part of the current IIT concept. However, both AE00 .

and Region V personnel feel that it may be useful and will be interested in the l results. Since responsible Region V personnel will be in headquarters for these i and other meetings, an infonnal meeting with you is planned for Mareb6. '

I Representatives of Region V. NRR and IE will be available to discuss any l questions that you may have on this status report. A follow-up meeting with i

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, . . .. l MAR 61986  :

{. Victor Stello, Jr.  !

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' the licensee is planned on March 12 to assure a mutual understanding of the licensee's and staff's status, plans, and requirements. l l

t We believe these efforts and~ plans will continue to give the licensee a ,

3 reasonable perspective of what the staff expects. The staff and licensee  ;

i- understand that it is the licensee's primary responsibility to establish an i acceptable program for restart of SONGS Unit 1. The licensee submitted their i i program for restart on March 2 and plans a comprehensive report of their 4

evaluations on March 28, 1986. The licensee also plans to brief the Comission  !

, on March 18 on their program and status. With a continuation of.the close  !

coordination to date, adjustments to this program from the Comission briefing or  !

l staff findings will be easily accommodated.

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! The NRC action item list was developed based on criteria that evolved during the l l planning process. A description of the general process and criteria is enclosed i for your information (Enclosure 1). An executive sumary of the action items is ,

, provided as Enclosure 2, and the detailed working list of identified NRC action j items with proposed schedule and a status is also included as Enclosure 3. ,

l This plan fo'r NRC staff activities resulted in three basic types of actions that

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the staff is-undertaking: .l

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o Making preparations for, and'then evaluatio.n of, licensee corrective l actions and proposals that are required for restart and beyond. Most
notably, assessment of the licensee's review of plant material '
condition and readiness for operation. j i

o Evaluation of generic implications of the SONGS Unit 1 event and '

j extent of similar problems at other plants through a sampling of  ;

industry experience and technical evaluations of root causes at  ;
SONGS-1, e.g., IST programs and check valve failures that may have 4

led to, water hamers.

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I o Evaluation of NRC renuirements and positions in light of existing 5

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- implementation practices, root causes found from the event, and l samples of industry practices.

l These actions outline a program that logically and expeditiously evaluate the  !

j SONGS Unit I restart program and assures that generic aspects are considered in j a timely, thorough manner. ^

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j The list of NRC action items (Enclosure 3) was outlined in accordance with the

enclosure to your February 4 memorandum. Additionally, a column for the source .

j of each action item is provided which cross-references to your memorandum, the

IIT report, the SRM, and/or the individual offices which initiated the item.

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The list also indicates the responsible office and whether or not the item is  ;

required for startup. This is a working list and will be modified as needed to  ;

follow licensee activities and staff findings. The due dates specified in the j l .

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lNU ftello,Jr. '6 1966 l

i re for completion of the review or inspection activity. Eva'suation s will be coordinated through the designated " lead" office for the major  ;

I itcms. Documentation of-inspection or evaluation results will generally m to the normal documentation process of each office, e.g., safety tion reports for NRR and inspection reports for Region V. i i

ratelist(notincludedinthisstatusreport)hasbeendevelopedto J 1

1-staff activities that are not related to the November 21 event. These ties include evaluation and inspection of environmental qualification, c and fire protection topics and modifications which have been planned i le_ current outage. These items are being tracked separately from the j ralat:d items to assure that appropriate attention is placed on the  !

usly planned outage activities. l laff's review of the licensee presentation on February 19 identified several that required information by February 28 in order to permit timely response

?SRM. This information included: the licensee's evaluation of the manual ,

Jg feature of the diesel generators; the impact of long-term outage on ,

the licensee's root cause analysis of check valve failures; l snt. reliability detailed list (a;ction list) of the items that the licensee concludes are 1 ed.to respond to the November 21 event. The licensee provided the

, tid infermation on March 2,1986. The licensee also comitted to provide a

  • fhensive startup report on the event by March 28, 1986 in which the ee intends to address all concerns relative to the event. The staff -

kasizedthespecificneedforthelicenseetoaddressthecurrentSONGS1

) which does -not include remote control of the main steam line isolation

,. The staff pointed out several items that should be specifically ghtsd by the licensee in their report. These items include the adequacy of design change reviews for reduced power operation and possible effects on jeck valves which failed, and the licensee's plans for plant material sign svaluations. Overall, the staff found the licensee's actions for

'p appeared to be consistent with those identified by the staff. A j

-en meeting at Re9hn V is schedul.ed for March 12, 1986 to further monitor

, fine the' licensee a corrective actions. In addition, a 50.54(f) letter ng prepared by the staff to formally transmit specific questions that the

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ce must_ address relative to the event.

censte's evaluation and troubleshooting activities have resulted in tntial progress. The cause of the feedwater system check valve failures has

re112inarily identified as partial or complete separation of the check disc assemblies due to fluid flow conditions. Changes in the ty a of itsr ch
ck valves being used, the installation of additional chec c valves in tsdwatsr line inside containment, and other modifications, including

>ed Ins rvice Testing, have been identified and initiated to reduce the

!ial for water hammers in the feedwater system. Repairs to the damaged ter system are in progress as well. The failure of the auxili &y j creer feeder cabling has been preliminarily attributed to damaging heat and gre csnditions in the turbine to Modifications building andspurious preclude additional protectionofforsafety annunciation the hgisplanned. ion due to electrical transients have also been planned, as well as 1

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Victor Stello, Jr. MAR 61986 numerous other modifications. The licensee is also evaluating the need for and feasibility of: automatic loading of diesel generators on loss of power; ,

improved offsite power reliability; uninterruptible power supplies to the  !

Technical Support Center computer and vital bus #4; and automatic closure of the main feed regulating valves (as additional water hammer protection) following a unit trip with loss of main feedwater pumps.

l w i

Harold R. Denton, Director [

Office of Nuclear Reactor Regulation

Enclosures:

1. Criteria for' Resolution of Restart Lists
2. Executive Sumary SONGS 1  !

Action Item Status

3. NRC Actibn Item List i (IIT SONGS 1) w/ Attachment  !

cc: R. Bernero F. Miraglia l

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4 Criteria for Resolution of Restart Lists To establish a list of issues, the staff examined specific analysis and inspection topics that were identified in the IIT report, previously issued InspectionReports,andNRCmanagementdirectives(e.g.,Commissionmeeting and EDO memos). Additionally, the staff continuously reviewed and evaluated the licensee's restart program and any other available information.

The staff evaluated each issue to determine whether the issue was required to be pursued and resolved prior to restart of the plant. The cr'teria used to evaluate, identify and select issues required to be resolved prior to restart were:

The issue is related to corrective action needed to preclude the recurrence of identified equipment failurus and/or prevent perconnel errors resulting from the water hammer or other recent events.  ;

The issue offers definitive improvements that will correct significant '

deficiencies identified in the licensee's management or quality assurance activities, which may have contributed to the water hammer transient.and '

other recent failures.  !

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EXECUTIVE

SUMMARY

SAN ONOFRE 1 ACTION ITEM STATUS The fo11cwing provides a summary status of NRC actions required in response to the San Onofre 1 trip and water hammer event of November 21, 1985. The references in parentheses identify the source of each item: the EDO memorandum  :

i dated 2/4/86; the SECY memo dated 2/7/86; or another NRC office identifying the concern.

Item Description Resp. Office Status

1. Implement / coordinate IE (Lead) actions to assure NRR reliability of safety- RV related check valves.

(EDO Memo Item 1)-

  • Plant-Specific Review of licensee's event analysis await-ing SCE submittal planned for 2/28/86.

Review of licensee's ,

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- IST program (submitted prior to event) is  ;

ongoing. Review of any needed upgrades to IST program awaiting 3/28/86 SCE submittal. Site, visit planned for - 4 3/17-3/21.

  • Generic adequacy of 3 plant visits completed; check valve design. 3 of 5 vendor

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and I.ST programs inspections completed; reviews of 16 IST l programs in progress.

2. Assess need to reevalu- NRR A review of post-1980 .

ate USI A-1 to address water hammer events will condensation-induced be carried out to water hammers in determine if faulted check valves were contri-feedwater (EDO Memo,pipingItem 2 ) buting factors and whether previous US! A-1 conclusions warrant revision. .

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i '3. Assess adequacy of NRR (Lead) Review of manual D-G SONGS-I design fea- RV loading following loss tures (other than of power awaiting 2/28 check valves) licensee submittal.

(EDO Memo, Item 3) . Review of other design features (includin feedwater system) g awaiting 3/28/86 licensee submittal. RV review / inspection of design changes is ongoing.

4. Evaluate abnonnal con- NRR(Lead) dition and post-trip RV reviews (EDO Memo,

-Item 4)

Generic requirements Ongoing for data retrieval capabilities Plant-specific Licensee's submittal concerns due 3/28/86

5. Evaluate overall RV Ongoing adequacy of SONGS-1 Licensee's submittal maintenance records due 3/28/86.

(EDOMemo. Item 5)

6. Adequacy of licensee RV(Lead) Ongoing procedures (EDO Memo, NRR Licensee's submittal Item 6) due 3/28/86
7. Adequacy 6f training RV(Lead) Licensee's submittal

_ (EDO Memo, Item 6) NRR due 3/28/86

8. Emergency' notification IE (Lead)

(EDO Memo,' Item 7) RV Adequacy of licensee Licensee's submittal procedures / training due 3/28/86 Evaluate NRC policies Ongoing for use of ENS Evaluate spurious Licensee's sutlinittal ringing of ENS due 3/28/86

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9. Existence / significance NRR Ongoing of backlog of license amendments (EDO Memo, l Item 8) '

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10. Evaluate effect of RY_(Lead) Licensee's submittal long outage on plant IE due 2/28/86 components (SECY Memo, - NRR 15)
11. Evaluate licensee RV Ongoing actions to review /

upgrade overall plant material cor.dition of SONGS 1 prior to restart (RegionV) s

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February 21, 1986 NRC ACTION ITEM LIST (IIT SONGS 1)

Required Status /

for Resp. Due Completion Item Description Startup Source Office Date' Date

1. Implement and coordinate the staff  ; ,' Stello memo IE/VPB 5/16/86* In progress and industry actions necessary 2/4/86 -

to assure the reliability of Enclosure safety-related check valves. Item 1 Areas to be evaluated include:

a. Adequacy of licensee's report Yes Stello memo IE/VPB 4/25/86 Awaiting licensee on root cause analysis and 2/4/86 (lead)- submittals planned for proposed corrective actions. Enclosure and 2/28/86 and 3/28/86 Item 1 NRR/PWR-A/EB  !

Note: The hydrodynamic aspects of the differences between the failed and replacement check valves will be reviewed by IE and factored into the overall feedwater system design review in item.3.b. The overall feedwater system design review

is listed separately to highlight t the importance of this review and to allow listing all NRR design change reviews in one location.
b. Adequacy of check valve design 'Yes IIT IE/VPB 4/25/86 In progress for SONGS 1 application - 13.3(Pg.3-6) (lead) attimeq{ November.21 Stello memo RV ,

event. 2/4/86 NRR/DSR0 Encl. Item 1 & PWR-A/EB

  • The SONGS 1. plant-specific issues will be completed and a plan to address the generic aspects will be developed by this date.

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NRCACTIONITEMl.IST(IITSONGS1)

Required Status /

for Resp. Due Completion Item Description Startup Source Office Date Date Note: A review of the design

system is covered in item 3.b.

  • The results of this evaluation will be ' considered as appropriate.
1) Determine which valves RV IE&RV/ SONGS 3/28/86 In progress are only partially open Residents during nominal operating conditions.
2) Review existing inspection RV IE&RV/ SONGS 3/28/86 In progress or test results. Residents
3) Review existing RV IE8RV/ 3/28/86 In progress reintenance histories.- SONGS.

Residents

4) Observe disassembly and RV IE&RV/ 3/28/86 In progress perform visual inspection SONGS of selected check valves Residents based on the results of the above reviews.
c. Generic evaluation of adequacy No IE/NRR IE/VPB 5/16/86* In progress of check. valve designs for this and application. (Other systems Chilk's are addregsed separately.) memo 2/7/86
  • The $0NGS 1 plant-specific issues will be completed and a plan to address the generic aspects will be developed by this date.

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  • , NRCACTIGHITEMLIST(II.TSONGS1)

Required

' Status / .

for Resp. Due Completion Item Description Startup Source Office Date Date

1) Perform vendor inspections. IE IE a) Anchor Darling 1/06/86- Completed on schedule b} Atwood Morrill ,, 2/10/86 Completed on schedule c) MCC Pacific 2/10/86 Completed on schedule d) Crane 3/3/86 Inspection scheduled e) Velan 3/24/86 Inspection scheduled
2) Review failure data and failure IE IE 3/28/86 In progress modes.

a) LERs, 50.55(e) P21, PNO 1 b) NPRDS c) Vendor Supplied d) Licensee Suppited j

3) Review check valve experience IE IE 4/11/86 at sites.  ;

- Hope Creek 2/6/86 Completed on schedule

- Millstone 2/10-14/86 Completed on schedule

- North Anna 2/10-14/86 Completed on schedule

- additional selected plants Inspection in plannin '

phase

4) Revsew comments and intended IE IE 4/25/86 '

act1ons of Owners' Groups meetings, t

5) Determine adequacy of check IE IE 5/16/86* Pending completion of  ;

valve design for this above '

application using input from C.1 to C.4 above.

  • The SONGS 1 plant-specific issues will be completed and a plan to address the generic aspects will be developed by i this date.

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4. . . . ,

MRC ACTION ITEM LIST (IIT SONGS 1) .

Required Status / t for Resp. Due Completion Item Description Startup Source Office Date Date

d. Adequacy of Inservice Testing IIT IE/VPB(lead) 5/16/86* In progress 16.7 (IST) Program and procedures to NRR/DSR0 detect degraded and failed.  ;

.(p. 6-14) valves. and t

Stello memo  :

2/4/86 Encl. Item 1 1

1) NRR review of adequacy of Yes NRR NRR/DSR0 3/14/86 In progress docketed IST program at and PWR-A/EB 1 SONGS 1 prior to event,
2) No .IE IE 5/16/86*

Evaluate Programs Adequacy)of (Generic . IST a) Visit' Plants.

- Hope Creek 2/06/86 Completed on schedule

- Millstone 2/10-14/86 Completed on schedule

- North Anna 2/10-14/86 Ccmpleted on schedule

- Additional Selected Plants Inspection in plannin!

phase b) Review a sample of 16 IE 3/28/86 In progress IST programs.

c) Review comments from Owners IE 4/25/86 Groups.

d), , Based on a), b), and c) IE/VPB & 5/16/86* Pending completing of above, make recommendations NRR/DSRO above on portions of Generic issue II.E.6.1 which should be accelerated or any more immediate licensee actions that should be considered.

  • The SONGS 1 plant-specific issues will be completed and a plan to address the generic aspects will be developed by this date.

__m.________m. _ _ _ ____._.-_.____.._.______._m._. _ _ . _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ . . , - e , ,-_--.*4 - ,-r-. _ . , -- - - - , . . . . - <-m,, ,.-. - -mua , - ._ , -. .-.-...

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NRC ACTION ITEM LIST (IIT SONGS 1)

Required Status /

for Resp. Due Completion Item Description Startup Source Office Date Date

3) Evaluate adequacy of Yes IE IE/RV 4/14/86 Inspection scheduled I existing implementation -

of IST program for SONGS 1.; i (Including check valves and other valves).

(Including the following considerations: test frequency; acceptance "

criteria; need for periodic disassembly /

inspection and QA involvement)

4) NRR review of SONGS 1 IST Yes NRR NRR/ 4/28/86 Licensee's submittal program requirements in PWR-A/EB due 3/28/86 light of November 21, 1985 event.
e. Evaluation of check val ms (and Stello memo IE/VPB(lead) 5/16/86* In progress related testing programs) for 2/4/86 NRR/PWR-A/EB other safety-related systems, Encl. Item 1 RV such as RHR system.
1) Evaluate SONGS 1 check Yes RV IE&RV/ SONGS 4/18/86 In progress valves in non-feedwater Residents system application as per sub-items listed in Ib.
2) Genepic adequacy of check No IE/NRR IE/YPB (lead) 5/16/86* In progress valves (and related testing NRR/DSR0 programs) in other safety-related systems as per sub-items listed under iten Ib including review of check valve data.
  • The SONGS 1 plant-specific issues will be completed and a plan to address the generic aspects will be developed by this date.

NRCACTIONITEMLIST(IITSONGS1)

Required Status /

for Resp. Due Completion item Description Startup Source Office Date Date

f. Evaluate check valve maintenance Yes IIT 16.5 IESRV/ SONGS 4/18/86 Inspection planned program implementation for SONGS 1: (p. 6-12) < Residents
1) Review adequacy of valve RV preventive maintenance (PM) program.  !
2) Evaluate the adequacy RV of licensee trending of i

IST and maintenance res its.

3) Evaluate the adequacy No RV of QA involvement in PM program.
g. Evaluate check valve maintenance RV IE/NRR-OHFS 5/16/86* Inspection planned programs generically. ,

t

2. A5:ess the need to reevaluate USI A-1 No IIT 16.3 NRR/DSR0 6/30/86 A review of post-1980 '

to specifically address the potential (pp. 6-7, 889) water hamer events for and prevention of condensation and will be perfonned.

, induced water hanuners in feedwater Stello memo See attachment to this piping. (Assume the issue concerning 2/4/86 enclosure for a detai~

check valve integrity will be resolved Encl. Item 2 in item 1.) and Chilk memo 2/7/86

  • The SONGS 1 plant-specific issues will be comp 1 ted and a plan to address the generic aspects will be developed by this date.
  • , 7 . . .

NRC ACTION ITEM LIST (IIT SONGS 1) -

Required Status /

for Resp. Due Completion Item Description Startup Source Office Date Date

3. Adequacy of SONGS 1. Design Features Yes Stello memo NRR/PWR-A 5/16/86 l (other than specific check valve  ; .* 2/4/86 design). Encl. Item 3
a. Implement and coordinate Stello memo NRR/PWRA 5/2/86 the staff's actions to 2/4/86 reevaluate the following Encl. Item 3 San Onofre design features:

~

1) Lack of automatic loading of IIT 14.14 PWR-A/ 3/10/86 Licensee's submittal r the diesel generators following (p. 4-16) EICSB/RSB due 2/28/86 a loss of power event. and and PSB Chilk's' memo 2/7/86 -
2) Lack of remote control of IIT 13.5 PWR-A/ 5/2/86 Licensee's submittal ,

steam line isolation valves and (p. 3-9) PSB and due 3/28/86 resultant impact on assurance and 14.2 RSB of steam generator availability (p. 4-1) to remove decay heat (in event of steam 11ne or feedline break).

Lack of steam generator IIT 13.7 PWR-A/ 5/2/86 Licensee's submittai

3) (pp. 3-10&11), PSB due 3/28/86 blowdown status in control 17.2.2,1 room or auto terinination '

capability (p. 7-9), and 18.7 (p. 8-3) -

Adeqyacy of the licensee's Stello memo PWR-A/ 5/2/86 Lt.censee's submittal

4) due 3/28/86 design change to eliminate 2/4/86 EICSB spurious SI indication on Encl. Item 3 loss of power (SI annunciator and SIS sequencer surveillance panel)

__m-m_ _ _ _ _ . - . - _ _ -_um_ ______---__w~ er _ - w L+- 1 ++- e- m- --- - - =me - =- - e'm:- 7

's 8_, . .

NRC ACTION ITEM LIST (IIT SONGS 1)

Required Status /

for Resp. Due Completion Item Description Startup . Source Office Date Date

5) IIT 13.4 PWR-A/ 5/2/86 Licensee's submittal ,

Non-safety sequencer (related reliabilityauto and (p. 3-6), . EICSB due 3/28/86 impact on station blackout).., 17.2.1.4 (p. 7-5), & i 14.12.2.1 (p. 4-11)

6) Impact of interlock between IIT 14.12.3 PWR-A/ 5/2/86 Licensee's submittal reactor bypass breaker and (p. 4-13) EICSB due 3/28/86 diesel generator output breaker on electrical power reliability.
7) Adequacy of labeling for selected IIT 14.16.3.1 PWR-A/ 5/2/86 Licensee's submittal control room indicators. (p. 4-20) EICSB due 3/28/86 17.2.1.2 (p. 7-4)
3) Reliability of power to IIT 13.4 PWR-A/ 5/2/86 Licensee's submittal vital buses, e.g., power (p. 3-6) EICSB due 3/28/86 to important control 14.12.1 p. 4-9),

room indications and 14.12.4 p.4-13),

controls. 14.12.5 p. 4-14),

14.17 (p.4-21 thru 24)

9) Increased reliability of IIT 13.2 PWR-A/ 5/2/86 Licensee's submittal 4KV power supplies (p.3-2), EICSB due 3/28/86 (includes evaluation of 14.12.3 ,

cause of failure of C (p. 4-11),

transforiner power cable). 14.13(p.4-15),

14.14(p.4-16), '

  • ' 17.2.1.5 (p. 7-6),  !

18.1 (p. 8-1) a) Cable reliability.

b) Alternate immediate source of offsite power (e.g., additional reserve transformer).

"O 9 -

NRC ACTION ITEM LIST (IIT SONGS 1)

Required '

for Resp.

Status /

Item Description Startup . Source Due Completion Office Date Date

b. Evaluate adequacy of SONGS 1 .IIT 16.3.2 NRR feedwater system design. S/2/86 Licensee's submittal (p. 6-9) < FWR-A/PSB due 3/28/86
1) Water haamier design NRR PWR-A/PSB considerations / engineering. DSRO
2) Water hanner design NRR PWR-A/PSB considerations / systems DSR0 aspects.
3) Possible instrumentation NRR PWR/PSB/EICSB to indicate impending DSRO water hammer conditions.
4) Adequacy of feedwater NRR PWR-A/EB repair / system integrity and material considerations.
c. Review and inspect selected RV RV/ SONGS 5/16/86 In progress design changes. Residents
1) Steam generator blowdown IIT 13.7 status indication or (pp.3-10811) automatic termination. 17.2.2.1 (p. 7-9), and 18.7 (p. 8-3)
2) Modifications to eliminate licensee IIT 117.2.1.3 spurious SI indications. commitment (p. 7-4)
3) Imp' roved labeling for IIT 14.16.3.1 selected control room (p. 4-20) and indicators. 17.2.1.2

~ (p.-7-4) m-,_u ./.__...__m. - . - _ - , . . _ _ _ -._.___.____-_m._______ _____._ _ ___ -m __--_m_ - - _ - _ _ _ - _ - ' m - e e- _ T-ww "

  • e* -M 's ---

~

,i.

10 . - .' .

NRCACTIONITEMLIST(IITSONGS1) .

Required for Status /

Resp. Due Completion 1 tem Description Startup Source Office Date Date

4) Continuity of power to IIT 14.17 event computer and (pp. 4-21 thru 24) vital buses.  ;. 13.4 (p. 3-6),

14.12.5(p.4-14),

14.12.1 (p. 4-9),

14.12.4 (p. 4-13) ,

5) Increased reliability of IIT18.1(p.8-1),

4kV power supplies. 14.12.3 (p. 4-11),

13.2 (p. 3-2),  ;

14.13(p.4-15). '

14.14 (p. 4-16),  ;

17.2.1.5 (p. 7-6)

a. Auto loading'of i diesel generators,
b. Loss of voltage automatic sequencer.  ;
c. Reactor bypass / diesel licensee generator output comitment breaker interlock. '

i

d. Environmental licensee ~

protection for 4KV commitment cables. '

e. Alternate 4KV power i e , source. .
6) UPS and automatic reset IIT ,.

for TSC computer. 17.2.2.4 (p. 7-10)

7) Feed line void detectors. RV I

- 11 - .

NRC ACTION ITEM LIST (IIT SONGS 1) -

Required Status /

for Resp. Due Completi3n Item Description Startup . Source Office Date Date

8) Modifications and repairs RV to feedwater system including independent 1.

NDE.

4. Abnormal Condition and Post-trip Review Concerns.
a. Evaluate generic NRC requirements No IIT 17.2.2.4 NRR 5/16/86 Ongoing for ensuring that sufficient (p. 7-10) & PWR-A/EICSB event data are retrievable to 'Stello memo accurately reconstruct event 2/4/86  :

following a loss of offsite power. Encl. Item 4  ;

b. Evaluate the licensee's process Yes IIT RV/ SONGS 5/16/86 Licensee's submittal for abnonnal condition and 17.2.2.4 Residents due 3/28/86 post-trip review, including (p.7-10) involvement of: ,
1) Onsite Review Comnittee IIT 16.6 (e.g., noise evaluations) (p.6-12) in feed line B prior to event).
2) Offsite Review Comittee. IIT 16.6 i (pp. 6-12&l3)
3) Quality Assurance. RV
c. Evaluate.gdequacy and Yes IIT 17.2.2.4 NRR/PWR-A/ 5/16/86 Licensee's submittal reliability of post-trip (p. 7-10) & EICSB due 3/28/86 i data retrieval equipment. Stello memo

,2/4/86

. Encl. Item 4 i

if . .

's .

NRC ACTION ITEM LIST (IIT SONGS 1) -

Required Status /

for Resp. Due Completion Item Description Startup Source Office Date Date .

1) Critical Function IIT Monitor not reset 17.2.2.4 -

after troubleshooting.-  ;

(p.7-10)  ;
2) Continuity of power IIT 14.17.3 to event computer. (p. 4-23)
5. Evaluate the overall adequacy of Yes IIT 16.5 RV/ SONGS 5/16/86 Ongoing SONGS 1 maintenance records. (p. 6-12) & Residents Licensee's submittal Stello memo . 3/28/86 2/4/86 Encl. Item 5
a. Completeness and retrievability RV of records.  !
b. QA overview. RV
c. Trending RV -
6. Adequacy of procedures. ,
a. Verify licensee actions to Yes RV/ SONGS 5/16/86 Ongoing correct the following Residents Licensee's submittal identified deficiencies due 3/28/86 with site procedures. ,
1) Lack of adequate precaution's IIT 17.2.1.5 on length of time diesel (p.7-6) genegators can operate unloaded ,

without AC power to radiator fans was improperly deleted from procedure.

I i

___ . _ . _ _ _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _. -. _- _ _. _ _ . __.....r- .- . - . .._m

q ~

13 . . .

NRCACTIONITEMLIST(IITSONGS1) -

Required Status /

for Resp. Due Completion Item Description Startup Source Office Date Date

2) Lack of provisions for IIT 16.1 recognizing and preventing (pp. 6-2,3&4) -

conditions which allow  ;,

the initiation of water '

hamers.

3) Inadequate instructions for IIT 13.4 manually bringing power onto (p. 3-6),

dead buses and for responding 17.2.1.4 to malfunction of the loss (p.7-5),

of ac power automatic 14.12.2.1 sequencer. (p. 4-11)

4) Inadequate instructions for IIT18.1(p.8-1),

troubleshooting of 4KV 14.12.3 (p. 4-11),

bus grounds. 13.2(p.3-2),

14.13(p. 4-15),

14.14 (p. 4-16),

17.2.1.5 (p. 7-6)

5) Lack of provisions for IIT 17.2.1.3 identifying alternate (p. 7-4)

. methods of verifying SI actuation.

6) Need for revision to AFW IIT 16.1 system flow control procedures (p. 6-3) to factor in effect of ficy,on reactor coolant .,

system temperature.

7) Procedure for going onto IIT 18.8 RHR cooling implied cle;'ing ~(p. 8-3),

of isolation valve interlock 13.8 (p. 3-12&l3),

at 400 vice 370 psig. 14.10 (p. 4-8),

17.2.1.8 (p. 7-8)

'- 14 - . -

ee .

NRC ACTION ITEM LIST (IIT SONGS 1) .

L Required Status /

for Resp. Due Completion ~

Item Description Startup Source Office Date Date 8)' Need for administrative time limit on loading .

diesel generators following ;,'

loss of station power.-

b. Assess appropriateness of Yes IIT 13.2 NRR/ 4/18/86 Licensee's submittal  ;

paralleling buses with (p. 3-2), PWR-A/ due 3/28/86 indicated ground fault. 15.1 (p. 5-1) EICSB  :

17.2.1.1  ;

(p. 7-1) i

c. Evaluate overall program Yes Stello memo RV/ SONGS 5/16/86 Licensee's submittal for developments of procedures 2/4/86 Residents due 3/28/86  !

in light of the above Encl. Item 6 l inadequacies. ,

7. Adequacy of training. Stello memo RV/SONCS 5/16/86 Licensee's submittal  !

2/4/86 Residents due 3/28/86 Encl. Item 6  !

a. Verify the adequacy of Yes RV/ Reactor 5/16/86 Licensee's submittal  ;

operator training in the Safety Branch due 3/28/86

  • Inspection planned following areas
1) Troubleshooting and IIT 17.2.1.1 isolating grounds (pp. 7-1 thru 4)  ;

(including bus and transformergrounds). '

-2) Tran'sfer of loads between IIT 17.2.1.1 l 4KV buses. (P. 7-1) .

i

3) Operator response to ~IIT 17.2.1.2 loss of offsite electrical (p. 7-4) power.

t i

, ~ - . , - . . . . - - . . - _ . , < . -w,.--.e. - -

_..._m., . . _ . - - , . ,w . _ , , , ,-

NRCACTIONITEMLIST(IITSONGS1) .

4 Required Status /

for . Resp. Due Completion

~

Item Description Startup Source Office Date Date

4) Resetting unit trip IIT 17.2.1.4 to allow reenergization (p. 7-5) .

i- of onsite electrical buses. ,,

5) Controlling SG blowdown. IIT 13.7 (pp.'3-10&11)
6) SLSS sequencer panel IIT 14.13 ,

indications. ~ (pp.-4-15&l6)

7) Not notifying MRC that IIT 17.2.2.2 a UE had been declared. (p. 7-9), & ~

17.3.2 (p. 7-15) ,

j

b. Evaluate implementation of Yes IIT 13.2 RV and 5/16/86 Licensee's submittal -

technical specification action (p. 3-2) PWR-A/ FOB due 3/28/86 statements when warranted, e.g.,  ;

reluctance to fully isolate failed transformer.

8. Emergency notification. Stello memo IE/DEPER (lead) 5/16/86 Licensee's submittal 2/4/86 RV due 3/28/86 ' '

Encl. Item 7 i

a. Verify the adequacy of the Yes IIT 17.2.2.2 RV/ 5/2/86 Licensee's submittal licensee's procedures and (p. 7-9) & Emergency due 3/28/86 '

training for reporting of Stello memo Preparedness events to NRC Operations 2/4/86 Section (lead) 2 Center. (See item 7.a.7 Encl. Item 7 IE/DEPER i above.),, .

b. Evaluate NRC policy for No IIT 17.3.1 IE/DEPER 4/18/86 In progress  ;

allowable uses of the ENS. (pp. 7-11&l4)  !

1) Use of MRC personnel as IIT 17.3.1.5 ENS comunicators. (p. 7-14) i

,r .

16 .. ., .

NRC ACTION ITEM LIST (IIT SONGS 1) [

Required for Status /

Resp. Due Completion Item Description Startup Source Office Date Date

2) Actions to improve NRC IIT 17.3.1 determination of overall (pp. 7-11 thru 14),

plant status during  ; ,* 17.3.2 (p. 7-15) events.

l

3) Site specific training IIT 17.3.1.2 of headquarters duty (p. 7-12) officers.
4) Licensee responsibility IIT 17.3.1.4  ;

to provide communicator (p. 7-14) ,

when requested.

5) Qualifications of licensee IIT 17.3.1.2 comunicator. (p. 7-12), i 17.3.1.5 (p. 7-14)  !
c. Evaluate spurious ringing of Yes IIT 18.10 RY/EP Section 5/2/86 Licensee's submittal ENS phones during event. (p. 8-4) (lead) due 3/28/86  ;

IE/DEPER I

d. Evaluate the adequacy of licensee Yes IIT 17.2.2.1 IE/DEPER 5/2/86 Licensee's submittal  !

procedures and training for (p. 7-8) due 3/28/86 t notifying on-shift personnel RV/EPSection(lead) of an emergency event. 1

9. Evalua'te whether a backlog of Yes IIT 16.4 NRR/ 4/1/86 In progress license amen (p. 6-10) & PAD-1 (lead),  !

specificatio n%changes nts andcontributed technical Stello memo PWR-A and to delays in approving the licensee's 2/4/86 DSRO l

IST program. , Encl. Item 8 i

10. Evaluate effect of long Yes Chilk's RV (lead) 3/10/86 Licensee's submittal outage period on plant components. 2/7/86 15 IE due 2/28/86 l (closely tied to item 11. below) Commissioner NRR '

Bernthal

, f

.17 ,--  ;

I NRC ACTION ITEM LIST (IIT SONGS 1) .

Rewired Status /

Item Description St rtup Source he , 'f '"

11. Perfom a comprehensive evaluation Yes RV RV/ SONGS 5/16/86 In progress of licensee actions to implement' ' Residents an integrated program for review  ;.*

and upgrading of overall plant material condition prior to restart of SONGS. r

a. Review existing maintenance RV and test data for key safety- ,

related systems and systems  !

that are important to on-line ,

plant reliability.

b. Review the overall backlog RV of maintenance orders not .l completed prior to restart. i
c. Review the licensee program RV' for operational readiness i testing of key safety-related systems and systems that~  !

are important to on-line plant reliability.

.d. Perfom a comprehensive RV t walkdown of key safety-  !

related systems and systems that are important to  !

on-line plant reliability. j

e. Review 1'icensee implementation RV of Area Monitoring Program. ,
f. Perfom independent measuremt .ts RV to confirm plant material condi- j tion (NDE van). Include steam  !

and feedwater system wall thickness to detect erosion. '

l o .

]

- Attachment to Enclosure 3 Influence of Check Valves on Water Hamer i

~

Question:

As a result of the water hamer occurrence at SONGS 1 on November 21, 1985, the Chairman requested that "the staff reexamine the water hamer safety issue (USI A-1) and decide if the influence of check valves on water hamer needs to be reexamined" (Ref. M860122 dated February 7, 1986). The EDO raised a similar question (Ref. Item 2 of the attachment to the V. Stello'to H. Denton, J. Taylor and J. Martin memo dated February 4,1986); that the staff " assess the need to j reevaluate USI A-1 to specifically address the potential for, and prevention of, condensation-induced water hammer in feedwater piping (assuming the issue concerning check valve integrity will be resolved in Item 1)."

Response: -

The November,21, 1985, water hamer occurrence at SONGS 1 was caused by multiple check valve failures in the feedwater systems; all five check valves were found to be failed. Loss of these check valves allowed tctal drainage of the feed-water (FW) lines prior to their manual isolation from the control room. The '

subsequent injection of cold auxiliary feedwater (AFW) into steam filled lines resulted in a condensation-induced water hammer. ]

The SONGS I water hamer resulted from the same phenomenon as could occur from the drain down of feedrings in steam generators having a top-feed ring design.

Such plants have had a history of water hammer occurrences when AFW was injheted and were extensively reviewed by the staff on a plant-specific basis and again during the resolution of USI A-1 (see NUREG-0918 and NUREG-0927. Revision 1).

This phenomenon was identified as steam generator water hammer (SGWH) and was minimized by fixes such as installing J-tubes and administrative controls on AFW flow rates.:- Failure of check valves to the extent that was incurred at SONGS 1 had not been reported in U.S. plants at the time USI A-1 was resolved. The

- staff was aware of an isolato water hammer incident in the FW system at the KRSK0 plant in Yugoslavia in July 1981 during hot functional testing. The cause was attributed to starting and stopping of FW pumps and possibly leaky check valves; detailed information was not available. No such similar occurrences had been reported from U.S. plants. Therefore, check valve failure was not considered to be an event with a high enough probability to warrant consideration.

The SONGS 1 occurrence does identify a need to reexamine this as a potential generic issue, and we plan to undertake such an assessment by June 1986. We will review the water hamer events that have occurred in U.S. plants since mid-1980 which were utilized in the resolution of A-1, and we will assess sueltaspects as underlying causes, corrective actions taken and generic implications." The results of this evaluation will be used to detemine if prior conclusions require revision. Based on our current understanding, the underlying causes of these post-1980 water hammers were not due to faulty check valves. However, a more

e i ..

i 2-detailed examination of these events is warranted before reaching a final conclusion. The results will be integrated with the findings obtained from Item i 1 (assurance of the reliability of safety related check valves) of Mr. Stello's memo. Nonetheless, it should be noted that any pipe failures resulti  :

water hammer occurrence are not expected to exceed current LOCA DBA a,ng from a ssumptions (i.e., quillotine break) and; therefore, the consequences previously estimated for A-1 would still be valid and no additional generic backfits would be justified under A-1. We also point out that check valve testing requirements are being addressed as part of Generic Issue II.E.6.1, in situ valve te ting. The results of the review of generic implications of the San Onofre 1 event will be assessed to determine if portions of Generic Issue II.E.6.1 warrant accelerated review. j i

e e*

f6 O

O W

9 f

1 i '

M 6 1585 Victor Stello, Jr. numerous other modifications. The licensee'is also evaluating the need for and feasibility of: automatic loading of diesel generators on loss of power; J improved offsite power reliability; uninterruptible power supplies to the Technical Support Center computer and vital bus #4; and automatic closure of the i main feed regulating valves (as additional water hamer protection) following a unit trip with loss of main feedwater pumps.

l edginalsitud #f j H. R. Dentos

]

Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

1. Criteria for' Resolution of Restart Lists
2. Executive Sumary SONGS 1 Action Item Status
3. NRC Action Item List (IIT SONGS 1) w/ Attachment  ;

l cc: R. Bernero 1 F. Miraglia l

See previous concurrences.* . ,

Office: R-V LA/ PAD #1 PD/ PAD #1 AD/PWR-A l Surname: 19tendonca*/dh PShuttleworth Glear* CRossi )

AChaffee j RDudley*:jm  !

Date: 3/ 4 /86 3/ /86 3/ 5 /86 2/28/86 3

i i

Office: Actg DD/PWR-A D/DSR0 D/IE R-V TNovak TSpeis* RVollmer* dMartin f 3/ /86 2/ 27/86 2/27/86 g/86 a -

Office: DD/NR

.D/%

dei nhut HDh(on l

/86 3/ h/86 ]

i l

.  :

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