ML20207D810

Summarizes 870724 Meeting W/Tp Speis,A Cutter,M Childers & Floyd to Hear Presentation on Plans for Resolution of Station Blackout

ML20207D810
Person / Time
Issue date:	07/29/1987
From:	Beckjord E NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML20195F793	List: ML20195F789 ML20195G040 ML20195G349 ML20207D767 ML20207D778 ML20207D800 ML20207D810 ML20207D969
References
FOIA-87-652 NUDOCS 8808160099
Download: ML20207D810 (11)

Text

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!!EMORACUti TO FILES FROM: Eric S. Beckjord, Director Office of Nuclear Regulatory Resear:h

SUBJECT:

STATION BLACK 0UT Dr. Speis and I met with Messrs. A. Cutter Mike Childers, and Steve Floyd ,

of NUGSB0 on July 24 to hear their presentaticn on plans for resolution of this issue; the attached documents were the basis of the discussion. They were informed of NRC's plan to issue a generic letter in September or early Octobe*. The recent LOOP event; at Palisades and Calvert Cliffs underline the importance of early resolution of this issue.

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Eric S. Beckjord, Director Office of Nuclear Regulatory Research cc: T. P. Speis

' :stribution:

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9 July 24, 1987 NUMARC-NUGSBO PRESENTATION REGARDING THE STATION BLACKOUT ISSUE NUMARC Al Cutter, Vice President Carolina Power & Light Company NUGSBO ,

- Mike Childers, Northeast Utilities Steve Floyd, Carolina Power & Light Co=pany e

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NUMARC INITIATIVES TO REDUCE SBO RISK A. NUMARC AND THE INDUSTRY COMMITTED 'to FOUR INITIATIVEI IN A JUNE 23, 1986 LETTER TO THE COMMISSION (THE INITIATIVES TO BE IMPLEMENTED NOTWITHSTANDING COMMISSION ACTION ON THE PROPOSED RULE) (PARAPHRASED BELOW).

B. INITIATIVE 1: DETERMINE SBO CATEGORY AND TAKE STEPS TO REDUCE RISK IT PLANT IS IN EIGHT HOUR CATEGORY.

C. INITIATIVE 2: IMPLEMENT PROCEDURES TO COPE WITH A STATION BLACKOUT, RESTORE AC POWER AND RESPOND TO SEVERE WEATHER.

D. INITIATIVE 3: REDUCE OR ELIMINATED COLD FAST STARTS OF EDGs THROUGH T.S. CHANGES OR OTHER MEANS.

E. INITIATIVE 4: MONITOR AC POWER UNAVAILABILITY USING DATA UTILITIES PROVIDE TO INPO ON A REGULAR BASIS.

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i NUMARC ACTIVITIES TO IMPLEMENT INITIATIVES i

I INITIATIVE 1 ACTIVITIES: o BEGINNING IN JUNE 1986, NUMARC DEVELOPED  !

1 AND ISSUED PROCEDURES (BASED UPON NRC STAFF'S METHODS) POR UTILITY ASSESSMENTS j OF COPING DURATION REQUIREMENTS (4 OR 8 HOUR CATEGORIES).

l o IN DEVELOPING THE PROCEDURES, NUMARC REPRESENTATIVES tlELD SEVERAL MEETINGS WITH NRC STAFF (JULY - OCTOBER 1986).

o IN OCTOBER 1986, NUMARC SPONSORED TWO UTILITY WORKSHOPS (ATTENDED BY REPRESENTATIVES OF VIRTUALLY ALL NUCLEAR UTILITIES).

o BY THE END OF 1986, NUMARC INITIATED EFFORTS TO CONFIRM EACH UTILITY'S APPROACH TO INITIATIVES 1.

.J STATUS: THERE ARE 105 _4-llOUR UNITSLAND 14 8-ilOUR UNITS. TIIE 8 IlOUR UNITS ARE EVALUATING WAYS TO REDUCE RISK BY MOVING TO Tile 4 IlOUR CATEGORY OR PROVIDING AN ALTERNATE AC SOURCE ( S_EE INITIATIVE 2.

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INITIATIVE 2 ACTIVITIES: o NUMARC DEVELOPED PROCEDURES FOR INITIATIVE 2(a) (UTILITY RESPONSE TO SBO EVENT).

o IN DEVELOPING THE PROCEDURES FOR INITIATIVE 2(a) NUMARC REPRESENTATIVES HAVE HELD SEVERAL MEETINGS WITH Tile NRC STAFF (DECEMBER 1986 - PRESENT)

STATUS: NUMARC HAS PROVIDED TO STAFF DRAFT GUIDELINES FOR RESPONDING TO A SBO EVENT. TNO OPTIONAL APPROACHES IIAVE BEEN DEVELOPED "ALTERNATE AC" AND "AC INDEPENDENT". THE ALTERNATE AC APPROACH DEFINES NON-EMERGENCY POWER SOURCES WHICH CAN RESPOND TO THE SBO AND ESTABLISHES GUIDANCE FOR ITS PROPER UTILIZATION. THE AC INDEPENDENT APPROACH ESTABLISHES GUIDANCE TO MAINTAIN SAFE PLANT CONDITIONS WITHOUT AC SOURCES. IN ADDITION, NUMARC HAS PROVIDED TO THE STAFF DRAFT GUIDELINES FOR RESPONDING TO SEVERE WEATHER EVENTS AND FOR RESTORING AC POWER.

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o INITIATIVE 3 STATUS: T IN RESPONSE TO NUHARC'S QUESTIONNAIRE DATED

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i OCTOBE 1986, AND FURTHER TO GENERIC L

LETTER 84-15 (A STAFF GUIDANCE DOCUMENT),

UTILIYid is VE (OR WILL HAVE) REDUCED k UNNECESSARY EDG COLD FAST STARTS.

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,1 INITIATIVE 4 STATUS: INPO'S PROGRAM FOR COMPILING DATA ON EDG UNAVAILABILITY IS PART OF INPO'S PERFORMANCE INDICATOR PROGRAM. (ON APRIL 2, 1987 A REPRESENTATIVE OF INPO MADE A PRESENTATION TO THE STAFF.)

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Icsues Important to Station Blackout Resolution

1. Need to identify high SBO risk plants to determine scope of required action. Sh g,b I

2. Operating Procedures are needed to ensure operations know how to cope with SBO and restore power.

3. Hurricanes pose a high risk to coastal plants.

4. coping analyses are needed to ensure plants can cope for minimum duration.

5. EDG reliability needs to be monitored and enhanced as appropriate.

6. Regulations do not currently address SBO.

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Iter.s Requiring Further Resolution

1. Alternate AC Criteria - EDG Cross Connect Feature.

2. Loss of Ventilation.

3. GDC-17 Revisien.

4. New Coping. Category Matrix.

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Ite: 81 Hour Category

1. NUMARC Initiative 1 . d c ri .a n e s 8-hou r plants . Commitment te get to 4-hour category or reduce risk by installing / crediting alterr. ate AC capability.

2. Evaluating new matrix - working with Staff to achieve comme..

understanding.

I:e= 82 - Procedures T llowing items are addressed in Procedure Guidelines.

1. Equipment is verified to be independent of AC powered support systems.

2. Procedures call for early assessment of DHR system operability.

3. Procedures identify potential sources of reactor coolant inventory loss and steps to isolate.

4. Back up sources of condensa:e makeup identified including steps to line-up sources.

5. Procedures identify steps t: conserve DC power through load shedding. ,

6. Procedures identify need for back up air /Ns for air operated valves or assessment of man:al valve operation capability.

7. Procedures assess need for 'ighting for access / egress to shutdown equipment requiring local control.

8. Procedures require assessme:t of loss of AC on security system operation for access to equipment needed for shutdown.

9. Procedures call for operater action to enhance . natural circulation ventilation of areas / cabinets containing shutdown equipment.

10. Procedures are required for power restoration to offsite ar.d on-site sources.

11. Procedurits allow an alternate AC power source to provide coping capability provided minimum requirements are met.

(see Appendix B of Procedure Guidelines. )

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Item 4 3 - Hurt: canes ,

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1. Procedures call for shutdown of plant in advance of possible LOOP, thereby reducing decay heat loads and reducing risk fQym SBO.

2. Anticipat:ng actions include EDG/ Alternate AC power warm-up and test as well as reduction of potential en-site missile hazards.

Item #4 - Coping Analysis [ ,

1. NUMARC re.iewing need for 1-hour and 4-hcar coping analysis.

2. Analysis focuses on 3 major resources - air, batter'es and condensate.

'3. Loss of ventilation can be addressed by generic analysis / study or demonstration.

Item 4 5 - EDG 1eliability

1. Initiative 43 reduces harsh testing to a minimum.

2. Initiative 44 monitors EDG performance.

3. EDG reliability targets and reliability program to be addressed by B-56. .

Item 46 - GDC-17 Change

1. GDC change not needed to address SBO. Similar re rulemakings have not required a GDC change (i.e., ATWS EG, PTS and A;pendix R).

2. Change to GDC opens door to potential interpretations of Station B'.ackout requirements not previously addressed in regulatory analyses.

3. Statements of consideration for rule can adequately address need for rule and intended scope without revising GDC.

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' Themis P. Speis, Deputy Director MEMORANDUM FOR: for Generic and Regulatory Issues Office of Nuclear Regulatory Research 9

FROM:

Aleck W. Serkiz, Senior Task Manager Reactor and Plant Safety Issues Branch Division of Reactor and Plant Systems, RES

SUMMARY

OF MEETING WITH NUCLEAR UTILITY GROUP DN STATION BLACKOUT (NUGSBO) ON USI A-44 <

August 13, 1957 MEETING DATES:

August 11, 1987 '

Phillips Building Metro No. 3 LOCATION: Metro Center, Suite 600 7920 Norfolk Avenue Bethesda, Maryland Bethesda, Maryland

- PURPOSE OF The purpose of these meetings was to continue discussions MEETINGS:

of guidelines and procedures dealing with NUMARCThese Initiative 2.

with NUGSBO. since the first meeting in July 1986.

ATTENDEES:

See attached attendee lists

REFERENCES:

(1) Letter to NRC Chairman Palladino from J. H. Miller, 17, 1986.

NUMARC, June (2) Procedures - Guidelinesofand "Assuring the Adequacy Station Blackout Response Technical Bases,"

, Revision 0.0, July 16,1987 (prepared by the Nuclear Utility Group on Station Blackout).

Reference 2meeting.

was the principal topic of discussion and review at thePre August 11, 1987 The outcome of this meeting was as follows:

lines.

1)

These guidelines appear to be technically sound and generally acceptable to the staff.

Some further revisions to Reference 2 are necessary, the more 2) important being:

l a) Utilization of the USI A-44 station blackout definition. j b) Utilization of the staff's definition of Alternative AC l (AAC) power sources as defined in the proposed rule. i f

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. i c) More explicit directior. regarding the development of procedures dealing with less of ventilation of energized electrical equipment necessary for safe shutdown during a blackout.

3) Outstanding items requiring further discussions are as follows:

a) The need for an additional electric circuit breaker in  :

Configurations 18 and 2A.

b) Wording on page 14 of the staf f's proposed RG 1.155 which deals with AAC design criteria, c) Single point vulnerability effects. ,,

Copies of the following documents were provided to NUGSB0 to expedite comparison of the NUGSB0 documents with the planned regulatory requirements:

(1) Selective pages of the staff's proposed Rule, which included a definition of the AAC source, (2) Draf t RG 1.155 (formerly Task SI 501-4), which included the staff's guidance for Q/A and tech spec requirements associated with non-safety grade equipment embodied in AAC sources, (3) Generic Letter 85-06 dated April 16, 1985, "Quality Assurance Guidance for ATWS Equipment that is not Safety Related."

The August 13, 1987 meeting focused on differences between NUGSBO's procedures and guidelines and the NRC staff's Rule requirements and RG 1.155. Three NU3SB0 reports identified as NUGSBO 8710,-8720 and -8750 were the focus of discussion at this meeting. Table 1 (enclosed) provides a comparison between the respective sections of RG 1.155 and the 3 NUGSB0 documents noted above.

To facilitate future discussions, NUGS80 will consolidate these 3 reports irto a singular report.

Considerable progress was made in these two meetings towards incorporatir,g the NRC staff's views and needs in the NUGSB0 coping assessments, procedures and guideline reports. The common goal of these meetings is to arrive at a technically acceptable NUGSB0 report (or references) that can be referenced in the proposed RG 1.155 and identified as being an acceptable approach to meeting the safety requirements attendant to USI A-44, Station Blackout.

There are several areas of disagreement (see Table 1) that will require followup discussions with NUGSBO. The next meeting is tentatively scheduled for August 19, 1987.

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Aleck W. Serkiz, Senior Tast Manager Reactor and Plant Safety Issues Branch Division of Reactor and Plant Systems, RES

Enclosures:

As stated cc: See next page O

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. Cc: B. Sheron, RES/0RPS W. Minners, RES/0RPS A. Thadani F. Rosa A. Rubin P. Baranowsty C. Liang J. Raval J. M. McGarry, III (BCP&R)

M. Childers (hd)

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1 DISTRIBUTION:

RES Circ /Chron DCS/NL-007 RPSIB R/F DRPS C/F KKniel SNorian IILSerkiz 0FC :RPSIB:DRP :RPSIB:DRPS :R IB: RPS :  :  :  :

NAME$ASerki d $PN iam $K dIel $ $

DATE 8/tjf/87 8/11/87 $8/if/87 $ $ $

OFFICIAL RECORD COPY O

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/p (O  % h i"N Staff Re f e r ence/

NUMAPC Document i

C1.1

• Rewrite and incorporate into I-1A docu ent, rewrite I-1 A summa ry, c reate C.1.1 appen:!ix ,

i i 1.2

• Rewrite and incorporate into I-1A summary or i

1.3 appendix exists at I-2, 4.1(1), 4.3(5).

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• Exists at 7-2', 4.3 with revision to reflect FPC Crystal River situation.

3 N/A.

3.1 Exists in I-1A - Precedure Section.

3.2.1 Exists I-5, 3.1.

l , 3.2.2 Exists I-5, 3.8, 4, 5, 6.

3.2.3 Exists I-5, 3.4, 3.5; I-2, 4.2(4).

3.2.4 *I-5, 3.6 to be revised to include representstive ventilation analysis.

l 3.,2.5 *I-5, 4, 6 ; 'i-5 ; N/A; I-5; Add 0-hr coping.

l 3.2.6 I-5; I-2, 4.2.

3.3 1-5, 4. 5, 6. .

3.3.1

• Add to I-5, 5.2 step 3 consistent with Staff.

3 3.2

• Add to I-5, 4.2 step 7 consistent with Staff.

• ... .* Add to I-2,

3. 3. 3

• 3.4; N/A due to assumption of RCI Loss

- revise assumption section as to why not

. applicable.

3.3.4a

• I ,S . B.10 revise.

3.3.4b *I-2, B.3-8 needs additional items consistent with Staff; revised Item B.7.

3.3.4c *I-2, B.14 issue taken with~ Staf f position I-2, 3.10.

3.3.4d *I-2, B.9; 2-2, 3.2.1(2); add to I-2, 3.2.1(2) (1/2

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3.3.5 *N/A: Ref 10.C.F.R., and numerous other regulatory

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and plant requiraments for procedural development,

_ testing naintenance.

Staff Reference NUGSB0 Document 3.3.6 *AAC reliability in I-2, B.15 - add non-IE, non AAC mode should have operability, testing per Stef f.

Added to I-2, 4.2(12).

3.4 Exists in I-2, 4.

3.5

• Create or take exception with staff position I-2, 4 or appendix - appropriate for SRP.

pp. 31-37 Exists in I-1A Procedure.

p. 38

• Incorporate outline into 1-1A summary or appendix.

pp. 39-41

• Incorporate into I-1A diagrams as appropriate.

• Add Staf f definitiagof:

1) Alt AC

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Attendees at NRC-NUGSB0 Meeting of 8/11/87 Name Organization Phone Al Serkiz NRC/RES 301/492-7487 Noel NRC/RES 301/492-7939

. Minnors NRC/RES 301/492-7827 K. Kniel NRC/RES 301/492-4705 S. D. Floyd NUGSB0/ CPL 919/836 6901 M. L. Childers NUGSBQ/NU 203/665-3472 Mike McGarry NUGSB0/BCP&R 202/857-9833 Stephen Maloney NUGSB0/0evonrue 617/426-4550 Charles S. Ondash NUGSB0/0evonrue 617/426-4550 Pat Baranowsky NRC/NRR 301/492-8352 Alan Rubin NRC/RES 301/492-8303 James E. Knight NRC/NRR/ DEST /SELB 301/492-7456 Paul Gill NRC/NRR/SELB 301/492-9474 Faust Rosa NRC/NRR/SELB 301/492-9466 Paul Norian NRC/RES 301/492-7112 J. Raval NRC/NRR/SPLB 301/492-9423 C. Liang NRC/NRR/SRXB 301/492-9459 A. Thadani NRC/NRR/ SAD 301/492-7687 I

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NJ1SB0 8/13/87 Meeting Attendee List i

Name Organization P ene Al Serkiz NRC/RES/0RPS 3;1/492-7487 Diane Noel NRC/RES/0RPS 3*1/492-7939 Stephen D. Floyd NUGSB0/ Carolina Power 9'.9/836-6901 Michael L. Childers kUGSB0/ Northeast Utilities 2;3/665-3472 Mike McGarry NOGSB0/BCP&R 857-9833 Stephen Maloney NUGSB0/Devonrue 617/426-4550 Charles S. Ondash NUGSB0/Devonrue 617/426-4550 J. H. Raval NRC/NRR/SPLB 3C1/492-9423 C. Y. LJang NRC/NRR/SRXB 301/492-9459 J. E. Knight NRC/NRR/ DEST /SELB 301/492-7456

. Paul Gill NRC/NRR/ DEST /SELB 3C1/492-9474 Faust Rosa NRC/NRR/ DEST /SELB 301/492-9466 Paul Norlan NRC/RES/RPSIB 301/492-7112 W

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