ML20077D898
| ML20077D898 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/22/1983 |
| From: | Selover R Public Service Enterprise Group |
| To: | Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20077D900 | List: |
| References | |
| EA-83-024, EA-83-24, GL-83-28, NUDOCS 8307270395 | |
| Download: ML20077D898 (10) | |
Text
.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ -
4 Public Service Electric and Gas Cornpany H. Edwin Selover 80 Par k Pla/a, Ne. var k, NJ 07101201-430 6%O Mailing Adifress: P.O. Box 570, Newark, N.I 07101 Vice Preskknt and cener.i counsel July 22, 1983 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission EW/W359 Washington, D. C. 20555; Re:
Norice of Violation and Proposed Imposition of Civil Penalties Docket Nos. 50-272, 50-311, License Nos. DPR-70, DPR-75 EA 83-24
Dear Mr. DeYoung:
This is to supplement the Company's July 6, 1983 response to the letter from the NRC dated May 5,
1983 transmitting a Notice of Violation and Proposed Imposition of Civil Penalties in the aggregate amount of $850,000, relating to events which occurred on February 22 and February 25, 1983 at Unit No.
1 of the Salem Generating Station.
We respectfully submit that the NRC's Generic Letter 83-28, dated July 8, 1983, entitled " Required Actions Based on Generic Implications of Salem ATWS Events" reinforces the appropriateness of the relief requested in the Company's July 6,1983 letter, in several respects:
1.
Generic Letter 83-28 reconfirms that the I
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l major items dealt with in the Notice of Violation are industry-wide;
- indeed, it requires all holders of operating licenses to take remedial measures to deal with such matters.
1 2.
All the major elements of the Action Program set forth in Generic Letter 83-28 had already been taken or committed to by the Company prior to the issuance of the Notice of Violation, so that the proposed civil penalty is not necessary to accomplish its stated purpose, namely, "to assure that PSE&G will fully implement lasting corrective actions that address the violations identified in
[the Notice of Violation]".
3.
Many elements of the Action Program set forth in Generic Letter 83-28 were either developed by the Company alone or by the Company and the NRC Staff
- together, demonstrating the Company's initiative in this regard.
4.
The comprehensiveness of PSE&G's responses to the Salem incident is demonstrated by the fact that the Action Program set forth in Generic Letter 83-28 does not include any major item applicable to the Salem units which has not already been taken or committed to
.. J by the Company.
We are undertaking a detailed review of Generic Letter 83-28 to determine what, if any, further action may be required by the Company in response thereto.
However, the principal requirements I
have becn addressed, and the NRC's safety evaluation for the restart of Salem 1 (NUREG-0995) specifically adopts the Company's corrective action plan as the basis for permitting the plant to be restarted, which seems to confirm the adequacy of the Company's plan in addressing these issues.
5.
The promptness of the Company's response to the Salem incidents is demonstrated by the fact that the Company is able to provide an initial response to Generic Letter 83-28 within two weeks of its date, rather than within 120 days (or possibly later) as contemplated by Generic Letter 83-28.
Specifically, and as more fully discussed in the Company's response to the Notice of Violation, including the Company's letters to the NRC submitted in conjunction with the restart of Salem 1 after the February events which are incorporated by reference in such response and which form the basis for our preliminary reply to Generic Letter 83-28 for Salem (copy attached),
the Company has taken or
4-committed to the following actions, which address virtually all of the requirements of Generic Letter 83-28.
References to the Company's letters incorporated by reference in the original response to the Notice of Violation are indicated where applicable.
In addition, the Company's letter to the NRC dated April 8,
1983 in conjunction with the restart of Salet 1 is referred to below.
Reference to such letter and to the Company's letter dated April 13,
- 1983, was inadvertently omitted f rom our original response, and such letters are hereby also incorporated by reference in this matter.
1.
The Company has established a
formal post trip review procedure.
See the Company's letters to the NRC dated March 8 and 14 and April 7,
8 and 28, 1983.
(Action 1.1 of Generic Letter 83-28.)
2.
The Company has a sequence of events recorder installed at Salem 1 which is capable of correctly sequencing and timing plant events leading to
. unscheduled reactor trips and indicating the proper actuation of safety-related equipment.
The recorder is driven by the plant computer and powered from a vital bus.
A report describing the data and information capability for unscheduled reactor shutdowns will be
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submitted to the NRC not later than November 7,
- 1083, in compliance with Generic Letter 83-28.
(Action 1.2. )
3.
The Company has reviewed those components whose functioning is required to trip the reactor, has verified that they are identified as safety-related on the Master Equipment
- List, which is used in classification of work orders and procurement documents, and is implementing a continuing program to insure that vendor information relating to the reactor trip system components is complete and maintained on a controlled-document basis.
See the Company's letters to the NRC dated March 8, 14 and 23 and April 7, 8
and 28, 1983.
(Action 2.1.)
4.
The Company has committed to a program to assure that components of safety-related systems are so identified on the Master Equipment List.
The Company is also implementing a continuing program to assure that vendor information for safety-related components is complete, current and maintained on a controlled-document basis.
See the Company's letters to the NRC dated March 8, 14 and 23 and April 7, 8
and 28, 1983.
(Action 2.2.)
5.
The Company has strengthened its program with
0 0 respect to post-maintenance operability testing of safety-related components in the reactor trip system so as to assure that the equipment is capable of performing its safety functions before being returned to service.
These procedures include current applicable vendor and engineering recommendations.
Related Technical Specification changes were submitted for NRC approval on June 20, 1983.
The Company is also engaged in a test program to determine the life cycle and replacement interval for the undervoltage trip attachments.
See the Company's letters dated March 8 and 14 and April 7, 8 and 28, 1983.
(Action 3.1.)
6.
The Company is establishing a
program to extend its test and maintenance procedures to assure post-maintenance operability testing of safety-related equipment, consistent with vendor and engineering recommendations. See the Company's letters dated March 8 and 14 and April 7, 8 and 28, 1983.
(Action 3.2.)
7.
The Company has obtained new undervoltage trip attachments from Westinghouse which have been verified as including all current modifications.
See the Company's letters dated April 7,
8 and 28, 1983.
(Action 4.1. )
l
8.
The Company has implemented a comprehensive preventative maintenance and surveillance program to assure reliable reactor trip breaker operation.
See the Company's letters dated March 8 and 14 and April 7, 8 and 28, 1983.
The life testing program for the reactor trip breakers is described in a letter to the NRC dated May 31, 1983.
(Action 4.2.)
9.
The Company has committed, by a letter to the NRC dated July 15, 1983, to incorporate the shunt trip attachments to the reactor trip breakers into the automatic trip system.
(Action 4.3. )
10.
Action 4.4 applies only to B&W reactors and is therefore inapplicable, 11.
The Company has strengthened its on-line testing procedures for the reactor trip system.
.See the Company's letters to the NRC dated March 8 and 14 and April 7,
8 and 28,
- 1983, and License Change Request, LCR 83-08, submitted June 20, 1983.
(Action 4.5.)
In all of the above matters involving station procedures, personnel have been re-educated in the importance of strict adherence thereto to assure that the procedures accomplish their intended results.
Upon completion of our review of
. Generic Letter 83-28, we will advise the NRC of further actions, if any, which may be necessary or appropriate with respect to Salem.
- However, as mentioned
- above, it is apparent that the Company's corrective action program comprehensively addresses the matters in Generic Letter 83-28, which is relevant to the determination of the amount of any civil penalties.
In the light of this record of
- prompt, comprehensive response to what the Commission has repeatedly characterized as a generic problem, and the adoption by the Company of a program before the issuance of the Notice of Violation that is now virtually embodied in the Commission's Generic Letter 83-28, we submit that the imposition of the proposed civil penalties cannot reasonably be viewed as serving a remedial purpose.
We again confirm to the Commission our commitment to safe nuclear operations and our dedication to strong remedial measures with respect to the equipment responsible for the February
- failures, the related operating and maintenance procedures, and the execution of such procedures by personnel.
For the reasons set forth above and in our July 6,
1983
- response, we respectfully request that the
!, i proposed civil penalties in the Notice of Violation be eliminated or mitigated substantially.
Respectfully submitted, Vic2 President and General Counsel cc:
Dr. Thomas E. Murley, Regional Administrator U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa. 19406
~-
.g STATE OF NEW JERSEY
)
sS.
COUNTY OF SALEM
)
RICHARD A.
- UDERITZ, being duly sworn according to law deposes and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in the attached supplemental response to the NRC's Notice of Violation and Proposed Imposition of Civil Penalties, Docket Nos. 50-272, 50-311, License Nos. DPR-70, DPR-75, EA83-24, are true to the best of my knowledge, information and belief.
t kA RICHARD A. UDERITZ /
4 Subscribed and sworn to before me this 22nd day-of July, 1983.
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't otary eublid of New Jersef
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nonoua L van r10CHER JR.
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on Expuu sept.10,174 L
My Commission expires l
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l Orc Sea. ice Elecinc and Gas Compam P O. Scx 236 Hancocws Br:cge. New Jersey C8038 Nuclear Department July 22, 1983 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission.
7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen:
RESPONSE TO GENERIC LETTER 83-28 NO. 1 AND 2 UNITS SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 PSE&G hereby submits its response with respect to Salem Generating Station, to Generic Letter 83-28, dated July 8, 1983, concerning required actions based on generic implications -
of the Salem reactor trip breaker failures on February 22 and February 25, 1983.
l.1 POST-TRIP REVIEW (PROGRAM DESCRIPTION & PROCEDURES)
The Salem post-trip review program is described in our letters to the NRC of March 8, 14 and April 7 and 8,
- 1983, submitted in conjunction with the restart of Salem 1 after the February events.
The detailed instructions are provided in Administrative Directive AD-16, which was submitted with our letter of March 14, 1983.
The latest revision of AD-16 is enclosed.
1.2 DOST-TRIP REVIEW ( DATA & INFORMATION CAPABILITY)
The Salem units have an existing sequence of events recorder installed which is capable of correctly sequenc-ing and timing plant events leading to unscheduled reactor trips, and indicating the proper actuation of safety related equipment.
The sequence of events recorder is driven by the plant computer and powered from a vital bus.
YO 2-
,q73g7270 ppd The Energy People
J Director of Nuclear, Reactor Regulation U.
S.
Nuclear Regulatory Commission 7/22/83 2.1 EOUIPMENT CLASSIFICATION & VENDOR INTERFACE (REACTOR TRIP SYSTEM COMPONENTS)
Equipment classification and vendor interface programs are described in our letters of March 8, 14, 23 and April 7 and 8, 1983.
2.2 EOUIPMENT CLASSIFICATION & VENDOR INTERFACE (PROGRAMS FOR ALL SAFETY-RELATED COMPONENTS)
Equipment classification and vendor interface programs are described in our letters of March 8, 14, 23 and April 7 and 8, 1983.
3.1 POST-MAINTENANCE TESTING ( REACTOR TRIP SYSTEM COMPONENTS)
Actions 3.1.1 and 3.1,2 of this position have been implemented as described in our letters of March 8, 14, and April 7 and 8, 1983.
3.2 POST-MAINTENANCE TESTING (ALL OTHER SAFETY RELATED COMPONENTS)
Actions 3.2.1 and 3.2.2 of this position have been implemented as described in our letters of March 8, 14 and.
April 7 and 8, 1983.
4.1 REACTOR TRIP SYSTEM RELIABILITY (VENDOR-RELATED MODIFICATIONS)
Vendor-recommended reactor trip breaker modifications have been implemented as described in our letters of April 7 and 8, 1983.
~
4.2 REACTOR TRIP SYSTEM RELIABILITY (PREVENTATIVE MAINTENANCE AND SURVEILLANCE PROGRAM FOR REACTOR TRIP BREAKERS)
Descriptions of the Salem preventative maintenance and surveillance programs have been provided in our letters of March 8, 14 and April 7 and 8, 1983.
The life testing program for the reactor trip breakers is described in our letter of May 31, 1983.
4.3 REACTOR TRIF SYSTEM RELIABILITY (AUTOMATIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR WESTINGHOUSE AND B&W PLANTS)
This item is addressed in our letter of July 15, 1983 (attached).
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Director of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission 7/22/83 4.4 REACTOR TRIP SYSTEM RELIABILITY (IMPROVEMENTS IN MAINTENANCE AND TEST PROCEDURES FOR B&W PLANTS)
This item does not apply to Salem.
4.5 REACTOR TRIP SYSTEM RELIABILITY (SYSTEM FUNCTIONAL TESTING)
On-line functional testing is described in our letters of March 8, 14 and April 7 and 8, 1983, and in o'ur License Change Request, LCR 83-08, submitted on June 20, 1983.
This response provides our current status of conformance with the positions described in Generic Letter 83-28.
Acceptance of our corrective action program is documented in your safety evaluation (NUREG-0995), transmitted with your letter of April 29, 1983, authorizing restart of the Salem units.
We are undertaking a detailed review of Generic Letter 83-28 to det. ermine what, if any, further actions may be required.
The results of this review will be submitted for your review no later than November 7, 1983.
Should yoi* have any questions, do not hesitate to contact us.
Sincerely, E.
A.
Liden Manager - Nuclear Licensing and Regulation Attachments CC:
Mr. Donald C.
Fischer Licensing Project Manager Mr. Leif Norrholm Senior Resident Inspector
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STATE OF NEW JERSEY
)
)
SS.
COUNTY OF SALEM
)
RICHARD A. UDERITZ, being duly sworn according to law deposes i
and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our
(
response to Generic Letter 83-28, dated July 22, 1983, concerning generic implications of the Salem ATWS events, are true to the best of my knowledge, information and belief.
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/d RICHARD A.
UDERITZ Subscribed and sworn to before me this
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Notary Public of New Jersey My Commission expires on O c 7 e--.*w, 7, / 7.\\ "i
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g SALEM GENERATING STATION N
OPERATIONS DEPARTMENT DOCUMENT APPROVAL COVER SHEET
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Post Reactor Trip / Safety Injection Review No.:
AD-16 Unit:
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Remarks: eight oages of text, one - six page form, one - four page fo a, on
- two pama _ahle, revised to add documentation for General
- 'anager res ew, de'.eted startup approval requirements after controllec shutdown, deletied I&C Supervisor signature on Sequence of Ivents.
Safety Related Review (Ref. AD-13 ) :
S/ R yes-X no Author's Checklist Completed:
yes x
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Salem Unit 1/2/
OTX" AD-1-B-1
ADMINISTRATIVE DIRECTIVE - 16 l
POST REACTOR TRIP / SAFETY INJECTION REVIEW l
1.0 PURPOSE The purpose of this directive is to establish the requirements to per:orm a ormal post trip review for all Reactor Trip and Safety Injection events.
This directive also establishes the requirements and criteria that must be et prior to the startup of either unit following e trip event.
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2.1.1 Ensure that a cost tric revieu of the even: has
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The cause of the event is c'_early identified.
2.1.4 Notify the Operations F.anager of the event and the subsequent findings of the report.
(The Operations Manager may elect to conduct this
.A review by telephone in direct conference with the Senior Shift Supervisor.)
2.2 The STA qualified Shift Supervisor shall assist and advise the Senior Shift Supervisor in the compiling of data and evaluation of the report.
Salem Unit 1/2 1
Rev. 3
~
AD-16 2.3 In the event of a Reactor Trip or Safety Injection, the operations Manager shall:
2.3.1 Perform the following prior to granting approval for startup:
4 a)
Review the post trip report with the Senior Shift Supervisor, b)
Ensure that the report was properly prepared and evaluated.
c)
Ensure that the cause of t'm event has been
.c roc. e r l.y identified.
i d)
Ensure that all ec.ute. ment and systems function'ed as dasigned during the event and I
receverv actions.
1 el Evaluate the event to deterr.ine if there are any corrective actions required orier tc the
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As ".ecessary, request additionni nechr.ical suppcr, to evaluate *.he event and ersure that the cause is clearly identified cnd the required corrective actions have been initiated.
2.3.2 Grant approfel for startup in ccordance with Sectier 4.0 of this directiva if all of the requirements 1,isted above are met satisfacterily.
- if one or v. ore of the 2.3.3 Denv accroval for startuo requarements listed above is not satis: actor:1y met.
If this is the case, direct the Senior Ocerations Sucervisor to conduct a furti er
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investigation of the event.
2.3.4 Perform a follow up review of the report and recommend any corrective actions. Conduct interviews as necessary to determine the effectiveness of the procedures used, this directive and, in particular, of the' report itself.
Note any changes which may enhance the conducting or the review of the report.
Sign and date the Followup Section of the report.
2.3.5 Forward the completed report to the Senior Operations Supervisor for additional processing.
Salem Unit 1/2 2
Rev. 3
r AD-16 i
t l
2.4 The Senior Operations Supervisor shall:
2.4.1 Incorporate the event into the Reactor Trip / Safety Injection history trending system.
2.4.2 Make three complete copies of the report.
These copies shall go to:
l a)
The Technical Department for assistance in preparing the Licensee Event Report or other.
rec. orts as ac.c.ropriate.
i b)
The General Manager Nuclear Support in order to conduct an independent review of the trip event.
c)
The Man?.ger - Nuclear Tr'aining for appropriate disbursament to the training classes.
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2.4.3 "nintain the original report on file for future reference.
2.4.4 Conduct an investigation of the even: if the Operations Manager denies startup approval.
Present the findings to the Station Opers.tions Review Ccamittee.
has been ranted by c.ae 4.s.o
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Operations Manager, cresent the recort to the Station Cperations Rev.tew Committee for revieu, l
2.4.6 Prepare a summary report on the event and issue it to all pertinent Operations Department personnel in accordance with the Informaticn Directives System.
- ~ ~
2.4.7 Revise this document as necessary to incorporate any comments on improving the effectiveness of it as directed by the Ope;ations Manager.
2.5 The Nuclear Support Department will perform an independent review of each Reactor Trip / Safety Injection.
Upon completion of the review, Nuclear Support will make recommendations to the station for corrective actions which may prevent this type of event from re-occuring in the future.
G Salem Unit 1/2
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Rev. 3 f
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AD-16 i.
2.6 The Instrumentation and Controls Engineer will designate a supervisory person to assist the Senior Shift Supervisor and the STA qualified Shift Supervisor in the review of the Sequence of Events print out for each Reactor Trip / Safety Injection Event.
3.0 TRIP EVENT REVIEW PROCESS l
3.1 The Senior Shift Supervisor shall ensure that:
I 3.1.1 The recuired information on Form AD-16-A l
concerning the condicion of che unic prior to the event is correct cc' has been recorded.
3.1.2 The evolutions in progress prior to the event that may be involved in the cause of event or could have contributed to the cause of the event have been recorded.
Exarples:
i a.
Unit scartup was in progres;, f e ed -ca te r l
control was in manuc1 control, b.
Unit startup ;as in progress, problems 'iere encountered with inservice ecuipment or control systems. (S eam Dump was in manual, 5 team Generator Feed Pump ccntrols were in manual, Atmospheric relief velves vere being used to dump steam, etc.).
c.
A rapid reduction in unit load was required due to loss of circulators, condenser vacuum, condensate pump, heater drair pump, condensate strainers were partially cicgged.
d.
Surveillance testing was in prcgress on the Reactor Protection System.
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e.
Maintenance or trouble shooting was in
- progress, i
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STER l
Salem Unit 1/2 4
Rev. 3
AD-16 i
l 3.1.3 All equipment that was cut of service that could have contributed to the event has been identified and recorded.
Examples:
a.
Steam Dumps were not available.
b.
Number 11A and 11B circulators were out of service.
c.
The positive displacement charging pump was Cleared and Tacced for recairs.
2s d.
Feedwater heater string was bypassed or out of service for repairs.
3.1.4 The proper classification of the event, the time that the event was declared, the time that the event was terminated, and if a'l the necessary
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Attach the oririnal co.cv. cd the Emergency Precedure tc the repc c package.
1.1.5 The P-250 computer sequer.ce of events prin::un has been reviewed and the Sequence of Events Checklist L*orm AD-16-3) has been completed tc verify the cause of the event and ensure that all equipment and systems performed as designed and in the proper and expected sequence.
The subsequent alarms listed or the Sequence of Events Checklist are not listed in the order in which they should occur; this will vary.ith the event.
In addition, all of the alarms listed on the checklist might not occur with every event.
Table 1 contains the expected times at which the Subsequent alarms should print out.
It shculd be noted that the times are onlv. accroximate and
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will be further refined as exc.erience is cained.
Attach the computer printout to the report package.
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Salem Unit 1/2 5
Rev. 3 l
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AD-16 1
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3.1.6 The following control room recorder charts have been reviewed for unexpected or unusual parameter
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changes during the event:
a.
Steam Generator Narrow Range Levels LA-5048, LA-5049, LA-5050, LA-5051 b.
Pressurizer Level LA-5304 c.
Pressurizer Pressure PA-5305 d.
TAVE TA-5306 e.
Reactor Coolant Loop Th, Tc TA-0014, TA-0016, TA-0036, TA-0033 f.
Nuclear Power Range MR-45 XA-5904 I
l g.
Other charts as necessary Have the Shift Technician remove these charts.
i I
Insure that all tracings are identified on the charts and the time is clearly v.arked.
A::ach the cric.inal charts to the reecrt.nack ac. e.
3.1.7 Any alarms received which were out of the ordinary for the even; and alarms whic'r should have been received but were'not have been recorded.
Include a revicu of the everhead alar =s, console alarms, P-250 alarms and the Auxiliary Alarm typeuriter.
At:ach the prin:cu:
from the Auxiliary Alarr typewriter and the P-250 alarm printout.
3.1.8 Fact finding sessions are conducted with the appropriate personnel to determine the cause of the event, actions taken and observed sequence of events.
3.1.9 The explanation of the cause of the event is l
recorded.
3.1.10 The corrective actions taken during the event to l
j mitigate the consequences of the event and bring the unit to a stable condition are recorded.
1 i
3.1.11 Any equipment out of service which would prevent
-the unit from being returned to service has been recorded.
Salem Unit-1/2' 6
Rev. 3 i,-,r e
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i l
i AD-16
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l 3.1.12 All T.echnical Scecification or Adminstrative Action Statements that are required to be te'minated prior to reactor startup have been r
recorded.
(Administrative Action Statements as identified in other Operations Department Directives, such as defined in CD-12.)
3.1.13 Any corrective actions that are required p
'.cr t:
the unit's return to service are recorded.
3.1.14 The names and assigned positions of all individuals involved in the event are rec rdef.
3.2 The Senior Shift Supervisor shall confer with the SJJ.
qualified Shift Supervisor in order to review and evaluate the report.
When both are satisfied with the conclusions, each shall sign and date the report.
3.3 The Operations Manager shall he briefed b-; the Senior Shift Supervisor en the report.
At that tire, a determination shall be made as to **.e:her cpprc"al should be granted for startup as definef in Eactior. 4.0 of :his directive.
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v TRIP / SAFETY IN~ECTION 4.1 Prior to requesting approval to startup th,e reactor after any Reactor Trip or Safety Injection, the.Ses:
Trip Review must be completed and evaluated.
4.2 Upon satisfactory completion of the review and evaluation of the Post Trip Periew, the Operations-Manager may authorize the reec:cr startup as long as the evaluation of the trip event clearly indicates the cause of the even:
and that all equipment and systems functioned as designed.
4.3 If the Operations Manager-Salem Operations is not i
available, then the individuals who are authorized to assume the Operations Manager's responsibilities may authorize the reactor startup.
l Salem Unit 1/2 7
Rev. 3 i
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AD-16 s
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4.4 If the cause of the event has not been clearly determined or there is question concerning the proper i
performance of equipment or systems during the event, then an investigation shall be conducted and the results of the investigation shall be reviewed by the Station Operations Review Committee.
Upon completion of the evaluation of the event by the Station Operations Review Committee, the Committee shall make recomme-t ti;.u.
_a the General Manager-Salem Operations on reactor startup.
Upon completion of the review and satisf:..-t:c.y determination that the unit can be resta: ted sefely, ne General Manager-Salem Operations Tay aurherire t.:
reactor startup.
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END OF ?RCCEDil2E i
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FINAL PAGE i
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ADMINISTRATIVE DIRECTIVE - 16 POST REACTOR TRIP / SAFETY INJECTION REVIEW REPORT CONDITIONS PRIOR TO EVENT Date of Event Time of Event Affected Unit Unit Conditions Prior to the Event Reactor Power Personnel Assignments SSS SS Board NCO Desk NCO l
Primary EO Secondary EO SSuos Shift Tecri.ician Oth'ers Shift Elect: 1._ E~
(Relay' Dept., ILC, l
Maint., Maplewood Lab etc.)
.'h a t e"olutions were in progresc at the enset of the event:
Surveil' lance Testing Yes No Trouble Shooting or Maintenance Yes No s
Unit Startuo or Shutdown Activities les No l
Other Activ' ties which could have contributed to the event i
Yes
-No If the answer to any of the above questions is yes, describe athe circumstances'in detail.
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1 We.re any of the following out of service or inoperable at the onset of the event:
Major Equipment Yes No Protection Systems or Trains Yes No e
Control Systems Yes No If the answer to any of the abcVe questions is yes, describe the circumstances in detail.
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Salem Unit 1/2 AD-16-A-1 l
Rev. 3
DESCRIPTION OF THE EVENT Reactor Trip Initiation Automatic Yes No If no, explain why.
If yes, give the Reactor First Out Annunciator Safety Injection Initiated Yes No l
If initiated, was it automatic
_ves No If no, explain why.
If yes, give the actor First Out Annunciator.
Attach ATT l-1 from EI I-4.2 if Safety Injection occurec.
What is the classification of the event as defined in EP I-O?
Time Declared Time Terminated nere all of the recuired notifications made?
Yes No If no, explain why, Attach Emergency Procedure to Report Package.
Does the Sequence of Events Printout frca the P-250 agree with the Reacter First Out Annunciator which was received?
Yes No If no, explain which First Out was received and any apparent reasons for the discrepancy.
(eg.
Two alarm conditions actuated simultaneously)
Attach Printout to Report Package.
Do the recorder charts indicate any trends which may have contributed to the event?
Yes No If yes, explain in detail.
Attach Recorder Charts to Peport Package.
Salem Unit 1/2 AD-16-A-2 Rev. 3
~
e9 Were there any alarms which annunciated which were unusual for the event?
Yes No If yes',- explain in detail.
I t
Were there any alarms which should have annuciated but did not?
Yes No If yes, explain in detail.
Explain in detail the sequence of events which led to the initiation of the event and the actions performed to place the plant in a stable condition.
Include the observaticns and actions of i
specific individuals and the adequacy of the procedures used.
Attach additional paces as required.
.a Salem Unit 1/2 AD-16-A-3 Rev. 3 i
CORRECTIVE ACTIONS Is there any equipment out of service which would prevent the unit from being returned to service?
Yes No If yes, explain in detail.
l Are there any Technical Specification sr Administrative Action i
i 3 t a t -2..e n t s in effect whicn would prc/ent the unit from returning
- c se r.-ice ?
(Administratise Action Statements are described in 33-12 or other Operations Dep?.rtreut documents)
Yes No If yes, list below.
Tech Specs Admin.
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.re there any corrective actions which should be performed before returning the unit to service, such as repairs uhich should be rade?
Yes No If yes, explain.
Provide specific recommendations as appropriate.
Report Prepared By Date Time Report Reviewed With Operations Manager Date Time Approval for startup by Operations Manager:
Granted Denied 1
Date Time STA Qualified Shift Supervisor Date Time (Signature)
Senior Shift Supervisor Review Date Time (Signature)
Salem Unit-1/2 AD-16-A-4 Rev. 3 J
i SORC AND GENEPAL MANAGER REVIEW This page will be used only when the initial approval for startup is, denied by the Operations Manager and subsequent reviews of the event l
are required.
MAJOR FINDINGS OF SUBSEQUENT INVESTIGATIONS I
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A::ach other sheets as necessary.
DETERMINATIONS SY SORC l
t Attach other sheets as necessary.
STARTUP APPROVAL l
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SORC Chairman Date l
General Manager-Salem Date MASTER S.1.m n1t 1m
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OPERATIONS MANAGER FOLLOWUP i
Corrective actions required to prevent reoccurrence of tnis event.
';ote any changes *o this document which may improve its e::ectiveness 1
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Report Reviewed By Cperations Manager Date Time (signature)
NOTE:
This review is not required prior to authorizing startup.
SENIOR OPERATIONS SUPERVISOR FOLLOWUP Copies of-the report sent to:
Technical Department Date Nuclear Support Department Date Nuclear Training Department Date Station Operations Review Committee Review Chairman Meeting No.
Date Salem Unit 1/2 AD-16-A-6 i
Rev. 3 4
SEQUENCE OF EVENTS CHECKLIST DIRECTIONS The-information to be recorded on the Sequence of Events Checklist (pages AD-16-B-2 and AD-16-B-3) is to be a direct transfer of information from the Sequence of Events print out.
Simply record the number of cycles at which the subsequent alarm occurred and the Sequence of Events start time in which it occurred.
The subsaquent a ' a rm s listed on the Sequence of Events Chechlist must be related to the initial Reactor Trip or Safety Injection signal associ-tod with each trip.
To perform this, the following l
guide'ines should b used.
I 1.
If the subsequent alarm occurred in the same s c,nence as "So T.aactor Trio, or Safety Injection sicnal, s i c c. i v.
d subtract the number of cycles at which the Reactor Trip or Safety Injection signal was generated frc: the number i
of cycles at which the s u b s e*c" a a -
=1=--
Nas generated.
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2.
If the subsequent alarn occurred in a sequence separate i
from the Reactor Trip or Safety Injection signal, perforn the following:
1 i
a.
Subtract the Reactor Tric or Safe:. :nie :icn j
signal sequence start time : rem :ne sucsequent j
alarm sequence start time and nul:iply this nurber l
by 60.
I b.
From this number, subtract the number of cycles at whic'r the Reactor Trip or Safety Infectier signal was generated.
c.
To this number, add the n. umber of cycles at which the subsequent alarm was generated.
This is the number of cycles at which the alarm *as generated after the Reactor Trip or Safety Injection signal.
This information shall be recorded on page AD-16-3-4.
.a Salem Unit 1/2 AD-16-B-1
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I SEQUENCE OF EVENTS CHECKLIST Reactor Trip or Safety Injection signal sequence start time:
~ REACTOR TRIP SIGNAL INITIATED AT cycles SAFETY INJECTION SIGNAL INITIATED AT cycles l-sequence start 4 cycles t ir..
in which alarr Sir.s'"" c.t Alarms into secuence was initiated REACTOR MAIN TRIP BKR A TRIP
?.EACTOR MAIN TRIP BKR B TRIP l
REACTOR TRIP AUX 1 BFR A TRIP l
J FIACTCP TRIP AUX 1 EKR 3 TRIP REACTOR MAK TRP 1 TRIP REACTOR MAN TRP 2 TRIP TURBINE STOP VA 11(21) CLOSED TURQINE STOP VA 12(22) CLOSED TURBINE STOP VA 13(23) CLOSED TURBINE STOP VA 14(24) CLOSED TURBINE TRIP TRIP TURBINE REMOTE EMERG TRIP TRIP T
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Salem Unit 1/2 AD-16-B-2 Rev. 3 t
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sequence start 4 cycles time in which alarm Subsequent Alarms into sequence was initiated 11(21) AUX FW PUMP START i
l 12(22) AUX FW PUMP START I
l 1
l13 ( 2 3 ) AUX FW PUMP TUPBINE STOP 7A ST CL 11(21) SGFP TURBINE HRH STOP VA CLOSED 12(22) SGFP TURBINE MS STOP VA CLOSED 12(22) SGFP TURBINE HPH STOP VA CLOSED 11(11) SGFP TUR3INE.IS STOP VA CLOSED
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Salem Unit 1/2 AD-16-B-3 Rev. 3
SEQUENCE OF EVENTS CHECKLIST
SUMMARY
number of cycles after Subsecuent Alarms Reactor Trip /SI sianal REACTOR MAIN TRIP BKR A TRIP 9.zACTOR MAIN' TRIP BKR B TRIP REACTOR TRIP AUX 1 BKR A TRIP REACTOR TRIP AUX.1 BKR S TRIP PEACTOR MAN TRP 1 TRIP
. REACTOR P.AN TRP 2 TRIP l'
i TL R3I::E STOP VA 11(21) CLOSED l
iTURPINE STOP 'IA 12(22) CLOSED I
l pCR3I'.1E STOP VA 13(23) CLOSED l
{TUREINESTOPVA 14(24) CLOSED L_URBINE TRIP TRIP iTURBINE REIOTE EMERG TRIP TRIP 11(21) AUX FM PUMP START 12(22) AUX FM PUMP START 13(23) AUX FW PUMP TURBINE STOP VA NT CL 11(21) SGFP TURBINE HRH STOP VA CLOSED 12(22) SGFP TURBINE MS STOP VA CLOSED 12(22) SGFP TURBINE HRH STOP VA CLOSED 1
11(21) SGFP TURBINE MS STOP VA CLOSED l
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l Salem Unit 1/2 AD-16-B-4 Rev. 3 I
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AD-16 SEQUENCE OF EVENTS STANDARDS FOR A REACTOR TRIP 1
Expected time to initiate after trio sianal Subsecuent Alarms cycles seconds REACTOR MAIN TRIP BKR A TRIP 4-6 0.06-0.1 REACTOR MA!N TRIP BKR B TRIP 4-6 0.06-0.1 REACTCR TRIP AUX 1 BKR A TRIP 4-6 0.06-0.1 REACTOR TRIP AUX 1 BKR B TRIP 4-6 0.06-0.1 REACTOR MAN TRP 1 TRIP less than 300 less than 5 REACTCR MAN TRP 2 TRIP less than 300 less than 5 TUFEIME STOP VA 11(21) CLOSED less than 90 less than 1.5 URBINE STOP VA 12(22) CLOSED less tha.- 90 less than 1.5 I
i frJRBISE STOP VA 13(23) CLOSED less than 90 less than 1.5 i
TURBINE STOP VA 14 (24) CLOSED less than 90 less than 1.5 TURE$ME TRIP TRIP 4-6 0.06-0.1 i
EURBINE REMOTE EMERG TRIP TRIP less than 60 less than 1 11(21) AUX FW PUMP START
- 12(22) AUX FW PUMP START
Should initiate within 10 cycles (0.2 sec) after any 1 Steau Generator Lo Lo Level valid trip signal.
i Should initiate within 100 cycles (1.7 sec) after any 2 Steam Generator Lo Lo Level valid trip signals.
Rev. 3
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Salem Unit 1/2 TABLE l-1 g
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SEQUENCE OF EVENTS STANDARDS FOR A SAFETY INJECTION l
Expected time to initiate after SI sicnal Subsecuent Alarms cycles seconds REACTOR MAIN TRIP BKR A T979 4-6 0.06-0.1 REACTOR MAIN TRIP BKR B TRIP 4-6 0.06-0.1 t
REACTOR TRIP AUX 1 BKR A TRIP 4-6 0.06-0.1 REACTOR TRIP AUX 1 BKR B TRIP 4-6 0.06-0.1
'11(21) AUX FW PUMP START less than 10 less than 0.2
?. 2 ( 2 2 ) AUX FU PUMP START less than 10 less than 0.2 1
'Ol ACTOR MAN TRP 1 TRIP less than 300 less than 5 fi..CTOR MAN TRP 2 TRIP less than 300 less than 5 i
.UR3INE STOP VA 11(21) CLOSED less thar 90 less than 1.5 j
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t:UR3INE STOP VA 12(22) CLOCED less than 90 less than 1.5 i
i TU?3I::E STOP VA 13(23) CLOSED less thar 9C less thar 1.5 1
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77E3INE STOP VA 14(24) CLOSED less thar 90 less than 1.5
.I TURBINE TRIP TRIP 4-6 0.06-0.1 i,
TURBINE REMOTE EMERG TRIP TRIP less than 60 less than 1 (11) 11 SGFP TURBINE HRH STOP VA CLOSED less than 90 less than 1.5 (22) 12 SGFP TURBINE HRH STOP VA CLOSED less than 90 less than 1.5
^ ~~
(21) 11 SGFP TURBINE MS STOP VA CLOSED less than 90 less than 1.5 i
(22) 12 SGFP TURBINE MS STOP VA CLOSED less than 90 less than 1.5 13(23) AUX FW PUMP TURBINE STOP VA NT CL
- Should initiate within 100 cycles (1.7 sec) after any 2 Steam Generator Lo Lo Level valid trip signals.
. Salem Unit 1/2 TABLE 1-2 Rev. 3 l
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