ML20244B662
| ML20244B662 | |
| Person / Time | |
|---|---|
| Issue date: | 10/10/1984 |
| From: | Lafleur J NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP) |
| To: | Brinkman D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20244B550 | List: |
| References | |
| FOIA-89-99 NUDOCS 8904190320 | |
| Download: ML20244B662 (11) | |
Text
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i UNITED STATES E"'. N NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20$55 y. c, 9. 1
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OCT 101984 MEMORANDUM FOR:
Donald Brinkman SSPB/DL/NRR FROM:
Joseph D. Lafleur, Jr., Deputy Director Office of International _ Programs l
SUBJECT:
GUIDANCE FOR ADVISORY MISSION TO THE PHILIPPINES 1
Ann Gore will provide you with certain background materials and information j
pertinent to your' scheduled visit to the Philippines.
In addition, I would like to offer the following generalized guidance which applies to NRC experts on IAEA-sponsored assistance missions to other countries.
Role of NRC experts on IAEA safety assignments An expert chosen by the IAEA and the NRC to participate in an IAEA-sponsored j
assistance activity is selected on the basis of his personal safety expertise and serves in an individual capacity while on the assignment, not as a govern-mental representative. The IAEA takes the position, with the government of the country which is being assisted, that the views of the expert who is being i
pr'ovided do not engage the IAEA or the expart's government in any way or imply any commitment on the part of the IAEA or that' government.
NRC and IAEA expect an NRC expert to give his best advice to the government and utility contacts of the foreign country on questions' which fall within his competence, including his professional training and experience and his knowledge of U.S. engineering and regulatory standards and practices.
Moreover, NRC and the IAEA hope that our exper's will give assistance which t
goes beyond simply answering questions on current problems; we hope our experts will provide advice which can help ~ structure the regulatory activities i
of a country to better prepare it to deal independently with its nuclear safety responsibilities in the future.
On the other hand, his comments should be formed to the scope of the mission on which he is sent.
He should not offer advice on political matters, or on other policy matters outside this scope.
Reporting IAEA instructions which cover the handling of reporting and travel i
requirements will be conveyed to you by the IAEA.
In addition, upon your return, you should make a brief verbal report to IP and your own management regarding your.mftssion.
If you believe that a written report is appropriate, ~
or after consultation with IP or your management, a written report is requested, you would be expected to provide such report to IP and to your I
management.. Any written reports and documentation produced or obtained in the course of or following the mission, are with the exception of your report to the IAEA, clearly subject to the provisions of the Freedom of Information Act.
Any materia.ls containing proprietary information or information which should l
be classified, shculd be clearly marked according to established procedures.
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Donald Brinkman OCT 101984 Backup support In case of some problem or unforeseen development during your visit, do not hesitate to contact one or more of the following people, day or night, by collect telephone call:
(a) Marsha Dewitt Ecenomic Section American Embassy 1201 Roxas Blvd.
Tel. 598-011 (Official U.S. Government contact for policy guidance or problems such as a lost 4
pass ort, official harassment, etc.
(b) Ann Gore Office of International Pro rams Telephone:
(301)492-7000 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)
(NRC international policy (301)492-4504 office) guidance, help on any otherproblem.)
I Contact with the Philippine Atomic Energy Comission:
Dr. Manuel R. Eugenio Commissioner Philippine Atomic Energy Commission l
P.O. Box 932 Metro Manila The Philippines
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Jos D. Lafleur, Jr.
DepMy Director j
Office of International Programs i
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Republika og Pilipinas J
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KOMISYON NG LAK AS ATOMIKA NG PILIPIN A S 5
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( PHILIPPINE ATOMC ENERGY COMMISSION) k Oon Mariano Marcoe Avenue, Citiman.
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Quezon Cuy P.O. BOX 932 Monito C4 ble g r o m PHI L ATOMIC Tele phe n.
No 97-60-11 to 15 Teien No 66804 Ref.: DNRSIS No.
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5 November 1984 MEMORANDUM FOR:
The Commissioner THRU: The Head, DNT
Subject:
Scientific Visit and Expert in Operating Reactor Licensing It is requested that a.2-month scientific visit and expert in operating reactor licensing be provided in the 1985 IAEA Regular Programe for PAEC.
The request is made on the strength of a recommendation made by Mr. Donald S. Brinkman, IAEA Technical Cooperation Expert on Technical Specifications who had expressed the need for a PAEC staff member to undergo a scientific visit in the field of operating reactor licensing. The PAEC staff member will observe the work of an Operating Reactor Project Manager of the Licensing Branch, Office of Nuclear Reactor Regulation, USNRC to enable him to learn the methods rad procedures of making license amendments.
Needless to state, operating if censes will be amended periodically during plant operations, especially !n the area of technical specifications.
PAEC should also request IAEA'for an expert in the area of licensing operating reactors to back stop the scientific visit of the PAEC staff member.
In this conneathn, it is recomended that Mr. Vicente V. Nacario, Officer-In-Charge, Safety Evaluation and Licensing Division, DNRS be notainated for the 2-month scientific visit.
Mr. Nacario has been involved in licensing PNPP-1 since he was designated OIC, SELD. He has been handling the review and prepa-ration of the PNPP-1 Technical Specifications aside from his assignment as coordinator of the review of the PNPP-1 Final Safety Analysis Report (FSAR) and preparation of the PNPP-1 Safety Evaluation Report (SER).
It goes without saying that the scientific visit will not only serve him well but also enhance the PAEC image as regulator.
It is likewise requested that this matter be acted upon imediately considering its importance now that PAEC is in the final stage of issuing NPC a license to operate PNPP-1.
AG BENITO C. BERNARDO k. /td Chief, Dh S
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KOMISYON NG LAKAS ATOMIKA NG PILIPIN AS 1
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(PHILIPPINE ATOMIC ENERGY COMMISSION)
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Oon Mariano Marcos Avenue, Dilman,
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Quezon Oty 1
P.O. Box 932 Monito Ccble g r am PHILAfoMIC Telephone No. 9 7-60-11 to 15 Tetet No. 66804 DNRS15 No. 2.1.84157 Ref:
i 13 November 1984 The President National Power Corporation Corner Quezon Avenue & GIP Pd.
l East Triangle, Oiliman Quezon City ATTN:
Mr. Jose C. Torres i
Manager. NPD SUBJECT : PNPP-1 Technical Specifications.
Dear Sir:
f Please be informed that we have found the proposed PNPP-1 Technical Specifications in general as addressing the necessary topics to be of this type in included in the Technical Specifications for a plant We arrived at this l
accordance with the current licensing requirements.
j evaluation af ter reviewing tne proposed PNPP-1 Technical Specifications 4
l with the assistance of Mr. Dnnald S. Brinkman, I AEA Technical Cooperat r/
Expert on Technical Specifications.
[
However, we also found tnat the PNPP-1 Technical Specifications needed l
to be modified in order to conform to the Technical Specifications that we l
These modifications shall be made in accordance to the j
want for PNPP-1.
All of recommendations and suggestions enumerated in the attached list.
j these recommended changes are explained in the text of the reconinendations However, if they are found to be vague or ambiguous, we will be glad to meet and sit with your specialists as early as possible to discuss them.
We may be able to arrive at agreements that would redound to nur mutual benefit.
Further to this we art: cequiring you to review again the proposeo Technical Specifications to verify that they accurately reflect the as-built plant, that they are consistent with the safety analyses and that the j
requirements of the proposed Technical Specifications can be complied wi I
Should' any inconsistencies be found please inform us and performed.
immediately so that resolutions can be made prior tn the issuance of :ne Operating License.
Thank you.
Very trul y jours,
MA UEL R, EUGENIr
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Commissioner fj, i
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l ATTAuiMENT-i-
Recommended Changes / Modifications in Proposed PNPP-1 Technical Specifications _
1.
Revise Definition 1.25 REPORTABLE OCCURRENCE to be consistent with the changes made by the issuance of 10 CFR 50.72 and 10 CFR 50.73. These
)
changes were noted in Generic Letter
- 83-43, " Reporting Requirements of 10 CFR Part 50, Sections 50.7,2 and 50.73, and Standard Technical
. Spec i fi ca t ions. '
2.
Revise Definition 1.27 SHUTOOWN MARGIN to require that the highest reactivity worth control rod cluster assembly always be considered fully i
withdrawn and unavailable for insertion. This allowance is necessary to account for an uncontrolled control rod cluster assembly' withdrawal.
3.
All figures be printed on' graph paper so that the limits can be accurately determined. Also note regions of unacceptable and acceptable operation.
4 Review Instrumentation tables to verify that the specified setpoints are i
consistent-with the values used in the safety analyses (See Chapters 7 and 15 of FSAR) and that values be provided for all Functional Units.
Also provide surveillance frequencies for all Functional Units.
l S.
Modify Action Statements for Specifications 3.1.1.1 and 3.1.1.1.2 to make acceptable equivalent boration rates.
6, Verify whether the Safety injection Pumps are capable of injecting water from.the RWST if they are to be considered an acceptable boration path in 3.1.2.2.
i 7.
Add Appropriate Surveillance Reaut rements to 4.1.2.3 and 4.1.2.4 for the Safety injection Pumps.
8.
The minimum temperature requirements for the RWST be deleted from i
3.1.2.5, 3.1.2.6, and 4.1.2.5 since there is no danger of freezing at PNPP-1.
9.
The SHUT 00WN MARGIN should be promptly detennined upon detection of a stuck control rod ( Action a of 3.1.3.1).
Also note that Action 3.b) could be deleted if other recommended changes associated with SHUTDOWN MARGIN are made. For convenience it is suggested those specification w be made the same as those found in the Standard Technical Specificatwns in NUREG-04 52, Rev. 4 ).
10.
Note that Functional Unit 8 floss of Power) of Table 3.3-3 referenced Action 19; however, the Table Notation for Table 3.3-3 does not include Action 19.
Therefore, add an appropriate Action 19 to Table Notation.
- A generic letter is fonnal correspondence, a mechanism used by USNRC and adopted by the PAEC to communicate with applicants / licensees.
It is formal' because it could be used as a basis for legal actions or sanctions.
It is legally enforceable.
Attached are cocies of Generic Letters referenced in this document.
I C__________--_-_________-____.-___
. y I
- 11. The Table Notation.for Table 3.3-4 includes ' notation (6) which does not appear referenced anywhere on Table 3.3-4.
Either that reference to notation (6') be approximately included on Table 3.3-4 or that notation (6) l l
be deleted from the Table Notation.
I
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- 12. Table 3.3-6 includes several area radiation monitors which may not be required to be included in the PNPP-1 Technical Specifications. Only radiation monitoring instruments required to be included in Table 3.3-6 are those that:
(1) initiate ESF actuations, (2) are used to monitor RCS leakage, (3) are used to monitor for criticality in fuel storage areas, (4).are post accident monitors, and (5) are used for effluent moni tori ng,
i
- 13. Revise Action 30 of Table 3.3-6 to permit alternate means of mcnitoring if the applicable instruments become inoperable. Generic Letter 83-37 l
I is addressed to all Pressurized Water Reactor Licensees. For applicants, it is opportune to have the requirements to be reflected-in the Technical Specifications be done now to preclude the necessity of naving to submit an amendment request in the future.
during plant operation (without requiring reactor shutdown)g can In the change suggested, an alternative means for monitorin q
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3 14 Revise Tables 3./-9 and 4.3-6 to include all the instruments needed to shutdown the reactor from the remote panel. Also modify Tables 3.3-10 I
and 4.3-7 to. list the PNPP-1 instruments.
Revise the entries in Table 3.3-11 (for minimum number of-0PEGABLE fire 15.
detection instruments) to require a specific number (the minimum required number) of fire detection instruments rather than "ALL."
i 16.
The W recommended frequency for performing SR 4.3.4.2.a has _recently been changed from once per 7 days to once per 31 days. Make the same change in PNPP-1 Technical Specifications.
Verify (to' be checked with W) that '3.4.1.2.b which only requires one 17.
Reactor Coolant loop to be In operation in MODE 3 is still a valid assumption and requirement. W recently notified the USNRC that for the l
3-and 4-loop plants at least 2 RC loops must be in operation to prevent l
J ONB during a MODE 3 control rod withdrawal transient Classify 3.4.6.1 to require 3 RCS leakage detection systems be OPERABLt 18.
and that the Action Statement permit operation to continue for up to 30 with only 2 systems OPERABLE. Also classify SR 4.4.6.1.a accordingly.
j 19.
Since the charging pumps are assumed for use in the steam generator tube rupture accident, a limit of 50% of the capacity of one charginq pump should be included in 3.4.6.2 as a limit on CONTROLLEO LEAKAGE.
Al so,
add an appropriate surveillance requirement for thiS l eakage limi t to 4.4.6.2.
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~ WST water maximum limit.o x
in the a
Include in 3.5.5.afor pH control
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Type necessary reduced pressuret cel 20 is conditions.
since of.10 CFR a
been performed an Delete 3.6.1.2.a PP-1'[
not 4.6.1.7 to the P 21.
testaccordance has l
SR in Add LCO 3.6.1.7 andthe tru operated insyste '
acc</
s 22 assure that the plant.can beconta r
allowed to' u Verif y that of the operated without of year) /
use prohibits are 23 plant can beNormally, plants rs per year (1%
/
iodically (once at all.
to 90 hou e tire Naf j
least up n
4.6,2.2.d to peror' NaOH) thru charc Modify water her SR for 24.
(either 4.6.8.1 and all ot8313 units!
ber per Generic Letterand charc j
Modify ils) 25 filtersenclosure for detaic HEPA (See Modify 3.7.9 per Gener 1
modification it changes to the 50.59) by the I i
Th s amendm Snubbers.and would then perm 26 r 10 CFR license
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evaluation (peof required 4.8.1.1.2.a.
number 4 and to Im Modif y ".8,1.1.2.a.
f f Actions numt,
y Sta h
8415, lity, which reduce
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4 Proposed
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y diesel generators 27 overall die 7
on'the/
Reliabi mergency expected to improveand w e
the s
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unnecessary stresaluate theAme reaf is
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s Determine (nd re-evDelet a
4.8.2.3.bmaterial sho ot 28, l
Reevaluate 6.2.3 ric' Table 6.2-1 per Grl 29 ModifyMaintenancersonnel th c/
30, Key more pe frequencies '
ne-change isRe audit Change the This 12 months. consis 31 x-~
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- 32. Modify 6.5.2.10.a.- c to specify to whom. these records are to be forwarded to.
]
- 33. Modify 6.6.1 and 6.9.1' per Generic Letter 83-43.
i
'34 Add 6.7.1.e to state that critical operation of the unit snall be resumed (following a. Safety Limit violation) until authorized by PAEC.
i
- 35. Add 6.8.4.d and e of the W-STS to PNPP-1 6.8.4 i
3 6.- Delete the detailed listing of various Special Reports in 6.9.2 since this listing'is redundant to the requirements spelled out in the' i
individual affected Technical Specifications.
- 37.. Review the proposed technical specifications to verify that the proposed technical specifications can be fully and completely implemented and-
.l' that.the proposed technical specifications accurately reflect the as-built plant and FSAR.
If any differences are detected during this review,
.j they should' be resolved with and approved by PAEC.
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